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D. ID
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t of Abbre
Introducti
Policies anB.1 Manage
B.1.1 B
B.1.2 S
B.2 Spent Fu
B.2.1 N
B.2.2 N
B.3 Radioac
B.3.1 N
B.3.2 N
B.3.3 N
B.3.4 R
B.3.5 L
B.4 Definiti
Scope of AC.1 Radioac
C.2 Reproce
C.3 Naturall
C.4 Radioac
InventorieD.1 Spent F
D.1.1 N
D.1.2 N
D
eviations
ion ······
nd Practicement Policy
Basic Policy
Strategy and
uel Manage
Nuclear Pow
Nuclear Res
ctive Waste
Nuclear Pow
Nuclear Res
Nuclear Fue
RI Waste M
LILW Dispo
on and Clas
Applicatioctive Waste
essing of Sp
ly Occurrin
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es and LisFuel Manage
Nuclear Pow
Nuclear Res
············
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y ···········
d Manageme
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wer Reactor
search Facil
Manageme
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search Facil
el Fabricatio
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ssification o
on (Articlwithin the
pent Fuel ·
g Radioacti
s within Mi
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wer Reactor
search Facil
Table
············
cle 32, Paroactive Wast
·············
ent Plan ··
tices ······
r Facility ·
lity ········
ent Practices
r Facility ·
lity ········
on Facility
Facility ··
y ··········
of Radioacti
le 3) ·····Scope of th
·············
ive Material
ilitary or De
le 32, Par·············
r Facilities
lities ······
e of Con
············
ragraph 1te and Spen
··············
··············
··············
··············
··············
s ···········
··············
··············
·············
··············
··············
ive Waste
············he Joint Con
··············
ls ··········
efense Progr
ragraph 2··············
·············
··············
ntents
············
1) ········nf Fuel ····
·············
·············
·············
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·············
·············
·············
·············
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·············
·············
·············
············nvention ··
·············
·············
rams ······
2) ·······················
·············
·············
··········
·········· ············
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············
············
1
7 9
9
10
12
12
13
14
14
15
15
16
16
18
19 22
22
22
22
25 25
25
26
D
D
D
E. LE
E
E
F. O
F
D.2 Radioac
D.2.1 N
D.2.2 N
D.2.3 N
D.2.4 R
D.2.5 L
D.2.6 O
D.3 Decomm
D.3.1 K
D.3.2 U
D.4 Record
LegislativE.1 Implem
E.2 Legislat
E.2.1 L
E.2.2 N
E.2.3 L
E.2.4 R
E.2.5 E
E.2.6 A
E.2.7 C
E.3 Regulat
E.3.1 A
E.3.2 SO
E.3.3 R
Other Gen
F.1 Respons
F.1.1 MH
F.1.2 U
ctive Waste
Nuclear Pow
Nuclear Res
Nuclear Fue
RI Waste M
LILW Dispo
Others ·····
missioning
KRR-1 and
UCF ·······
Keeping an
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tive and Reg
Legislative F
Nuclear Reg
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Regulatory I
Enforcemen
Allocation o
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ory Body ·
Authority an
Structure anOrganization
Regulatory I
neral Safe
sibility of th
Mechanism Holder will
Ultimate Re
Manageme
wer Reactor
search Facil
el Fabricatio
Management
osal Facility
··············
············
2 ··········
··············
nd Reportin
gulatory Fasures ·····
gulatory Fra
Framework
gulatory Fra
ystem and S
Inspections
nt ···········
of Responsib
··············
··············
nd Responsi
nd Resourcens ·········
Independen
ety Provis
he License H
for the RegMeet its Pri
sponsibility
Table
ent Facilitie
r Facilities
lity ········
on Facility
t Facility ·
y ··········
·············
·············
·············
·············
ng ··········
Framewo·············
amework
of Nuclear
amework ·
Safety Evalu
···········
·············
bility ·····
·············
·············
ibility of the
es of the Reg·············
nce ········
sions ····
Holder ···
gulatory Bodimary Resp
y ···········
e of Con
es ··········
·············
··············
···········
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··············
··············
··············
··············
ork ·····················
··············
r Regulation
··············
uation ·····
··············
··············
··············
··············
··············
e Regulator
gulatory Bo··············
··············
············
··············
dy to Ensuronsibility fo
··············
ntents
·············
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n ···········
·············
·············
·············
·············
·············
·············
·············
ry Body ···
ody and Sup·············
·············
············
·············
e that the Lor Safety ·
·············
·············
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·············
·············
·············
pporting ·············
·············
···········
·············
License or Pe·············
·············
28
28
29
29
30
30
31
32
32
32
33
35 37
37
38
46
48
49
50
51
51
52
52
53
61
63
65
ermit 65
66
F
F
F
F
F
F.2 Human a
F.2.1 N
F.2.2 N
F.2.3 N
F.2.4 L
F.2.5 R
F.2.6 SR
F.3 Quality A
F.3.1 Q
F.3.2 Fr
F.3.3 Im
F.3.4 R
F.4 Operatio
F.4.1 R
F.4.2 RN
F.4.3 R
F.4.4 ImUF
F.5 Emergen
F.5.1 R
F.5.2 N
F.5.3 T
F.5.4 E
F.5.5 In
F.6 Decomm
F.6.1 R
F.6.2 H
F.6.3 R
F.6.4 E
F.6.5 R
and Financi
Nuclear Pow
Nuclear Rese
Nuclear Fuel
LILW Dispo
RI Waste Ma
ecuring of FRadioactive
Assurance
QAP ········
ramework o
mplementat
Regulatory A
onal Radiati
Regulations
Radiation PrNuclear Pow
Restriction o
mplementatUnplanned/UFacility ····
ncy Prepare
Regulations
National Rad
Training and
Environment
nternational
missioning
Regulations
Human and F
Radiation Pr
Emergency R
Record Keep
ial Resource
wer Reactor
earch Facili
l Fabrication
osal Facility
anagement F
Financial RWaste Disp
·············
··············
of QAP ···
ion and Ass
Activities ·
ion Protectio
and Require
otection Frawer Utilizati
on Release f
ion of ComUncontrolle··············
edness ·····
and Require
diological E
d Exercises
tal Radioact
l Arrangeme
·············
and Require
Financial R
otection ··
Response ·
ping ·······
Table
es ·········
Facilities
ities ·······
n Facility
y ···········
Facility ··
Resources foposal Facilit
·············
·············
·············
sessment of
·············
on ········
ements ···
amework ation Facility
from a Nucl
mplementaryed Release fr·············
·············
ements ···
Emergency R
············
tivity Moni
ents ·······
·············
ements ···
Resources ·
·············
·············
·············
e of Con
··············
··············
··············
··············
··············
··············
or Managemty ··········
··············
··············
··············
f QAP ·····
··············
··············
··············
t Each Stage ············
lear Power U
y Measures from a Nucl··············
··············
··············
Response ·
··············
toring ·····
··············
··············
··············
··············
··············
··············
··············
ntents
·············
·············
·············
·············
·············
·············
ment after th·············
·············
·············
·············
·············
·············
·············
·············
e of Manage·············
Utilization F
against ear Power U·············
·············
·············
·············
·············
·············
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············
············
············
he Closure o············
············
············
············
············
············
············
············
ement of ············
Facility ·
Utilization ············
············
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············
············
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· 67
67
70
72
73
75
of a 75
76
76
77
77
78
80
81
84
88
91
92
92
93
97
98
100
102
103
104
104
105
106
G. SG
G
G
G
G
G
G
Safety of SG.1 General
G.1.1 N
G.1.2 M
G.1.3 I
G.1.4 P
G.1.5 I
G.2 Existing
G.2.1 O
G.2.2 S
G.3 Siting o
G.3.1 O
G.3.2 S
G.3.3 C
G.4 Design
G.4.1 C
G.4.2 D
G.4.3 P
G.5 Assessm
G.5.1 S
G.5.2 S
G.6 Operatio
G.6.1 O
G.6.2 O
G.6.3 Tm
G.6.4 R
G.6.5 I
G.6.6 D
G.7 Disposa
Spent Fuel Safety Req
Nuclear Crit
·············
Minimizatio
Inter Depen··············
Protective A
Impacts and
g Facilities
On-site Spen
Spent Fuel I
of Proposed
On-site Spen
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Consideratio
and Constru
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Decommissi
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Supplement
on of Facili
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Technical Sumonitoring,
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ticality, Res
··············
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rk ·········
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t Assessmen
·············
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on ·········
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·············
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l Material
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············
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nt ········
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maintenance············
············
············
············
············
107 109
· 110
110
ment 110
110
111
112
112
112
113
113
114
114
115
115
116
116
118
118
119
120
120
121
e, 122
123
123
123
124
H. SH
H
H
H
H
H
Safety of RH.1 General
H.1.1 S
H.1.2 S
H.1.3 S
H.2 Existing
H.3 Siting o
H.3.1 R
H.3.2 S
H.4 Design
H.4.1 R
H.4.2 C
H.4.3.
H.5 Safety A
H.5.1 S
H.5.2 R
H.5.3 IA
H.6 Operati
H.6.1 R
H.6.2 S
H.6.3 L
H.6.4 O
H.6.5 E
H.6.6 P
H.6.7 E
H.6.8 A
H.6.9 EA
Radioactil Safety Req
Standards fo
Safety Anal
Safety Requ
g Facilities
of Proposed
Regulatory
Site Selectio
and Constru
Regulatory
Criteria of D
Implementa
Assessment
Safety Anal
Renewal of
ImplementaAssessment
on of Facili
Regulatory
Safety Mana
Limiting Co
Operating P
Engineering
Procedure fo··············
Event Repor
Analysis an
EstablishmeAuthority ·
ive Wastequirements
or Permit of
ysis ·······
uirements to
and Past Pr
Facilities
Requiremen
on for the P
uction of Fa
Requiremen
Design and C
ation of Reg
t of Facilitie
ysis and En
Safety Ana
ation of Safeof the LILW
ities ·······
Requiremen
agement of
onditions of
Procedures
g and Techn
for Characte··············
rting and R
d Incorpora
ent of a Dec··············
Table
e Manage ············
f Constructi
·············
o be conside
ractices ···
·············
nts and Perm
Proposed Fa
acilities ··
nts ········
Constructio
gulatory Re
es ·········
nvironmenta
alysis and R
ety AssessmW Dispoasl
·············
nts ········
f Operation o
f Operation
·············
nical Suppor
erization and·············
Record Mana
ation of Ope
commission·············
e of Con
ement ·················
ion and Ope
··············
ered ·······
··············
··············
mit Procedu
cility ······
··············
··············
on ··········
equirements
··············
al Impact A
Reassessmen
ment and Ral Facility ··
··············
··············
of a Dispos
of a Dispos
··············
rt ··········
d Categoriz··············
agement ··
erating Expe
ning Plan an··············
ntents
·························
eration ····
·············
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·············
ure ········
·············
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·············
···········
·············
ssessment
nt of Safety
adiological E·············
·············
·············
al Facility
sal Facility
·············
·············
ation of Rad·············
·············
erience ···
nd Review o·············
·········· ·············
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Environmen·············
·············
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············
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·············
dioactive W·············
·············
·············
of the Regul·············
125 127
128
128
129
132
134
134
136
138
138
139
141
145
145
147
ntal 148
149
150
150
151
151
152
Waste 152
152
153
latory 154
H
I. TI
I
I
J. DJ
J
H.6.10
H.6.11
H.7 Instituti
H.7.1 R
H.7.2 In
H.7.3 In
rans-bou.1 Domestic
.2 Safety R
I.2.1 G
I.2.2 Tr
I.2.3 Tr
.3 Approva
I.3.1 D
I.3.2 Re
I.3.3 Tr
Disused SeJ.1 Legal Sy
J.2 Managem
J.2.1 R
J.2.2 M
J.2.3 R
EstablishmAuthority
ImplementDisposal F
onal Measu
Record Keep
nstitutional
ntervention
ndary Moc Transport
equirement
eneral Requ
ransport Co
ransport ···
al and Admi
esign Aprov
eport on Tra
rans-bounda
ealed Sourystem ······
ment of disu
equirement
Management
eturn ······
ment of a Clo ·············
tation of Safacility ····
ures after Cl
ping ······
Control ··
n in Case of
ovement (Regulation
s ··········
uirements
ontainers ··
··············
nistrative A
val ········
ansport ···
ary Movem
rces (Arti··············
used sealed
s for Facilit
t ···········
··············
Table
osure Plan a·············
fety Regula·············
losure ····
·············
·············
Unplanned
(Article 2ns ··········
·············
·············
·············
·············
Action ····
·············
·············
ment Cases
icle 28) ··············
sources ··
ties and Han
·············
·············
e of Con
and Review··············
ations on Pa··············
··············
··············
··············
d Release ··
27) ·····················
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··························
··············
ndling ·····
··············
··············
ntents
w of the Regu·············
rtial Operat·············
·············
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ulatory ············
tion of a ············
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154
154
156
156
157
158
159 162
164
164
164
164
165
165
165
165
167 169
170
170
170
171
K. P
K
K
K
K
K
K
ANNA
A
A
A
A
A
A
A
Planned AK.1 Measure
········
K.2 TechnolManage
K.3 Prepara
K.4 Spent F
K.5 Enhance
K.6 Integrat
NEXES Annex A Li
Annex B Li
Annex C Li
Annex D Nu
Annex E Nu
Annex F No
···
Annex G No
·····
Annex H Re
Activities es Taken to
··············
logy Improvement ·····
ation of Dec
Fuel Manage
ement of Sa
ted Regulato
···········st of Spent
st of Radioa
st of Nuclea
uclear Safet
uclear Safet
otices of the
··············
otices of the
··············
eferences ·
to Improo Challenges
··············
vement of t··············
ommissioni
ement Polic
afety of a LI
ory Review
············Fuel Manag
active Wast
ar Facilities
ty Charter
y Policy Sta
e NSSC App
··············
e MOTIE A
··············
··············
Table
ove Safetys Identified
·············
the Regulato·············
ing of NPPs
cy ·········
ILW Dispo
w Service M
············gement Fac
te Managem
s under Dec
·············
atement ··
plicable to R
·············
Applicable to
·············
·············
e of Con
y ··········at the Prev
··············
ory Systems··············
s ············
··············
sal Facility
ission ·····
············cilities ·····
ment Faciliti
ommissioni
··············
··············
Radioactive
··············
o Radioactiv
··············
··············
ntents
············ious Review
·············
s for the Ra·············
·············
·············
············
·············
·························
ies ·········
ing ········
·············
·············
e Waste Man
·············
ve Waste M
·············
·············
·········· w Meeting
············
adioactive W············
············
············
············
············
·········· ············
············
············
············
············
nagement
············
Management
············
············
173
175
Waste 177
178
179
180
181
183 185
187
192
193
194
201
t
206
207
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
Tabl
le D.1-1 I
le D.1-2 I
le D.2-1 I
le D.2-2 I
le D.2-3 I
le D.2-4 I
le D.2-5 I
le D.3-1 ID
le E.2-1 L
le E.2-2 C
le F.4-1 D
le F.4-2 AR
le F.4-3 AR
Inventory of
Inventory of··············
Inventory of
Inventory of
Inventory of
Inventory of
Inventory of
Inventory ofDecommiss
Laws Conce
Contents of
Dose Limits
Annual RadiReleased fro
··············
Annual RadiReleased fro
··············
f Spent Fue
f Spent Fue··············
f Radioactiv
f Radioactiv
f Radioactiv
f RI Waste
f the LILW
f Radioactivioning Site
erning Nucl
Nuclear Sa
s ···········
ioactivity inom Nuclear
··············
ioactivity inom Non-Nu
··············
Lis
els Stored at
els in Storag·············
ve Waste St
ve Waste St
ve Waste St
Stored by th
Disposal F
ve Waste St ············
lear Safety R
afety Act ·
·············
n Liquid andPower Site
·············
n Liquid anduclear Power
·············
st of Tab
t NPP Sites
ge Pools of R··············
tored at NPP
tored at the
tored by the
he KORAD
Facility ····
tored at the ··············
Regulation
··············
··············
d Gaseous Res and Calcu
··············
d Gaseous Rr Site and C
··············
bles
············
Research Re·············
P Sites ···
KAERI ··
e KEPCO N
D ···········
·············
KRR-1 and·············
············
·············
·············
Radioactiveulated Off-s
·············
RadioactiveCalculated O
·············
·············
Reactor Facil·············
·············
·············
NF ·········
·············
·············
d 2 ·············
·············
·············
·············
e Effluents site Dose
·············
e Effluents Off-site Dos
·············
· 26
lities · 27
· 28
· 29
· 30
· 30
· 31
· 32
· 39
· 42
· 82
·· 90
se
·· 90
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
Figu
ure A.1-1 LG
ure B.2-1 S
ure E.2-1 L
ure E.2-2 L
ure E.2-3
ure E.3-1 O
ure E.3-2 O
ure F.2-1 O
ure F.2-2 O
ure F.2-3 R
ure F.2-4 O
ure F.2-5 O
ure F.5-1 N
ure F.5-2 AE
ure F.5-3 N
ure H.4-1 B
ure H.4-2 C
ure H.6-1 R
ure J.2-1 R
Locations anGeneration
Spent Fuel M
Legal Frame
Legal Hiera
Organization
Organization
Organization
Organization
Radioactive
Organization
Organization
National Ra
Atomic ComEmergency
National En
Bird’s Eye V
Cross Sectio
Radioactive
RI Waste M
nd OperatioSources and
Managemen
ework for N
rchy of the
·········
n Chart of t
n Chart of K
n Chart of t
n Chart of a
Waste rela
n Chart of K
n Chart of K
adiological E
mputerized T(AtomCAR
nvironmenta
View of the
on View of
waste carri
Management
List
onal Status od Managem
nt Practices
Nuclear Safe
Radioactiv
·············
the NSSC ·
KINS ·····
the KHNP H
a Nuclear P
ated Organiz
KEPCO NF
KORAD ·
Emergency
Technical ARE) ········
al Radioacti
e Wolsong L
Undergroun
ier ········
t System ··
t of Figu
of Major Rament Facilitie
············
ety Regulati
e Waste Ma
··············
··············
··············
Head Office
ower Site
zation Chart
F ···········
··············
Response S
Advisory Sy··············
vity Monito
LILW Dispo
nd Facilitie
··············
··············
ures
adioactive Wes ·········
·············
ion ········
anagement A
·············
·············
·············
e ···········
·············
t of KAERI
·············
·············
Scheme ···
ystem for th·············
oring Netwo
osal Center
s ··········
·············
·············
Waste ·············
·············
·············
Act ·······
·············
·············
·············
·············
·············
I ···········
·············
·············
············
he Radiologi·············
ork ······
···········
·············
·············
·············
· 5
· 12
· 41
· 45
· 47
· 54
· 60
· 68
· 69
·· 70
· 73
· 74
95
ical · 96
100
· 143
· 143
· 163
· 171
AA. Int
- 1 -
troduuction
- 2 -
The gfosteCurregene
Sincethe lnucleaccorunitsconst In OComKoreCorp2009for tWastin Juradioconstcomp In thgoveinterimanaand perspComManaon S2013
governmentering nucleaently, nuclration in Ko
e the commlatest commear power rdance with
s of NPPs intruction are
October 201mmission (Nean governporation (KR9 pursuant tthe safe andte Managem
uly 2013. Cuoactive wastruction andpleted at the
e 253th meeernment decim-storage agement aftto implemepective. In t
mmission in agement Plpent Nucle
3 to carry
t of the Repar power tolear power orea.
mencement omercial opeplants (NPh the 6th Bancluding five planned to
1, the KoreNSSC) to ennment also RMC), whito the provid efficient
ment was reurrently, thete (LILW) d operatione end of 201
eting of Atocided to confacility. It w
fter due conent the polithis line, the
Novemberan which car Fuel Ma
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accounts
of the commeration of SPs) are opeasic Plan fove units und be construc
ean governnhance the
establisheich is a radisions of thmanageme
enamed intoe KORAD hdisposal fa, and the ph14.
omic Energynstruct a LILwas also decnsideration icy based oe Korean gor 2012 andalled for es
anagement aic engagem
A. In
- 3 -
orea has mathe insuffi
for approx
mercial opeShin-Wolsoerating comor Long-termder construccted by 202
nment estabregulatory
ed the Kordioactive w
he Radioactient of radioo the Korea has been coacility sincehase 1 cons
y CommissiLW disposacided to detof technolo
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blished the y independerea Radioa
waste managive Waste M
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e the governstruction of
ion held in Dal facility, stermine a nogy developconsensus fheld the 2nd
on the Exect of a Publiendent adviities. When
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Kori Unit 1 in July 20as of Marty Supply aour units be
Nuclear Saence of nucactive Wasgement ageManagemente. The Koe Waste Aga low and innment granthe disposa
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from the mid meeting ofcution Planc Engagemisory body n the Publ
national polis in the coutotal elect
in April 19012, 23 unrch 31, 201and Demaneing prepare
afety & Secclear safetyste Manageency, in Jannt Act (RWorea Radioagency (KORntermediatented a permal facility w
2004, the Kfrom a spenicy for spenome and ab
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Korean nt fuel nt fuel broad
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- 4 -
Commission’s recommendation report based on the results of public engagement activities that the commission is currently carrying out, the Korean government will decide on a national policy for spent fuel management and develop a basic plan for radioactive waste management by the end of 2014 according to this national policy for spent fuel. Spent fuel generated from operating NPPs has been stored in spent fuel storage pools or dry storage facilities (only applies to PHWRs) on site and LILW generated from NPPs has been stored at on-site radioactive waste storage facilities. Currently only one research reactor is in operation: High-flux Advanced Neutron Application Reactor (HANARO) at the Korea Atomic Energy Research Institute (KAERI) located in Daejeon. Operation of HANARO commenced in 1995 and HANARO has the thermal power of 30MW. Spent fuel as well as radioactive waste generated from HANARO has been stored in an on-site storage facility. Two research reactors, Korea Research Reactor 1 and 2 (KRR-1 and 2), located at the former the KAERI site in Seoul, were permanently shut down, and the decommissioning of the reactors and the auxiliary facilities are currently underway. Fuel for NPPs is fabricated by Korea Electric Power Corporation Nuclear Fuel (KEPCO NF) in Daejeon. Radioactive waste generated from fabrication process is stored in the on-site radioactive waste storage facility. In addition, as of late December 2013, the number of radioactive material users in medicine, research and industry has increased steadily to nearly 6,100. They are located throughout the country and generate various types of radioactive waste. The radioactive isotope (RI) waste generated from these facilities is stored in the RI waste management facility of the KORAD in Daejeon. The locations and operational status of major radioactive waste generation sources and management facilities in Korea are shown in Figure A.1-1.
Figure A.1-1. Lo
Socations andSources and
d Operationd Managem
- 5 -
nal Status oment Faciliti
of Major Rades (As of M
dioactive WMarch 31, 20
Waste Gener014)
ration
In shPathesh
B.1.1 The the “Atomnatio 1) Di
- u
2) Sa
- Rat
-
B
ARTICLE
accordancall submit
arties. Thise obligatioall also ad
spent fu spent fu radioact radioact criteria u
1 Basic Pol
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irect managRadioactiveunder the re
afety on TopRadioactiveand environthe harmfulRadioactive
B.1
E 32. REPO
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uel manageuel managetive waste tive waste used to de
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sic policy foe Waste MaCommittee
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ORTING
e provisionnal report all address Conventio
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efine and ca
or radioactivanagement e (AEC) hes:
he governmhich needs y of the gov
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- 9 -
ns of ARTto each
s the meason. For ea
cy; ctices;
ment policy;ment practic
ategorize r
ve waste anPlan” whic
eld on Sept
ment long-term
vernment.
ly managedo protect huve waste, should be o
ICLE 30, eReview M
sures takeach Contra
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nd spent fuch was adoptember 30,
safe manag
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el managempted in the 21998. The
gement, sho
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tracting Paf Contractment eachrty the rep
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ould be man
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arty ting h of port
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naged
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on the
- 10 -
safety. 3) Minimization of radioactive waste generation
- The generation of radioactive waste which accompanies the use of nuclear power and RI should be minimized.
4) “Polluter pays” principle
- The cost incurred in managing radioactive waste should be borne by the generator at the point of generation, without imposing undue burdens on future generations.
5) Execution under the public trust
- Radioactive waste should be managed transparently and openly so as to improve the understanding and trust of the general public
- Radioactive waste management project should be executed in such a way to contribute to harmony and development of local communities.
B.1.2 Strategy and Management Plan B.1.2.1 LILW The disposal of LILW was adopted as a management plan in 1986. In particular, the AEC decided on construction of a LILW disposal facility with the capacity of 800,000 drums (100,000 drums in the 1st stage) in the 253th meeting held in December 2004. Accordingly the construction of 1st stage facility (Rock Cavern Disposal Type) commenced in 2007 with the completion target of late 2014. B.1.2.2 Spent Fuel Discussion on a strategy and management plan for spent fuel started in the AEC in 1988. Afterward, the construction and operation of a spent fuel interim storage facility (either wet- or dry-type) was decided several times as a strategy and management plan for spent fuel by the AEC. In the 253th meeting held in December 17, 2004, however, the committee changed its position to increase the capacity of temporary storage facilities of NPPs to manage spent fuel on site by 2016 and to establish spent fuel management plan after consideration of a national policy direction, technology development at home and abroad, and based on public consensus reached through the discussion from a mid- to long-term perspective. Afterward, the Atomic Energy Commission decided on the “Execution Plan for Spent Fuel Management Policy” in the 2nd meeting held on November 20, 2012 and setting a direction for developing a spent fuel management plan as follows: (1) put safety first (2) develop short-, mid- and long-term management plans (3) prepare supporting measures
- 11 -
which can be accepted by the general public to ease the burden borne by future generations and local residents. At the same time, it was decided to form and run a Public Engagement Commission on Spent Nuclear Fuel Management so as to develop a management plan while securing the highest possible level of acceptance. On October 30, 2013, the Public Engagement Commission on Spent Nuclear Fuel Management was lunched and embarked on public engagement activities with an aim of presenting recommendations on the method for managing spent fuel to the government by late 2014. Therefore, a national policy, strategy and management plan for spent fuel will be presented in detail in the Basic Plan for Radioactive Waste Management where the results of above-mentioned public engagement activities will be incorporated.
Spenand rsumm
B.2.
Spenhavepoint
Spenfuel pto ad
B
nt fuels in Kresearch reamarized as s
1 Nuclear
nt fuels gen been implet of on-site
nt fuels genpool for eacddress the
Pressurize
B.2 Sp
Korea are gactor, HANshown in Fi
Figur
r Power Re
erated fromemented to storage faci
nerated in thch unit. To lack of sto
ed Water R
pent Fue
generated frNARO. The igure B.2-1.
re B.2-1. Spe
eactor Fac
m NPPs are increase onilities.
he Pressurizdate, almos
orage capac
Reactor (PW
l Manage
- 12 -
rom 23 NPPKorea’s fra.
ent Fuel Man
cility
stored and n-site storag
zed Water Rst all PWR pity such as
WR)
ement Pra
Ps located amework fo
nagement Pra
managed oe capacity o
Reactors (Pplants contis installing
actices
in four nucor spent fue
actices
on site and or to postpo
PWRs) are sinue to implstorage rac
clear powerel managem
diverse meone the satur
stored in a lement meacks addition
r sites ment is
ethods ration
spent
asures nally,
instaother
SpenWolsthen constand cplace400) Febru B.2.
All o1998
Spenstore
Someexam(PIEFin thein ro
alling high-dr neighborin
nt fuels gensong Units transferred tructed in Wcurrently a e. Additiona
with the cuary 2011 a
2 Nuclear
of the 299 s8 when the d
nt fuels fromed in the spe
e spent fumination areF) which ise PIEF hot d-cut conta
Pressurize
KRR-1 an
HANARO
Post-irrad
density storng units.
nerated in 1, 2, 3 and to the dry s
Wolsong sitetotal of 300ally, seven capacity of and are curr
r Research
spent fuel rdecommissi
m operationent fuel poo
fuels genere stored in currently rcells, and thiners and st
ed Heavy W
d 2
diation Exam
age racks o
Pressurize4, are storestorage facie in 1992 an0 canisters (modules of
f 168,000 brently in ope
h Facility
rods from Kioning proje
n of HANAl connected
rated and the storage
run by the Khe remainintored in the
Water Reac
mination Fa
- 13 -
or transferrin
d Heavy Wed in spent fility on site.nd expande(with the tof MACSTObundles wereration.
KRR-1 and ect of the re
ARO and irrd to the reac
transshippee pool of thKAERI. Posng part of thspent fuel p
ctor (PHWR
acility (PIEF
ng spent fu
Water Reacfuel pools fo Initially, 6d three time
otal capacityR-400 (More construct
2 were sensearch reac
radiated tesctor pool of
ed from Phe post-irradst-irradiationhe fuel rodspool.
R)
F)
els to the sp
ctors (PHWfor longer th0 dry storages (in 1998,y of 162,000dular Air-Cted in the W
nt back to ttors was un
t fuels fromHANARO.
PWRs for diation examn examinatiafter exami
pent fuel po
WRs) whichhan six yearge canisters, 2002 and 20 bundles) a
Cooled STOWolsong s
the USA inndertaken.
m HANARO.
post-irradimination faion is carrieination is pa
ool of
h are rs and were 2005) are in
ORage ite in
n June
O are
iation acility ed out acked
B.3.
Gasedurintreateinto Gasehigh-undewithidefinand r
Liquof thwith efflualso liquidcalcu
Solidpapefilterdrumusingwastewastetime compstabithe c
B
1 Nuclear
eous radioacng the opered using a gthe atmosp
eous waste f-efficiency
er continuouin the Excluned in the Nreport the re
uid radioactihe reactor co
evaporatoruent is releas
under contd effluent dulate off-site
d radioactivrs, clothes,
rs. The DAWms. For Hang a “LILW Ve from Hane and spentin the past
pletely drieilization waconcentrated
B.3 Ra
Gaseous R
Liquid Rad
Solid Rad
r Power Re
ctive waste ration of NPgas decay taphere after from the veparticulate
us monitorinusion Area
Notice of theesults regula
ive waste isoolant and rrs, deminerased to the setinuous modischarged e dose estim
ve waste co gloves, shWs are comnul Units 5Vitrification
nul Units 5 at resin had (~ 1995); a
ed in a dryis discontinud waste, wh
adioactiv
Radioactive
dioactive W
ioactive Wa
eactor Fac
is mainly gPPs. Gaseoank or charcconfirming
entilation syfilters and cng. The gasBoundary (e NSSC. Tharly to the r
s mainly gerelated systealizers, filteea when me
onitoring. Tinto the en
mates and re
onsists moshoes, etc.) ampressed by5 and 6, con Facility.” and 6 has bbeen solidiafterward, ting facility ued considehich is gene
ve Waste
e Waste Ma
Waste Mana
aste Manag
- 14 -
cility
generated inous waste gcoal delay bg radioactivystems is dicharcoal filtseous efflue(EAB) shouhe licensee sregulatory b
enerated froems. In geners and/or reasured rad
The Notice nvironment eport the res
stly of Dryand concen
y a conventiombustible
Thanks to teen reducedfied mainly
the concentry and stabilering the staerated newl
Manage
anagement
agement
gement
n the deaerenerated in
bed to reducvity levels scharged inters, and its ent being re
uld satisfy Eshould calcu
body.
om the cleanneral, liquid reverse osmioactivity leof the NSSwithin the
sults regular
y Active Wntrated wasional compamiscellaneothat, the vold by approxy with cemerated waste ized with p
ability of perly in the NP
ment Pra
t
ration or venn the deaerace radioactivthrough sam
nto the envirradioactivit
eleased intoEffluent Conulate off-sit
nup or mainradioactive
mosis (RO) evel is belowSC prescribEAB. The
rly to the re
Wastes (DAtes, spent ractor (capacous solid wlume of mis
ximately 90%ent during agenerated f
paraffin. Hormanent disPPs, is pack
actices
entilation pration procesvity and relmpling anaronment thrty levels are
o the atmosntrol Limit te dose estim
ntenance pre waste is tr
equipmentw ECL, whbes ECL fo
operator shegulatory bo
AWs, used resins and city: 30 tonwaste is vitscellaneous%. Concenta fixed perifrom NPPs owever, pasposal as of ked in the H
rocess ss are eased
alysis. rough e also phere (ECL) mates
rocess reated t. The hich is or the hould
ody.
parts, spent
n) into trified solid trated iod of were
raffin f 2011, High-
Integspent B.3.
The vreleasysteventi
Liqufacilinaturthe e
Solidtreatmwith concdose Comurani B.3.
Any filterstackexceethe li
grity Contait resin dryin
2 Nuclear
ventilation ase into theem. When tilation is sto
uid radioactiities and derally evapor
environment
d radioactivment and sta high rad
rete monoliis compres
mbustible waium conver
3 Nuclear
radioactiver in the ventk. Gaseous reds the reguimits.
Gaseous R
Liquid Rad
Solid Rad
Gaseous R
iner (HIC). ng system. S
r Research
system of ee atmospherthe radioacopped to kee
ive waste geelivered to arated and tht.
ve waste, extorage facilidiation doseith with adessed and paaste generatsion facility
r Fuel Fab
e material frtilation systradioactive ulatory limi
Radioactive
dioactive W
ioactive Wa
Radioactive
Spent resin Spent filters
h Facility
each facilityre. The stactivity conceep off-site e
enerated froan evaporatihe residue i
xcluding spities. Accorde are packeequate shielcked in 200ted in the dy (UCF) is i
rication Fa
rom gaseoutem before effluent is
its ventilatio
e Waste Ma
Waste Mana
aste Manag
e Waste Ma
- 15 -
is kept in as are stored
y is equippedcks of eachentration oexposure do
om researchion plant fois bituminiz
pent fuel, iding to inted in 50-lite
lding. Solid 0-liter steel
decommissioincinerated.
acility
us radioactivits release tcontinuous
on is stoppe
anagement
agement
gement
anagement
an HIC or eqin a shieldi
d with filterh facility hf off-gas ex
ose below th
h facility is or concentrazed, no liqu
s transporteernal guidelier stainless radioactivedrums, and
oning proce
ve effluent to the outsidsly monitoreed to keep o
t
t
quivalent afing containe
rs to treat ofhave continuxceeds effluhe limits.
collected ination. Becauuid waste is
ed to the raines, solid rsteel drum
e waste withd kept in a sess of KRR-
should be tde environmed. If the raoff-site expo
fter drying ier.
ff-gas prior uous monitluent limita
n the tanks ouse condenss discharged
adioactive wradioactive w
ms, and kepth a low radistorage buil
R-1 and 2 an
treated throument througadioactivity osure dose b
in the
to its toring
ations,
of the sate is d into
waste waste t in a iation lding. nd the
ugh a gh the
level below
LiquPHWlime charaby thdisch
Solidclothdurinsynthare tsurfa B.3.4
RI uwasteRI wusersfacili B.3.
The LILWusers
The will b
uid waste is WR fuel fab
precipitatiacteristics. The Notice harged is rec
d waste fromhes, gloves,ng liquid whetics, limethen stored ace contami
4 RI Waste
users utilize e is classifie
waste generas or transpoity.
5 LILW Dis
LILW dispW generateds, etc.
total capacibe disposed
Liquid Rad
Solid Rad
Radioactiv
Disposal C
classified ibrication proon, polymeTreated liquof the NSScorded and
m fuel fabri, metals ge
waste treatm deposits, win a waste
nation level
e Manage
two kinds ed into comated by RI ort agents. T
sposal Fa
posal facilid from NPP
ity of the Ld in the first
dioactive W
ioactive Wa
ve Waste fo
Capacity
nto two typocess. Theyer coagulatiuid waste isSC and datmaintained
cation facilienerated durment. They wood, glasse storage fal, and radiat
ment Faci
of RI: sealmbustibles, i
users, are cThe KORAD
cility
ity, which Ps, research
LILW dispot phase of th
Waste Mana
aste Manag
or Disposal
- 16 -
pes: waste fy are treatedion and ces dischargeta such as
d.
ities consistring facilityare classif
s, etc., and pfacility aftertion dose ra
ility
led source incombustibcollected anD manages
is currentlyfacilities, n
osal facility he disposal f
agement
gement
l
from PWR fd by severalentrifugationed after com
volume an
ts mostly ofy repair, anfied into mpacked in 2r measuringate for each
and unsealebles, non-cond delivered RI waste i
y under conuclear fuel
is 800,000facility.
fuel fabrical treatment n in accord
mpared withnd amount
f protective nd lime depiscellaneou
200-liter steg the radiopackage.
ed source. Uompactable,d to the KOn its RI wa
nstruction, fabrication
0 drums and
ation processystems su
dance with h ECLs spec
of liquid w
supplies sueposits geneus waste, meel drums, woactivity, w
Unsealed s, spent filterORAD by thaste manage
will dispon facilities an
d 100,000 d
ss and uch as
their cified waste
uch as erated
metals, which eight,
ource rs, etc. he RI ement
ose of nd RI
drums
LILWwaste9-pacplacesuch
W will be de. For loadick (3×3) died inside thas a crane.
Disposal M
disposed ining efficiencisposal cone disposal c
Method
n six silos dcy, 16-pack
ntainers for containers, w
- 17 -
depending k (4×4) disp
320-liter dwhich are h
on the sizeposal containdrums are uhandled with
e and charaners for 200used. The wh remote co
acteristics o0-liter drumwaste drumontrol equip
of the
ms and ms are pment
C.
The NotherwhicradioconcLow than in the
-
- LILWNSANoticdispovery intermradiowasteClass Exemself-dIAEAyear
B
Nuclear Sar materials cch is all subjoactive waentration anand intermthe HLW. e NSSC No
- radioact
- heat gen
W is definedA and the d
ce No. 2014osal). Acco
low level mediate lev
oactivity lime managemsification).
mpt waste adisposal in A Safety Sefor individu
B.4 De Sco
afety Act (Ncontaminateject to disp
aste (HLWnd the heat
mediate levelThe limit v
otice No. 20
tivity: ≥ 4l
neration rate
d to be catedetails regar4-003 (Radrding to thradioactive
vel radioactimit are dev
ment in Kore
according tthe NSA
eries No. 1ual dose and
efinition ope
NSA) defineed by such rosal. The E
W) as the release rat
l radioactivevalues on ra013-49 (Stan
4,000 Bq/glonger thane: ≥ 2 kW
egorized by rding LILW
dioactive Wae Notice, Le waste (Vive waste (I
veloped by ea and the I
o the IAEAand subord15 (1996) ad less than 1
and Clas
- 18 -
es “Radioacradioactive
Enforcementradioactive
te are highee waste (LILadioactivityndards for R
g for α-emi20 years
W/m3
its radioactW sub-categ
aste ClassifLILW is cla
VLLW), lowILW). Thisconsidering
IAEA Safet
A radioactivdinate statutare applied 1 person-Sv
ssification of
ctive Wastematerial (in
t Decree of e waste, oer than leveLW) means
y and heat gRadiation Pr
itting radio
tivity in thegorizations fication andassified intow level rad classificatig the curreny Standard
ve waste clte. The samto self-disp
v for collect
n of Radi
” as radioacncluding spthe NSA d
of which ls prescribes the radioacgeneration rrotection, et
onuclide ha
Enforcemeare describ
d the Standao three subioactive waion system nt status ofGSG-1 (Ra
lassificationme criteria posal: less ttive dose.
ioactive W Applic
active materpent nucleardefines high
the radioaed by the Nctive waste rate are spectc.) as follow
aving a hal
ent Decree obed in the Nards for the b-categorizaaste (LLW)of LILW anf the radioaadioactive W
n corresponfor dose rathan 0.01 m
Waste
cation
rial or r fuel)
level active
NSSC. other cified ws:
lf-life
of the NSSC
Self-tions: ) and nd its active Waste
nds to ate in
mSv a
C. Sccope
of A Appliccationn
1.
2.
3.
4.
ARTICLE
This Convthe spentSpent fueis not covParty decl
This Conmanagemapplicationcontains ooriginate sealed sothis Conve
This Convor radioadeclared Conventioapply to tfrom milittransferreprogramm
This Conv4, 7, 11, 1
E 3. SCOP
vention shat fuel resul held at revered in thlares repro
nvention sment whe
ns. Howevonly naturafrom the
ource or it ention by t
vention shaactive was
as spent on by the the safety ary or defd perman
mes.
vention sha4, 24 and
C. Sco
E OF APP
all apply toults from teprocessinhe scope ocessing to
shall also n the raver, this Cally occurrnuclear fuis declarehe Contrac
all not applte within fuel or ra
Contractinof managfense prog
nently to
all also app 26.
ope of A
- 21 -
PLICATION
o the safetythe operat
ng facilitiesof this Co
o be part o
apply to adioactive Conventioning radioauel cycle, d as radiocting Party
ly to the samilitary o
adioactive ng Party. ement of grammes and man
ply to disc
Applica
N
y of spent ftion of civ as part of
onvention f spent fue
the safety waste n shall noctive mateunless it
oactive wasy.
afety of maor defense
waste forHowever,
spent fuel if and whaged with
harges as
ation (A
fuel managvilian nuclef a reproceunless the
el managem
y of radioresults f
ot apply toerials and t constituteste for the
anagemente programr the purp this Con and radioen such m
hin exclus
provided f
Article
gement whear reacto
essing active Contractment.
oactive wafrom civilo waste tthat does es a disuse purposes
t of spent fmmes, unleposes of tnvention shoactive wamaterials sively civil
for in Artic
e 3)
hen ors. vity ting
aste lian hat not sed s of
fuel ess this hall
aste are ian
cles
The
Spen
Conv
relate
NPP
fuel
class
Spen
mana
home
repro
those
Pursunaturfacili
Pursu
defen
Conv
are in
C
C
C
C
scope of th
nt Fuel Man
vention) is
ed Act and
s and nucle
cycle facili
sification of
nt fuel is pr
agement wi
e and abro
ocessing act
e activities h
uant to Arrally occurrities and the
uant to Art
nse program
vention. Bu
ncorporated
C.1
C.2 Re
C.3 Na
C.4
his national
nagement a
the radioac
d subordinat
ar research
ties and RI
f radioactive
resently in s
ill be later
oad. There
tivities of s
have not be
ticle 3.2 oring radioace industrial
ticle 3.3 of
ms are not
ut the RI wa
d in the inve
eprocess
aturally O
l report acc
and on the
ctive waste
te statute. S
facilities as
users are c
e waste are
storage insi
determined
efore, pursu
spent fuel a
en conducte
f the Jointctive materiusers of nuc
f the Joint C
t declared
aste transfer
entories men
sing of Sp
Occurring
- 22 -
cording to t
Safety of R
e defined in
Spent fuel
s well as rad
covered in t
specified in
de the NPP
d taking int
uant to A
are not desc
ed in Korea
t Conventioials (NORMclear mater
Convention
as radioact
rred to RI m
ntioned in th
pent Fue
g Radioa
the Joint C
Radioactive
n accordanc
and radioac
dioactive w
this nationa
n Section B.
Ps, and a na
to account
Article 3.1
cribed in th
a.
on, this NaMs) generatial.
n, radioactiv
tive waste
management
his Nationa
el
active Ma
onvention o
Waste Ma
ce with the
ctive waste
waste genera
al report. Th
4.
ational polic
technology
of the Jo
he National
ational Repted from nu
ve waste w
for purpos
t facilities fr
al Report.
terials
on the Safe
anagement (
e Nuclear S
e generated
ated from nu
he definition
cy for spen
y developme
oint Conven
Report, be
port includeuclear fuel
within milita
ses of the
from militar
ety of
(Joint
Safety
from
uclear
n and
nt fuel
ent at
ntion,
cause
es the cycle
ary or
Joint
ry use
DD. Inv
vento
ories and Listss
2.
D.1.
Spencerta
D
ARTICLE
This repor
(i) a lisConv
(ii) an inis beiinvengive i
(iii) a list Conv
(iv) an inthat: (a) is
nu(b) ha(c) ha
Thapact
(v) a listand t
1 Nuclear
nt fuels witain period,
D. Inv
D.1 Sp
E 32. REPO
rt shall also
st of the vention, theventory ofing held in
ntory shall information of the rad
vention, thenventory of
being heuclear fuel as been dias resultedis inventorpropriate tivity and st of nucleathe status o
r Power Re
hdrawn froand efforts
ventorie
pent Fue
ORTING
o include:
spent fueeir location spent fue storage acontain a n on its madioactive weir locationf radioactiv
ld in stora cycle facilsposed of;
d from pastry shall coninformatio
specific radar facilitiesof decomm
eactor Fac
om NPPs ars to avoid
es and L
l Manage
- 25 -
el managn, main purel that is suand of that
descriptionass and its waste mann, main purve waste t
age at radlities; ; or t practicesntain a des
on availabdionuclidess in the prmissioning
cilities
re stored insaturation
Lists (Ar
ement
ement facrpose and ubject to thwhich has n of the m total activ
nagement rpose and that is sub
ioactive w
. scription of
ble, such s; rocess of activities a
n a spent fuof the poo
rticle 32,
cilities subessential f
his Conven been dispaterial andity; facilities sessential f
bject to this
waste mana
f the mateas volum
being decoat those fac
uel pool at l have been
, Paragr
bject to tfeatures; ntion and tposed of. Td, if availab
subject to tfeatures; s Convent
agement a
rial and otme or ma
ommissioncilities.
t each unit n made su
raph 2)
this
hat This ble,
this
tion
and
her ass,
ned
for a ch as
expaneighfuel sof sp
D.1.
HANmatecurre
The stainstoredurinspentfrom
The NPP
H
H
W
ansion of onhboring unistorage faci
pent fuel in s
T
2 Nuclear
NARO is a erial irradiatently in use
spent fuel p
nless steel pe temporarilng normal ot fuel pool o
m HANARO
PIEF was cs. It consist
Site R
Kori
Hanbit
Hanul
Wolsong P
HANARO
PIEF
n-site storagts. Annex Ailities at eacstorage are
Table D.1-1.
r Research
multi-purption testing,for various
pool of HAplate. The vly fuels loaoperation ofof HANAR
O.
constructed ts of three p
Reactor Typ
PWR
PWR
PWR
PWR / PHW
e capacity aA-1 shows thch plant. Thgiven in Ta
. Inventory o
h Facilities
pose researc RI productresearch an
ANARO is vault contaiaded into tf HANARO
RO. Table D
for performpools (for re
pe Type
WR w
- 26 -
and transferthe locationhe inventorieable D.1-1.
of Spent Fu
s
ch reactor dtion, and band developm
a heavy coins three stthe reactor O for 20 yeaD.1-2 shows
mance testineception, un
of Storage
wet
wet
wet
wet / dry
r of spent fu, characterises, initial en
uels Stored
designed foasic science ment activit
ncrete structorage latticcore as we
ars. Annex s the invento
ng and evalnloading and
Invento
(MTU
2,121.
2,202.
1,848.
7,252.
uels to the spstics, and innrichment o
at NPP Site
(As of
or fuel perfoand applicaies.
cture with ices and hasell as spenA-2 provid
ory of spent
uation of fud testing), f
ory
U)
Init
(
5
1
1
3 4.5 /
spent fuel ponventory of of fuel, and
es
March 31, 2
formance teations study
interior linis the capacnt fuel genedes details ont fuels gene
uels irradiatfour concret
tial Enrichm
(w/o of 235U)
4.1 ~ 4.5
4.5
4.5
/ natural uran
ool of spent types
2014)
sting, y. It is
ng of ity to erated of the erated
ted in te hot
ment
)
nium
- 27 -
cells, two lead hot cells, and supporting installations. Annex Table A-2 shows the details of the spent fuel storage pool in the PIEF.
As of the end of March 2014, spent fuels transshipped from NPPs are stored in the PIEF in the form of assemblies, spent fuel rods, and specimens to carry out post-irradiation examinations. Table D.1-2 shows the inventory of spent fuels stored in the PIEF.
Table D.1-2. Inventory of Spent Fuels in Storage Pools of Research Reactor Facilities
(As of March 31, 2014)
Facility Inventory (MTU)
HANARO 0.8
PIEF 3.3
D.2.
NPPwasteradiosystetreatmosmodryinsyste The separwith facili Sinceand (Genbeenradiolate Mon-si
W
D
1 Nuclear
s, which are treatment
oactive wasem consistsment systemosis (RO) eng system, pem and wast
on-site radrate storageradiation m
ities are list
e 2010, a to2,536 drum
neral Accepn transferreoactive wastMarch, 201ite storage f
Table
Site
Kori
Wolsong
Hanbit
Hanul
Total
D.2 Ra
r Power Re
re currentlyfacilities ante generate
s of gas dem is equippquipment. Tpolymer sote compacto
dioactive we spaces for monitoring ted in Annex
otal of 3,53ms from Wtance Criterd to the Kte generated
14. Table Dfacilities as
e D.2-1. Inv
Inve
[200L
42
9,
22
17
91
adioactiv
eactor Fac
y in operatind storage f
ed in the precay tanks
ped with a lThe solid w
olidification or.
waste storagsolid wastesystems. T
x B-1 and B
6 drums of Wolsong sitria for LowKORAD fd from NPP
D.2-1 showsof the end o
ventory of R
entory
L drum]
2,184
,840
2,453
7,016
,493
ve Waste
- 28 -
cilities
ion, are equfacilities onrocess of op
and/or chliquid waste
waste treatmn system, sp
ge facility ies accordingThe locatioB-2.
f radioactivete) suitable
w and Intermfor permanPs are stores the inventof March 20
Radioactive
M
Radio
60Co, 1
60Co, 1
60Co, 1
60Co, 1
Manage
uipped withn-site to ensperation. Th
harcoal delae evaporato
ment facilitypent filter tr
is a concreg to radioacon and char
e wastes (1,e for the Nmediate Levnent disposed at the ontory of radi014.
Waste Stor
Major
onuclide
37Cs, Etc.
37Cs, Etc.
37Cs, Etc.
37Cs, Etc.
-
ment Fac
h gaseous, lure the safehe gaseous ay beds. Tor, ion exch
is composereatment sy
ete slab-typtivity level,racteristics
,000 drums NSSC Noticvel Radioactal. The 91
n-site storagioactive wa
red at NPP
(As of
Tot
Estim
cilities
liquid, and e managemewaste treat
The liquid whanger or reed of spent
ystem, pack
pe building , and is equof these o
from Hanuce No. 20tive Waste)1,493 drumge facilities aste stored a
Sites
March 31, 2
tal activity
mated [TBq]
5.6E+2
1.9E+2
9.5E+4
4.3E+2
9.7E+4
solid ent of tment waste
everse resin
aging
with ipped n-site
ul site 13-29 have
ms of as of
at the
2014)
]
- 29 -
D.2.2 Nuclear Research Facility
The KAERI operates radioactive waste treatment as well as storage facilities for the safe management of liquid and solid radioactive waste generated from research facilities. Annex B-3 and B-4 show the KAERI’s radioactive waste storage and treatment facilities. Liquid radioactive waste generated from the KAERI is treated with an evaporation process. The resulting concentrate is solidified by a bituminization process, whereas the condensate is treated by a solar evaporation process. Solid waste is treated for volume reduction with a compactor and stored on-site. Radioactive waste generated from KRR-1 and 2 at Nowon-gu in Seoul, where is former site of KAERI, was solidified in cement and packaged in 200-liter drums. It was transferred to the KAERI facility in Daejeon in 1985. Since then, they have been stored at the radioactive waste storage facility there. Table D.2-2 shows the inventory of the KAERI’s radioactive waste storage facility with major radionuclides as of late March 2014. Beginning in 2011, the KAERI operates a combustible waste treatment facility to reduce the volume of combustible waste generated in the UCF, KRR 1 and 2 decommissioning process. Table D.2-2 shows the inventory of combustible waste stored in the storage building of the combustible waste storage facility with major radionuclides and Annex B-5 lists the location and capacity of this facility.
Table D.2-2. Inventory of Radioactive Waste Stored at the KAERI
(As of March 31, 2014)
Facility Inventory
[200L drum]
Major
Radionuclides
Total Activity
Estimated [TBq]
Radioactive waste
storage facility 10,957
54Mn, 60Co, 238U, 137Cs, 131I, Etc.
1.2E+0
Combustible waste
treatment facility 9,075
60Co, 137Cs, Natural
Uranium 7.5E-1
D.2.3 Nuclear Fuel Fabrication Facility
Two nuclear fuel fabrication plants are operated by the KEPCO NF. The 1st plant started to produce PWR fuels in 1989 and the 2nd plant for PHWR/PWR fuels started its commercial operation in 1998. The solid waste treatment and storage concept of the two fabrication plants are almost identical, and details of the storage facilities are listed in
- 30 -
Annex B-6. However, the liquid waste treatment process for the PWR fuel fabrication plant is different from that of the PHWR fuel fabrication plant as shown in Annex B-7. As of the end of March 2014, the amount of solid waste generated from the nuclear fuel fabrication facility is up to 7,041 drums. All of them are stored and managed at the on-site waste storage facility. Table D.2-3 shows the inventory of radioactive waste stored at the on-site storage facility.
Table D.2-3. Inventory of Radioactive Waste Stored at the KEPCO NF
(As of March 31, 2014)
Facility Inventory
[200L drum]
Major
Radionuclide
Total Activity
Estimated [TBq]
Radioactive waste
storage facility 7,041 234U, 235U, 238U 4.2E-1
D.2.4 RI Waste Management Facility
The RI waste generated from domestic RI users is collected and stored at the RI waste management facility operated by the KORAD. There are 3,192 drums of RI waste managed in the facility as of the end of March 2014. Annex B-8 lists the location and main characteristics of the RI waste management facility. Table D.2-4 shows the inventory of RI waste stored in the RI waste management facility, as of the end of March 2014.
Table D.2-4. Inventory of RI Waste Stored at the KORAD
(As of March 31, 2014)
Facility Inventory
[200L drum]
Major
Radionuclide
Total Activity
Estimated [TBq]
RI waste storage
facility
2,904
(disused unsealed sources) 125I, 99mTc, Etc. <1.00
288
(disused sealed sources)
60Co, 137Cs, 241Am,
Etc. 2.8E+2
D.2.5 LILW Disposal Facility
For the management of LILW, the 1st stage of a LILW disposal facility is under construction with the completion target of late December 2014. First of all, a radwaste receipt/storage building of the disposal facility has already been constructed and is now
- 31 -
in operation to receive radioactive waste from some NPPs whose storage capacity has been almost saturated. Annex B-9 lists the location and major characteristics of the radwaste receipt/ storage building.
As of the end of March 2014, 4,243 drums of LILW are stored in the receipt/storage building. Table D.2-5 shows the inventory, major radionuclide and total activity of LILW.
Table D.2-5. Inventory of the LILW Disposal Facility
(As of March 31, 2014)
Facility Name Inventory
[200L drum] Major Radionuclide
Total Activity
Estimated [TBq]
LILW disposal facility
(Radwaste receipt /
storage building)
4,243 60Co, 137Cs, Etc. 4.3E+1
D.2.6 Others
Taekwang Industrial Co., Ltd. in Ulsan generated radiologically contaminated byproducts in the process of producing synthetic fiber using licensed nuclear material, depleted uranium, as a catalyst. Nuclear materials have not been used since they were replaced by a non-radioactive catalyst in 2004. The total inventory of radioactive waste stored in this facility is 7,131 drums, as of March 31, 2014. Taegutec Co. in Daegu generated radiologically contaminated byproducts in the process of producing wire. Since the closure of their production facilities in 2004, contaminated byproducts have not been generated from the facility (decontamination and decommissioning of the facility were carried out from October 2004 to May 2005). The total inventory of radioactive waste stored in this facility is 52 drums, as of March 31, 2014.
D.3.
Radito thcontainvengiven152Eu Annewaste
s
D.3.
The fromcombnatur
D
1 KRR-1 a
oactive washeir characteainers, and ntory of radn in Table Du.
ex C showse from the d
Facility
Temporary
storage area
2 UCF
decommissm the decom
bustible waral uranium
D.3 De
and 2
ste from theeristics andtemporarily
dioactive waD.3-1. The
s the list of decommissi
Table D.3at th
[2
sioning of thmmissioningste treatmen
m.
ecommis
e decommisd radioactivy stored in taste generatmajor radio
f nuclear facioning of KR
3-1. Inventohe KRR-1 an
Inventory
200L drum]
757.1
he UCF comg process hnt facility. T
ssioning
- 32 -
ssioning of Kvity levels, pthe reactor ted from theonuclides in
cilities decoKRR-1 and 2
ory of Radiond 2 Decom
60C
mmenced inhas been sThe radioac
KRR-1 and packed intohall of KRR
e KRR-1 ann radioactive
ommissione2.
oactive Wasmmissioning
Major
Radionucli
Co, 137Cs, 152E
n 2001 andstored in thctive wastes
2 were claso 200-liter dR-2. As of Md 2 decomme waste are
ed and estim
ste Stored g Site
(As of
ide E
Eu, Etc.
d completedhe storage were conta
ssified accodrums and March 2014
missioning s 60Co, 137Cs
mated amou
March 31, 2
Total Activ
Estimated [T
1.9E+0
d in 2012. Wbuilding o
aminated on
ording 4 m3
4, the site is s, and
unt of
2014)
vity
TBq]
Waste of the nly by
The nrecorArticReguNuclmontfrom
D
nuclear licerd managemcle 98 of tulation of tlear Safety (th after the
m the license
D.4 Re
ensee has bement systemthe NSA anthe NSA, t(KINS) info end of eve
ee, and conf
ecord Ke
een maintaim. In accordnd Articlethe nuclear ormation onery quarter.firmed infor
eeping an
- 33 -
ining recorddance with127 and Alicensee h
n both radio. The KINSrmation thro
nd Repor
ds on radioathe reporti
Attached Tahas reportedoactive wastS has evaluough period
rting
active wasteng requiremable 5 of td to the Kote and spent
uated and mdic inspectio
e using theirments definthe Enforceorea Institu
nt fuel withimanaged theons, etc.
r own ned in ement ute of n one
e data
ERegu
. Legulato
gislatry Fr
tive arame
and eworkk
t
The Conv
1.
2.
E
E
ARTICLE
Each Contthe legislanecessary
legislative,vention are
ARTICLE
Each Coregulatorywaste maThis legis(i) the e
regul(ii) a sy
mana(iii) a sys
waste(iv) a sys
and d(v) the e
licens(vi) a cle
E. Le
E.1 Im
E.2 Le
E 18. IMPL
tracting Paative, reguy for implem
regulatorydiscussed in
E 19. LEGI
ntracting Py framewoanagementslative and establishmations for ystem of agement astem of proe managemstem of adocumentaenforcemenses; ear allocat
egislativ
mplement
egislative
LEMENTIN
arty shall talatory and
menting its
y and othern relevant s
ISLATIVE
Party shalork to govet. regulatoryent of apradiation s
licensing ctivities;
ohibition ofment facilitppropriate
ation and rent of appli
ion of res
ve and
ting Meas
e and Reg
- 37 -
NG MEASU
ake, within d administrs obligation
r measures sections of t
AND REG
ll establishern the saf
y frameworplicable n
safety; of spen
f the operaty without a institutioneporting; icable reg
sponsibilitie
d Regul
sures (Ar
gulatory
URES
the framerative means under th
to fulfill ththis report.
GULATORY
h and maifety of spe
rk shall proational sa
nt fuel a
ation of a sa license; nal control
ulations a
es of the
latory F
rticle 18)
Framewo
work of its asures andis Conven
he obligatio
Y FRAMEW
ntain a leent fuel an
ovide for: afety requi
nd radioa
spent fuel o
, regulato
nd of the
bodies inv
Frame
ork (Artic
s national lad other stention.
ons of the
WORK
egislative and radioact
rements a
active wa
or radioact
ory inspect
terms of
volved in
ework
cle 19)
aw, eps
Joint
and tive
and
aste
tive
tion
the
the
- 38 -
different steps of spent fuel and of radioactive waste management. 3. When considering whether to regulate radioactive materials as
radioactive waste, Contracting Parties shall take due account of the objectives of this Convention.
E.2.1 Legislative Framework of Nuclear Regulation
E.2.1.1 Nuclear Safety Related Act and Subordinate Statute National laws related to the safety of spent fuel and radioactive waste management are the NSA, RWMA, Environmental Impact Assessment Act and others as shown in Table E.2-1. Matters on nuclear safety regulation and radiation protection are stipulated in the NSA. The NSA was enacted as a main law concerning the safety regulations for spent fuel and radioactive waste management. Laws concerning nuclear regulation (Figure E.2-1) consist of four levels: NSA, its Enforcement Decree (a Presidential Decree), its Enforcement Regulation (an ordinance of the Prime Minister), the Regulation of the NSSC (Regulations on Technical Standards for Nuclear Reactor Facilities, Etc. and Regulations on Technical Standards for Radiation Safety Management, Etc.), and the Notices of the NSSC. The NSA is composed of a total of 11 chapters including General Provision, Establishment and Execution of Comprehensive Nuclear Safety Plan, Construction Permit (CP) and Operation License (OL) and inspection of disposal facilities, Etc. The Enforcement Decree of the NSA provides the particulars entrusted in the NSA and administrative particulars, including the detailed procedures and methods necessary for enforcement of the NSA. The Enforcement Regulation of the NSA and the Regulation of the NSSC provide the particulars, including detailed procedures, format of documents and technical standards, as entrusted by the same Act and the same Decree. The Notices of the NSSC prescribe the regulatory requirements, technical standards and guidelines, as entrusted by the NSA, its Decree and Regulation.
- 39 -
Table E.2-1. Laws Concerning Nuclear Safety Regulation
Title Major Contents Competent Authorities Remarks
Nuclear Safety Act Basic law on the nuclear safety regulations NSSC -
Korea Institute of Nuclear Safety Act
Provides the establishment and operation of the Korea Institute of Nuclear Safety NSSC -
Act on Physical Protection and Radiological Emergency
Establishes more effective system for physical protection of nuclear material and nuclear facilities, and provides legal and institutional basis for preventing radiological disaster and preparing countermeasures against radiological emergency
NSSC -
Nuclear Liability Act
Provides the procedures and the extent of compensation for any damages which an individual has suffered from a nuclear accident
NSSC -
Act on Protective Action Guidelines
Against Radiation in the Natural
Environment
Provides the matters concerning safety management of radiation encountered in environments
NSSC
Act on Indemnification Agreement for
Nuclear Liability
Provides the particulars on a contract between the government and the operator to make up any compensation not covered by insurance
NSSC -
Act on Establishment and Operation of the
NSSC
Provides the particulars on establishment and operation of the NSSC NSSC
Atomic Energy Promotion Act Basic law on the nuclear utilizations MSIP
Radioactive Waste Management Act
Provides procedures related to radioactive waste management MOTIE
Refers to the NSA for the safety regulations of radioactive waste management facilities
Electricity Business Act
Provides the basic system of electricity business MOTIE
Specifies the basic system of the Electricity Business Act including nuclear power plants
Electric Source Development
Promotion Act
Provides special cases relevant to the development of electric sources MOTIE Prior designation notice of nuclear site
Basic Act of Environmental
Policy
Mother law of the environmental preservation policy MOE
The NSA is entrusted with the particulars on measures to prevent radiological contamination
Act on Assessment of Impacts of Works
on Environment, Traffic, Disasters,
Etc.
Provides the extent and procedures to assess environmental impact according to the Basic Act of Environmental Policy
MOE Assessment of environmental impacts excluding radiological impacts
Framework Act on Fire Services
Provides for general matters on the prevention, precaution and the extinguishment of fires
NEMA The requirements for safety management of inflammables
Basic Act on Civil Defense
Provides for general matters on the civil defense system MOSPA
Preparedness against disasters due to nuclear accidents is included in the basic civil defense plan
Basic Act on Management of
Disasters and Safety
Provides for general matters on the control of man-made disasters MOSPA
It prescribes corrective or complementary measures for violations in the implementation of the basic civil defense plan
Industrial Accident Compensation Insurance Act
Provides insurance to compensate workers in case of an industrial disaster MOEL
Nuclear workers are to be compensated in accordance with the compensation standards in the NSA.
- 40 -
Industrial Safety and Health Act
Provides for the preservation and enhancement of workers' health and safety MOEL The NSA is entrusted with the
particulars on radiological safety
Building Act Provides for general matters on construction MOLIT
When the sites of disposal facilities have obtained prior approval, they are to be seen as having obtained construction permission in accordance with Building Act
FFigure E.2-1. Legal Fram
- 41 -
mework for NNuclear Safetty Regulationn
- 42 -
Table E.2-2. Contents of Nuclear Safety Act
Contents Main Description
Chapter 1 General Provisions Purpose of Nuclear Safety Act and Definitions of Terms
Article 1 (purpose) Purpose of Nuclear Safety Act
Article 2 (definitions) Definition of radioactive waste
Chapter 2 Establishment and Execution of Comprehensive Nuclear Safety Plan
Establishment and enforcement of Comprehensive Nuclear Safety Plan and the implementation of nuclear safety research and development projects
Chapter 3 Construction and Operation of Nuclear Reactor and Related Facilities
Describes overall matters related with the construction and operation of nuclear power reactors and related facilities Section 1 Construction of Nuclear Power Reactor and
Related Facilities
Section 2 Operation of Nuclear Power Reactor and Related Facilities
Article 28 (Decommissioning of Nuclear Power Reactor and Related Facilities)
Specifies the contents that must be included in the decommissioning plan
Section 3 Construction and Operation of Nuclear Research Reactor, etc.
Describes overall matters related to the construction and operation of research reactors
Chapter 4 Nuclear Fuel Cycle Business and Use of Nuclear Material, Etc. Permission procedure and criteria for nuclear fuel cycle
enterprise Section 1 Nuclear Fuel Cycle Business
Article 42 (Decommissioning of Nuclear Fuel Cycle Facility)
Specifies the contents that must be included in the decommissioning plan
Section 2 Use of Nuclear Material Permission procedure and criteria for the use of nuclear material
Chapter 5 Radioisotope and Radiation Generating Device Permission procedure and standard, inspection procedure and method
Article 54 (Registration of Business Agent) Specifies that those who wish to collect, treat, and transport radioactive isotopes, Etc. and radioactive waste must register with the NSSC
Chapter 6 Disposal and Transport Construction and operation permit and inspection of disposal facilities, Etc.
Article 63 (Permit for Construction and operation of Disposal Facilities, Etc.)
Specifies that those who wish to construct and operate a radioactive waste disposal facility, Etc. must obtain the permission from the NSSC
Article 70 (Restrictions on Disposal of Radioactive Wastes) Prohibition of sea dumping of radioactive waste
Chapter 7 Dosimeter Reading, Etc. Registration and inspection of dosimeter reading service provider
Chapter 8 License and Examination Examination of license and issue of license, Etc.
Chapter 9 Regulation and Supervision Set up of a restricted area and radiation hazard protection measures, Etc.
Chapter 10 Supplementary Provisions Conditions for permit or designation, approval of topical report, etc.
Article 103 (Gathering Residents’ Opinion) Specifies that those who wish to obtain a construction and operation permit for a radioactive waste disposal facility or spent fuel storage facility must gather residents’ opinions
Article 104 (Preservation of Environment) Specifies that the constructor and operator of a radioactive waste disposal facility must conduct an environmental radiation survey and a radiological environmental impact assessment
Chapter 11 Penal Provisions Penal provisions, fine for negligence, and joint penal provisions
Addenda Enforcement date, relationship to other acts, etc.
The Nfacili
The requi
The the rFacil
1 Di
NSA prescrity, etc.1 as
matters
matters operatio
matters prohibit
matters
Enforcemeirements ne
matters applicat
matters facility,
matters preoperAssuran
matters and
matters
Enforcemenregulations lities, etc.
sposal facil
Nuclear S
Enforcem
Enforcem
ribes basic ms follows:
concerning
concerninon of a disp
concernintion of dum
concerning
ent Decree ecessary for
concerningtion for cha
concerning, etc.;
concerninrational insnce (QA) in
concerning
concerning
nt of Regulof the NSSand Regu
ity, etc. : a
wa
Safety Act (
ment Decree
ment of Reg
matters on s
g CP and OL
g safety inosal facility
g limitatiomping into th
g safe transp
of the NSimplement
g applicationge permit
g nuclear
ng implemspection, penspection ap
g procedure
g transport a
lation of thSC (Regulatulation on
storage, proastes and ac
NSA)
e of the NS
ulation of t
- 43 -
safety to be
L of a dispo
nspections y, etc.;
ns on disphe sea; and
port and pac
SA (Presidting basic m
on for CP aof permitte
material ac
mentation oeriodic insp
pplicable to
es and meth
and packagi
he NSA (an tion on Tec
Technical
ocessing andccessory fac
SA
the NSA an
applied to
osal facility,
with respe
posal of ra
ckaging of r
dential Decmatters in the
and OL of d matters;
ccounting a
of regulatpection, dia disposal f
ods for clea
ing of radioa
ordinance chnical Stan
Standards
d disposal fcility
nd Regulatio
a radioactiv
, etc.;
ect to the
adioactive
radioactive m
ree) specife NSA as fo
a disposal f
and securit
ory inspecisposal inspfacility, etc.
arance of ra
active mate
of the Primndards for Ns for Radi
facility of ra
ons of the
ve waste dis
installation
waste inclu
material, et
fies the deollows:
facility, etc
ty in a dis
ctions sucpection, Qu.;
adioactive w
erials, etc.
me MinisterNuclear Reiological S
adioactive
NSSC
sposal
n and
uding
c.
tailed
c. and
sposal
h as uality
waste;
r) and eactor Safety
Mana
The NmanaRegumana
agement, et
Mattersnecessacontrol transpor
Matterstreatmennuclear Reactor
Mattersand relaStandar
Mattersdisposa(Regulaand
MattersStandar
Notices of agement spulation andagement of
Sitting C
Accepta
RadioloFacility
Regulat
Notices of
tc.) specify
s entrusted ary for impl
and manart of radioac
s concerningnt and storfuel cycle
r Facilities,
s concerningated facilitierds for Nucl
s concerninl, deep di
ations on T
s concerninrds for Radi
the NSSC ppecified in d NSSC Rradioactive
Criteria for
ance Criteri
ogical Protey
tion on the C
f the NSSC
below conte
in the NSAlementing tagement ofctive materi
g structure, rage facilitie
facilities (etc.);
g radioactives, and nucllear Reactor
ng facilitiesisposal facechnical St
g disposal ation Safety
present the the NSA
Regulations. e waste.
Radioactiv
a for LILW
ection Crit
Clearance L
C
- 44 -
ents;
A and its Ethe Act andf radioactivials, etc. (En
equipment es for nucl(Regulation
ve waste malear fuel cycr Facilities,
s, equipmencilities, spetandards for
of radioacty Managem
detailed tecand its EAnnex F
ve Waste Di
W
teria for L
Level of Rad
nforcementd the Decreve waste anforcement
and perforear reactorss on Techn
anagement dcle facilitiesetc.);
nt and perent fuel mr Radiation
tive waste ment, etc.).
chnical stanEnforcement
lists the
sposal Facil
Long-term S
dioactive W
t Decree, anee, and maas well as Regulation
rmance of ras and relatenical Standa
during opers (Regulatio
rformance management
Safety Ma
(Regulation
ndards for rt Decree, iNotices ap
lity
Safety of
Waste, etc.
nd other matters conce
packagingn of the NSA
radioactive wed facilitiesards for Nu
ration of reaons on Tech
of near sut facilities,anagement,
ns on Tech
radioactive wits Enforcepplicable to
LILW Dis
matters erning g and A);
waste s, and uclear
actors hnical
urface , etc. etc.);
hnical
waste ement o the
sposal
E.2.1
MattManalevelMOTKOR
Fig
The implewaste
1.2 Radioac
ters concernagement Acls: RWMA,TIE, and proRAD, and es
gure E.2-2.
Notices ofementation,e are listed
Regulatfuel ma
Regulat
Regulat
ctive Waste
ning radioacct (RWMA its Enforceovides partistablishmen
Legal Hiera
f the MOT, matters enin Annex G
tion on calcanagement
tion on man
tion on meth
e Managem
ctive waste mA). As showement Decreiculars regant of radioac
archy of the
TIE prescribntrusted by tG.
culation crit
nagement of
hod for radi
- 45 -
ment Relate
managemenwn Figure E
ee, its Enfoarding manactive waste
e Radioactiv
be the stanthe higher l
teria of exp
f Radioactiv
ioactive wa
ed Act
nt are defineE.2-2, the Rorcement Reagement of managemen
ve Waste M
ndards andaw Main N
penses for r
ve Waste M
ste acceptan
ed in the RaWMA is coegulation anLILW, estant fund.
Managemen
d procedureotices regar
radioactive
Management
nce, etc.
adioactive Womposed ofnd Notices oablishment o
nt Act (RWM
es necessarrding radioa
waste and
Fund
Waste f four of the of the
MA)
y for active
spent
- 46 -
E.2.1.3 Laws related to Physical Protection and Radiological Emergency of Nuclear Facilities, etc.
The Act on Physical Protection and Radiological Emergency (APPRE) was enacted in May 2003 to strengthen the physical protection system for nuclear materials and facilities and the radiological emergency management system. This Act inherits the articles related to physical protection and radiological disaster prevention as previously specified in NSA as well as specifies various requirements for strengthening physical protection and radiological disaster prevention measures. The APPRE was revised in May 2014 to divide the Emergency Planning Zone (EPZ) into the Precautionary Action Zone (PAZ) and the Urgent Protective Action Planning Zone (UPZ). This was to incorporate IAEA standards which recommends designating the PAZ up to 3~5 km from the plant and the UPZ within 20~30 km radius of a damaged NPPs to ensure effective emergency response in case of radiological emergency.
E.2.1.4 Laws related to Nuclear Damage Compensation
For the civil liabilities of the license or permit holder due to a nuclear accident, the Nuclear Liability Act (1969) and the Act on Indemnification Agreement for Nuclear Liability (1975) were enacted to prescribe the general principles for civil liabilities concerning internationally accepted nuclear damage. The Nuclear Liability Act was revised in January 2001 to reflect on domestic laws the contents of the Vienna Convention revised in 1997. The revision of the Act concretized the concept of nuclear damage, set the limit of liability of the business operator to 300 million Special Drawing Rights2 (SDRs) and set the upper limit of the compensation amount also to 300 million SDR. Actual amounts of compensation are specified in the Enforcement Decree of the Nuclear Liability Act, and the amount of compensation of NPPs is 50 billion KRW as of the end of March 2014. E.2.2 Nuclear Regulatory Framework
In the Korean framework for nuclear safety regulation, the NSSC has absolute authority with regard to overall nuclear safety regulations. The Korean government gave the NSSC the authority in relation to nuclear safety regulations such as establishment of a nuclear safety policy and licensing under the provision of nuclear safety related laws such as the NSA. Likewise, Ministries of the government deal with nuclear safety management related operations in fulfilling their own duties by forming an organic system with the NSSC. For example, the Ministry of Environment (MOE) has absolute authority with regard to the environment protection policy; it is also in charge of environmental protection and management concerning natural background radiation.
2 It is the Special Drawing Rights of the International Monetary Fund (IMF) and a type of international
reserve currency exercised since 1970.
The MAgenin chthe gpowe The absolomissectoManaeach Koreauthorevieor om For noperaand Kregarconcreviesafet
Fig
Ministry ofncy), whichharge of the government er facilities
Korean golute author
ssion of safeors are esagement (Pother throu
ea prescribeorities betwewed by themission of s
nuclear safeating the KIKorea Instirding nucleerning nucl
ews, inspectty regulation
gure E.2-3. G
f Security anh implemen
safety of cosectors thaand activiti
overnment rity over gety regulatitablished o
Presidential ugh overall es that bills ween admine Cabinet Msafety regula
ety regulatioINS as a pritute of Nucear safety lear safety tions, trainins and accu
Governmen
nd Public Ats national ombustible
at are relatedies.
separately governmentons when laor amendeDecree) alslegislative for the esta
nistrative bMeeting presation requir
on requiringrofessional rclear Safetyregulation. entrusted bng and R&
umulated exp
nt Organizat
- 47 -
Administratidisaster prematerials ind with the s
operates tt legislationaws relateded. The Rso stipulatesactivities. A
ablishment obranches ansided by th
rements.
g professionregulatory ay Act, in or
The KINby the NSS
&D based onperiences.
tions related
ion (Nationevention ann nuclear fasafety mana
the Office n to ensur
d to the operRegulation s that relateArticle 89 oor amendme
nd major pohe President
nal expertiseagency underder to streS is engag
SC which inn expert kno
d to Radioa
nal Emergennd managemacilities. Figagement con
of Legislae neither orations of thon Legisla
ed sectors mof the Constent of laws,olicy adjust to prevent
e, the Koreaer the provingthen expged in regnclude areaowledge con
active Waste
ncy Management measugure E.2-3 sncerning nu
ation whichoverlappinghese governative Oper
must consulttitutional La, confirmatistments mut the overlap
an governmision of the
pertise in mgulatory seras such as sncerning nu
e Managem
ement ures is shows uclear
h has g nor nment ration t with aw of ion of ust be pping
ment is NSA
matters rvices safety uclear
ment
E.2.3
An ashouEnvisafetKINS
An ato thcontr(QAPNSSC The condconfoincluregulthe cthosea conresid
Any can aNSSC
3 Licensin
applicant, wuld submit t
ronmental ty review wS, the NSSC
applicant, whe NSSC arol, specificP) with resC may gran
safety reviducted to coformity witudes safety latory criterconstructione impacts. Tnstruction s
dents of the
change of paffect the sC.
Prior App
CP and O
Change P
ng System
who wishesto the NSSCReport (RE
with respect C may grant
who wishes tan applicatications of dspect to its nt CP and O
iew of apponfirm thatth the rele
reviews ofria in due cn and operaThe RER, tosite or applarea surrou
permitted msafety of a
roval for Co
OL of Dispos
Permit
and Safet
s to construC an applicER) and oto RER andt a prior app
to obtain CPon which adesign and constructio
OL to the app
plication fort the site avant regulaf the princicourse, asseation of a dio be submittlication fornding the si
matters such disposal fa
onstruction
sal Facility,
- 48 -
ty Evaluat
uct a dispocation for p
on-site inved on-site inproval for a
P and OL ofattached w
d work procon and operplicant.
r the CP aand the desatory requiples and cessment of isposal facited at the timr CP and Oite.
h as design oacility, etc.
n Site
etc.
ion
sal facility,prior approvstigation re
nvestigation a constructio
f a disposalith RER, Scess, and Qration. Afte
and OL of sign of a direments aoncepts of environmen
ility, etc., ame of applic
OL, should
or technicalis required
, etc. prior val togethereport. The report. Aft
on site to the
facility, etcSAR, regulaQuality Asser review by
a disposaldisposal facnd technicdesign, im
ntal impactand proposacation for pcontain the
specificatiod a change
to CP andr with RadiKINS con
ter review be applicant.
c., should suations on ssurance Proy the KINS
l facility, ecility, etc. acal standardmplementatiots resulting al on minimprior approve opinion o
ons that affpermit from
d OL, iation
nducts by the .
ubmit safety ogram S, the
etc. is are in ds. It on of from
mizing val for of the
fect or m the
E.2.4
Regupreopperio
The pbeenequiptechnand p
The dis in Act adispo
The faciliNSAwith dispothe p
The disporegul
4 Regulato
ulatory inspperational odic inspect
preoperation progressedpment and nical standaperformance
disposal insconformityand subordose of radio
periodic inity, etc. is m
A, whether sthe techni
osal facilitypreoperation
QA inspecosal facilitylatory body
Preoperat
Disposal I
Periodic I
QA Inspe
ory Inspec
pections for inspection
tion, QA ins
onal inspectid according
performanard. The Pree.
spection is cy to all relatedinate statutoactive wast
nspection ismaintained storage, treical level ry, etc. is manal inspectio
ction is cony, etc. carriey.
tional Inspe
Inspection
nspection
ction
ctions
a disposal ffor const
spection, an
ion is condug to the connce of a deoperational
conducted ted technicale when the
te.
s conductedproperly acatment andeferred to aintained inon.
nducted to es out QA
ection
- 49 -
facility, etctruction annd daily insp
ucted to verntent of CP
disposal facl Inspection
to verify whl standards
e operator o
d to verifyccording to d disposal oin the NSA
n a state wh
check whetactivities a
. under connd performpection by r
rify whetheP and to chcility, etc. n consists of
hether the dstipulated in
of the dispo
whether ththe technic
of radioactivA and whehich a dispo
ther an conaccording to
struction orance, dispo
resident insp
er the constrheck whethis in confof inspection
isposal of rn the Nucle
osal facility
he operatiocal standardve waste arether the peosal facility
nstructor ano the QAP
r in operatioosal inspepector.
ruction worher the struformity withn for constru
radioactive wear Safety rey, etc., inten
on of a disds referred tre in confoerformance
y, etc. has p
nd operatorsubmitted t
on are ction,
rk has cture, h the uction
waste elated nds to
sposal to the
ormity of a
passed
r of a to the
The constinspeabno E.2.5
Afterpermnecemay meas If it nuclesubmthe dto takresul The speciof a dcauseimpo
The Nrelev
daily inspetruction or ections, invormal state,
5 Enforce
r a safety remit to the ap
ssary for saorder the l
sures in acc
is deemed ear enterpri
mitted documdocuments ake correctivlts.
NSSC mayifying a perdisposal face a grave inose a penalty
When twhich r
When th
When tconductinspecti
When ththe regu
NSA descrivant provisio
Daily Insp
ection by rein operati
estigation oand adequa
ment
eview of apppplicant. Theafety. If violicensee of ordance wit
necessary fser to submments. The are in confove or compl
y order theriod not exccility, etc. fanconveniency surcharge
the construcrequires app
he construc
the construt a correction;
he construculations on s
ibes details ons.
pection by
esident inspion on a dof the measuacy verificat
plication foe NSSC ma
olation has ta disposal th the NSA.
for enforcemmit necessary
NSSC mayormity to aclementary m
e revocatioeeding one alls under ace or to be
e in lieu of th
ctor and opeproval witho
tor and ope
uctor and otive or co
ctor and opesafety meas
of penalty
Resident In
- 50 -
pectors is todaily basis.ures taken wtion of radia
or CP and Oay impose mturned out afacility, etc.
ment of nuy document
y also conductual condit
measures, if
on of licenyear, in a c
any of the bedetrimenta
the suspensi
erator has cout obtainin
erator has fa
operator hasomplementa
erator has vsures during
and/or fine
nspectors
o check a d. It includewhen the diation safety
OL, the NSSminimum coas a result oc. to take co
uclear safetyts on its busuct regulatotions, and o
f any, in acc
se or the case where telow items.l to the pubion of busin
changed theng approval;
ailed to mee
s violated ry action
iolated the g operation
to be impo
disposal faces observatisposal facicontrol acti
SC may granonditions thof the inspeorrective or
y, the NSSCsiness and try inspectio
order the nucordance wi
suspension the construcIf such me
blic interestness.
e matters, a
t the standa
the order oas a resul
conditions fof a disposa
osed for any
cility, etc. ution of perility, etc. is ivities.
nt a certificherein, if deection, the Nr compleme
C may ordeto supplemeons to verifyuclear enterpith the inspe
of businesctor and opeeasure is likt, the NSSC
any of chan
ards for licen
of the NSSlt of regul
for the permal facility, e
y violation o
under riodic in an
ate of eemed NSSC entary
er the ent all fy that priser ection
ss by erator ely to
C may
nge of
nse;
SC to latory
mit or etc.
of the
- 51 -
E.2.6 Allocation of Responsibility
The NSA and the RWMA prescribe definitely where the responsibility lies for each stage of radioactive waste management. Under the NSA, the NSSC is responsible for CP an OL, and safety-related regulations of a disposal facility, etc. As a professional regulatory agency for the NSSC, the KINS perform safety-related regulatory activities as entrusted by the NSSC. According to the RWMA, MOTIE has the responsibility of formulating basic policies regarding radioactive waste management including estimated amount of radioactive waste generation and construction plan of disposal facilities. The KORAD is responsible for radioactive waste management business. E.2.7 Clearance
The clearance of radioactive waste, as shown in Section B.4, is incorporated into the concept “self-disposal” in the NSA. The same criteria for dose rate in IAEA Safety Series No. 115 (1996) are applied to self-disposal.
1.
2.
E.3.
The Orgaautho
The NstandNSSC(site
E
ARTICLE
Each Coentrustedframeworauthority,assigned Each Conframeworindependorganizatmanagem
1 Authorit
authority oanization anority is as fo
to issueutilizatimeasure
to concbodies,
to obtaorganiz
to mainorganiz
to accereview.
NSSC assumdards for saC also has sselection, d
E.3 Re
E 20. REGU
ntracting Pd with therk referred competen responsibntracting Prk, shall t
dence of ttions are ment and in
ty and Res
of the NSSnd Enforceollows:
e, suspend ion facilitieses;
clude agreemand to entru
ain documations, or p
ntain contacations; and
ss to any n
mes responafety measursafety reguldesign, cons
egulatory
ULATORY
Party shale implemed to in ARnce and f
bilities. Party, in acake the ahe regulatinvolved
n their regu
sponsibility
C as the reement Regu
and revoks, and to m
ments withust tasks to
ments and ersons that
ct with fore
nuclear pow
nsibility for res in respelation respostruction, op
y Body (A
- 52 -
Y BODY
l establishentation ofRTICLE 1financial a
ccordance appropriatetory functiin both s
ulation.
y of the Re
egulatory bulations of
ke a licensmake an orde
h other domother organ
opinions may be nec
eign regula
wer utilizati
developmenect to operaonsibility regperation, clo
Article 20
h or designf the legi9, and prnd human
with its lege steps toons from
spent fuel
egulatory
body is spethe NSSC
se or CP aer to take co
mestic govenizations if n
from pubcessary;
atory bodies
ion facilitie
nt of criterition of a digarding radosure, and d
0)
nate a regslative anrovided w
n resource
gislative ao ensure other func
or radioa
Body
cified in th. Main con
and OL ofomplementa
rnment or necessary;
blic organiz
s and releva
es that is li
a for CP / Osposal facil
dioactive wadecommissio
gulatory bond regulat
with adeques to fulfill
nd regulatthe effectctions whactive wa
he NSA anntents of N
f nuclear pary or corre
non-govern
zations, pr
vant internat
icensed or u
OL and techlity, etc. Anaste manageoning).
ody ory ate its
ory tive ere
aste
nd the NSSC
power ective
nment
rivate
tional
under
hnical nd the ement
- 53 -
E.3.2 Structure and Resources of the Regulatory Body and Supporting Organizations
E.3.2.1 NSSC
The Korean government grants the NSSC to take full responsibility for safety regulation administration for nuclear power utilization facilities according to the Act on the Establishment and Operation of Nuclear Safety and Security Commission (Statute No. 11715). The members of the NSSC are appointed among those who have in-depth expertise and experience in nuclear safety. Members from various fields that can contribute to nuclear safety such as nuclear energy, the environment, public health, science and technology, public security, law, and social & human sciences are to be evenly appointed to the NSSC. The Chairman is appointed by the President among the nominees referred by the Prime Minister. Four members including the standing member are appointed by the President with the referral of the Chairman of the NSSC, while the rest four members are appointed by the President with the referral of the National Assembly. It is prescribed that those who are working or worked as the head or employee of the nuclear operator, or the nuclear operator groups within the recent three years; or who are being involved or were involved in the projects performed by the nuclear operator or the nuclear operator groups within recent three years including research and development projects entrusted by the nuclear operator or the nuclear operator groups should not be appointed as a member of the NSSC. The term of office of the NSSC members should be three years, and they may be reappointed once. AS of March, 2014, the NSSC is composed of nine members including the Chairman. The Chairman and one member are standing members. The standing member holds an additional position of the Secretary General. The Secretariat, which deals with the general affairs of the NSSC, consists of two bureaus, one office, four officers, nine divisions and four site offices, staffed with 141 persons as shown in Figure E.3-1.
The Nsafetsafetutiliznucle(DeleInstitsafegInstit7 (Du The NBure
Figure
NSSC entruty reviews ity inspectionzation faciliear power egation of tutions) of guard and ptute of Nucluties of KIN
NSSC are meau, Plannin
e E.3-1. Org
usts professin relation ns in relatioities and R&
utilization Authority)
f its Enforchysical protlear Non-prNAC) of the
mainly comng and Coo
ganization C
ional and teto license a
on to fabrica&D for tech
facilities of the NS
cement Dectection of nroliferation e NSA.
mposed of Nrdination O
- 54 -
Chart of the
echnical tasand permit ation, consthnical standto the KIN
SA and Artcree. Mean
nuclear relatAnd Contro
Nuclear RegOffice and f
NSSC (As
ks for nucleof nuclear ruction and
dards in relaNS in accticle 153 (nwhile, theted facilitiesol (KINAC)
gulatory Bufour site off
of June 30,
ear safety repower utili
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e NSSC ens and mater) in accorda
ureau, Radiafices under
, 2014)
egulation suization faciof nuclear p
fety regulatiwith Articleion of Entrntrusts taskrials to the Kance with A
ation Emergwhich divi
uch as lities,
power ion of e 111 rusted ks for Korea
Article
gency isions
are cassesregulradiotasksas fo
charged wissment, inslations on oactive wass of the NSollows;
Establi
Develoand the
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Mattersnuclearfuel cyc
Matters
Mattersincidenreactor
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Mattersresearcfacility
Mattersand rela
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Nuclear S
Nuclear S
License R
ith nuclear spection an
the use otes, and preSC related
ishes the obj
ops the Come detailed pr
ops and coor
ees, coordin
ains and imp
cts the reser safety.
s concerninr power, rescle facility.
s concerning
s concerninnts & failur
and related
s concerninr power, res
s concerninh or educa
y.
s concerninated faciliti
s concerning
Safety Policy
Safety Divis
Review Divis
safety regund enforcemof radiationeparation anto radioacti
jectives and
mprehensiveromotion pl
rdinates the
ates and ma
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arch, analy
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g periodic s
ng investigares in the opd facilities a
ng safety research or ed
ng QA inspeation reacto
ng license fes.
g permit for
y Division
ion
sion
- 55 -
ulatory actment, develn, radiationnd managemive waste a
d direction o
e Nuclear Salan of Comp
e basic polic
anages polic
s and system
ysis, plannin
spections anducation rea
safety asses
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and nuclear
egulations oducation rea
ections andor and rela
for nuclear
r nuclear fu
tivities suchlopment ofn protectioment of em
and nuclear
of a nationa
afety Plan, tprehensive N
cy on nuclea
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ms concernin
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sments of N
evaluationf nuclear pofuel cycle f
on shutdowctor and rel
d follow-up ated faciliti
power, res
uel cycle pro
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spent fuel
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the executioNuclear Saf
ar safety.
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oject.
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s. The nt are
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Mattersand rela
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Establienviron
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Mattersdecomm
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Safety Sta
Radiation
Environm
s concernins for nucleaclear fuel cy
s concerninand related
s concerninated faciliti
s concerninss.
s concernination of use
s concerniny of radioact
s concerninal.
ops and coor
ains and imp
s, analyzes,
s concernin
shes and ortation of ra
shes and exnmental rad
es R&D p
s concerninmissioning
s concernin
andard Div
Safety Div
mental Radia
ng investigaar power, reycle facility
ng standardsd facilities.
ng standardses.
ng standards
ng standardof nuclear s
ng standardstive waste a
g technical
rdinates bas
proves laws
plans and e
g complian
operates adioactive m
xecutes polidiation, radio
projects reg
ng safety reof nuclear r
ng safety r
ision
vision
ation Safety
- 56 -
ation of incesearch or e
y.
s for CP of
s for OL o
s for permi
ds for permsource mate
s for permiand accessor
standards f
sic policy re
and system
executes R&
nce of intern
a monitomaterial.
icies and syoactive was
garding env
egulations freactor and
regulations
y Division
idents·failueducation r
f nuclear po
f NPPs, res
it or design
mit of nucerial.
it for storagry facility.
for package
egarding rad
ms regarding
&D projects
national con
ring syste
ystems regarste and spen
vironmental
for wastes related faci
for transpo
ures during reactor and
ower, resear
search or e
nation of nu
lear fuel m
ge, processi
and transpo
diation safet
g radiation s
regarding r
nventions on
em for th
rding safetynt fuel.
l radiation
generated lities.
ort, storage
the construrelated fac
rch or educ
education re
uclear fuel
material an
ing and dis
ort of radioa
ty.
safety.
radiation sa
n radiation s
he transnat
y manageme
and radioa
from closu
e, treatment
uction ilities
cation
eactor
cycle
d for
sposal
active
afety.
safety.
tional
ent of
active
ure or
t and
disposa
Mattersand dis
Mattersdisposa
Mattersfor radi
Mattersmanage
Develoradiolo
Manag
MaintaNationa
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Establineighbo
Develo
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Establimeasur
Matterscountri
Admini
Nuclear E
Nuclear S
Site Office
al of radioac
s concerninsposal facilit
s concerninal facility of
s concerninioactive wa
s concerniement of sp
ops, compigical emerg
es radiologi
ains and mal Emergen
s regarding es, and mony.
shes and oporing count
ops and exec
ops and execr safeguard.
sh and exres
s regardingies.
istrative aff
Emergency
Safeguard &
es
ctive waste.
g permit anty of radioa
g safety regf spent fuels
g design apste.
ng complient fuel and
iles and cgency prepa
ical emerge
manages emcy Managem
environmennitoring and
perates a syry.
cutes plans
cutes plans
ecutes poli
detection
ffairs conce
Division
& Export Co
- 57 -
.
nd supervisioactive waste
gulations fors.
pproval and
iance of id radioactiv
coordinatesaredness.
ency situatio
mergency rment Comm
ntal impact d assessmen
ystem to re
for nuclear
and operate
icies regar
and analysi
erning on-si
ontrol Divis
on of storage and related
r storage fa
inspection
internationave waste.
s plans fo
ons.
response ormittee (NEM
assessmentnt of environ
espond to a
Non-Prolif
es laws and
ding IAEA
is of nuclea
ite safety re
sion
ge facility, td facility.
cility, treatm
of transport
al convent
or national
rganizationsMC).
t of surrounnmental rad
a radiologic
feration Reg
d systems re
A and tran
ar activities
egulations
treatment fa
ment facilit
rtation conta
tions on s
l and reg
s including
ndings of nudiation acros
cal accident
gime.
egarding nat
nsnational s
s of surroun
for reactor
acility,
ty and
ainers
safety
gional
g the
uclear ss the
t in a
tional
safety
nding
s and
- 58 -
related facilities, nuclear fuel cycle facilities as well as facilities for storage, treatment and disposal facilities of radioactive waste and auxiliary facilities.
Administrative affairs concerning protection of nuclear material and facilities as well as on-site regulations of radiological emergency preparedness.
E.3.2.2 Korea Institute of Nuclear Safety (KINS)
The KINS was established in February 1990 as a professional regulatory agency, under the Act on the Establishment of the KINS. The KINS performs tasks on nuclear safety regulation as entrusted by the NSSC in accordance with the NSA and subordinate statute. Its major functions in relation to nuclear safety regulation are as follows:
Nuclear facility safety regulation - Review and inspection of NPPs - Review and inspection of nuclear fuel cycle facility and research reactor,
etc.
Radiation safety regulation - Confirmation of safety in the use of RI - Review and inspection of disposal facility, etc.
Radiation emergency response - Emergency response and preparedness for radiological accident and
terrorism - Monitoring of environmental radioactivity throughout the territory and area
near NPPs - Detection of nuclear tests and nuclear accidents in neighboring countries
Nuclear safety regulation research and development and professionalization - Development of safety regulation criteria and techniques - Development of safety regulation policy and system, cultivation of
professional human resources
National technical qualification examination
- License examinations related to operation of nuclear power utilization facilities and handling of nuclear materials
- National technical qualification examinations related to nuclear power
Enhancement of global leadership and national trust - Enhancement of contribution and support of regulatory techniques to the
international community - Programs to spread safety culture as well as enhance public trust
The KINS is comprised of 442 staff members as of the end of July 2014 and Figure E.3-2 shows the organization of the KINS
- 59 -
To share its safety regulatory techniques and experience with the international community, the KINS opened the International Nuclear Safety School in January 2008, which has also functioned as the IAEA’s Asian training center since conclusion of a Nuclear Safety Cooperation Agreement with the IAEA. The safety regulation of radioactive waste management facilities is under the responsibility on the Radiation and Waste Safety Division, Department of Radiation Protection and Radioactive waste Safety Evaluation and Department of Radiation Application Safety Evaluation in the KINS. The budget of the KINS comes from the government.
Figure E.3-2. OOrganizatio
- 60 -
on Chart of KKINS (As off June 30, 22014)
- 61 -
E.3.3 Regulatory Independence
The NSA, APPRE, Nuclear Liability Act specify that the NSSC takes legal responsibility for nuclear regulation. On the other hand, MOTIE shoulders responsibility for nuclear power industry and for radioactive waste management in accordance with the Electric Business Act and the RWMA, respectively. In other words, the functions of the NSSC which is responsible for nuclear regulation and the MOTIE which is responsible for promotion of nuclear power generation are legally divided under the provisions of the Government Organization Act and its subordinate provisions. In the NSA and related laws, the authority for nuclear safety regulation is given to the NSSC, and the NSSC is also in charge of making decisions for nuclear safety. The KINS conducts regulatory operations concerning nuclear safety and control as entrusted by the NSSC based on the NSA and related laws. The KINS was established and is operating as an independent professional regulatory agency.
FSF. OthSafety
her Gy Pro
Geneovisio
ral ons
1.
2.
F.1.
Pursuthis Ndurinviolacompfacili The manaaccordisporespospent
F
ARTICLE
Each Cosafety of holder ofensure th
If there responsibthe spent
1 MechaniPermit
uant to the National Rng the conations occuplementary ity.
licence holdagement ofrdance withosal facilityonsibility act fuel).
F.
F.1 Re
E 21. RESP
ontracting spent fuef the relevhat each su
is no sucbility rests t fuel or ov
ism for thHolder wi
NSA, the NReport to ennstruction aur, the NSS
measures
der of a nuf spent fuh related lay. The opecceptance,
. Other
esponsib
PONSIBIL
Party shael or radiovant licencuch licence
ch licencewith the Cer the radi
e Regulatll Meet its
NSSC carriensure that thand lifetimSC immediso as to se
clear poweruel and radaws before erator of a treat, storag
r Gene
bility of th
- 65 -
LITY OF TH
ll ensure oactive wace and shae holder me
e holder oContracting
oactive wa
ory Body ts Primary
es out regulhe operator
me of the niately orderecure the sa
r utilizationdioactive wthey are trradioactive
ge and disp
ral Saf
he Licens
HE LICENC
that primeaste manaall take theets its res
or other Party whi
aste.
to Ensure Responsib
latory inspecomply w
nuclear pors the operafety of the
n facility hawaste generansferred te waste maposal of rad
fety Pr
se Holde
CE HOLDE
e responsagement ree appropr
sponsibility
responsiblch has jur
that the Lbility for S
ctions descrith regulatower utilizarator to take nuclear po
as the responrated durinto a storaganagement dioactive w
rovision
r (Article
ER
ibility for ests with riate stepsy.
le party, risdiction o
License orSafety
cribed in E.2ory requiremation facilitke correctivower unitiz
onsibility forng operatio
ge, processinfacility ha
waste (excep
ns
e 21)
the the
s to
the ver
r
2.4 of ments ty. If ve or zation
r safe on in ng or
as the pt for
- 66 -
F.1.2 Ultimate Responsibility
“Nuclear Safety Policy Statement”(Annex E) declared in 1994 specifies that “The ultimate responsibility for the safety of a nuclear facilities rests with the licensee and this is in no way diluted by the separate activities and responsibilities of designers, suppliers, constructors and regulators. The Government has an overall responsibility for ensuring the protection of the public health and the environment from radiation hazards that may occur in the development of nuclear energy”. According to the 249th meeting of the AEC, the Korean government adopted the State’s ultimate responsibility of radioactive waste management in light of the fact that these wastes are needed and that they require long-term safe management. The Minister of Trade, Industry and Energy should establish the basic plan for radioactive waste management to manage radioactive wastes safely and effectively which are deliberated and decided on at the meeting of the Atomic Energy Commission.
Ea
F.2.
As thfour Humshow
In thEnvirespodurinappropreparespo At amemmana
F
ARTICLE
ach Contra
(i) qualifieduringmanag
(ii) adequfacilitieoperat
(iii) financinstitutthe pefacility
1 Nuclear
he sole NPPnuclear po
man Resourcwn in Figure
he head offironment Donsibilities ng operationoximately aredness foonsible for m
a power plambers engagagement, a
F.2 Hu
Organizat
E 22. HUM
cting Party
ed staff ag the operagement fac
uate finances for spenting lifetimeial provistional conteriod deemy.
r Power Re
P operator ower sites, ce Develope F.2-1.
ice, the KHDepartment
for radiation of NPPs. five staff
or NPPs. Smanagemen
ant level, tges in hea
and among
uman an
tion and Hu
AN AND F
y shall take
are availabating lifetimcility; cial resourcnt fuel and e and for dion is mrols and mmed neces
eactor Fac
in Korea, thand special
pment Instit
HNP operatewhich con
on safety mThe Radiomembers
Spent Fuel nt of Spent F
the Radiatioalth physic
them, five
d Financ
uman Reso
- 67 -
FINANCIA
e the appro
ble as neeme of a sp
ces are a radioactiv
decommissmade whicmonitoring ssary follo
cilities
the KHNP hl institutes tute and R
es the Radiansists of ap
managementological Em
also takes Team whFuel.
on Safety cs, radiatioe members
cial Reso
ources
AL RESOU
opriate ste
eded for spent fuel a
vailable toe waste m
sioning; ch will enarrangemeowing the
has seven dincluding C
Radiation H
ation Safetypproximatel and manag
mergency Res charge ohich consis
Team staffn protectio
s are in ch
urces (Ar
RCES
ps to ensu
safety-relaand a radio
o support anagemen
nable the ents to be
closure o
divisions in Central Resealth Resea
y Team undly 10 staffgement of Lesponse Teaof radiologts of 4 st
fed with apon, and raharge of ra
rticle 22)
ure that:
ated activitoactive wa
the safetynt during th
appropricontinued
of a dispo
the head osearch Instiarch Institu
der the Safef members LILW geneam consistigical emergtaff membe
pproximateladioactive wadioactive w
ties aste
y of heir
ate for
osal
office, itutes, ute as
ety & with
erated ng of gency ers is
ly 20 waste waste
manaalso pthe drelies
At eaundeemeremer
agement suplanning to
disposal facs on contrac
F
ach power er the Genergency preprgency staff
ch as radioo establish aility. For mctors such a
Figure F.2-1
site, the Emeral Adminparedness sf. The NPP
active wasta team in eacmaintenance as KEPCO P
. Organizat(As of D
mergency Prnistrator Desuch as radoperating o
- 68 -
te treatmentch power si of radioactPlant Servic
tion Chart oDecember 3
reparednessepartment tdiological
organization
t and tempoite to take chtive waste rce & Engine
of the KHNP31, 2013)
s & Environto take respemergency
n is shown in
orary storagharge of delrelated facileering Co., L
P Head Offic
nment Teamponsibility
exercises n Figure F.2
ge. The KHNelivering walities, the KLTD (KPS)
ce
m is put in for radioloand trainin
2-2.
NP is aste to KHNP ).
place ogical ng of
Fig
Sincefuel has aElect As thhousto thmanacost spentand tfuel effec
ure F.2-2. O
e 1983, the generated iaccumulatetricity Busin
he Radioacte liability w
he RWMA, aging radioato the Fundt fuel shoulthen transfesmoothly.
ctuation of
Financial
Organization
KHNP hasin the operad this cost ness Act (E
tive Waste was convertthose who active wasted. As for spld be imposerred to the
Meanwhilthe RWMA
Resources
n Chart of a
s deposited ation and d
as in-housBA).
Managemeed into the have genere to the KOpent fuel gesed on the KFund to im
le, the conA should be
- 69 -
a Nuclear P
the cost reqdecommissiose liability
ent Act camRadioactive
rated radioaORAD whicenerated byKHNP as "S
mplement prntribution fe paid by t
ower Site (A
quired for doning procein accorda
me into effece Waste Maactive wasteh should, in
y the KHNPSpent Fuel rojects relatfor spent the KHNP
As of Decem
disposal of Lesses on a ynce with th
ct in 2009, hanagement Fe should tran turn, pay tP, the cost oManageme
ted to manafuel generafor 15 year
mber 31, 20
LILW and yearly basihe provisio
however, thFund. Acco
ansfer the cothis manageof managin
ent Contribuagement of ated beforers from the
013)
spent s and
ons of
he in-ording ost of ement ng the ution" spent e the e date
when The accum F.2.2
The wastefaciliorgan
n five years
KHNP alsomulated thi
2 Nuclear
KAERI hase, includingities. Figurenization.
Figure
has passed
o deposits ts cost as in-
r Research
s several fag HANARe F.2-3 pres
F.2-3. Rad
since the e
he cost of p-house liabi
h Facilities
acilities relaO, the PIEsents KAER
ioactive Wa
(As o
- 70 -
ffectuation
plant decomility.
s
ated to manEF, and radRI’s spent fu
aste related
of June 30,
of RWMA.
mmissioning
nagement ofdioactive wfuel and rad
Organizati
2014)
.
g on a year
f spent fuelwaste treatm
ioactive wa
on Chart of
rly basis an
l and radioament and staste manage
f KAERI
nd has
active orage ement
HA
Withfor Hreactradiothe H
PI
The Techmainare arespomanaincluare irelevmoniPIEF
Ra
12 stnucletreatmbitumdecomanawith
Co
Begiundecombcomb2 andmana
ANARO
h 40 staff mHANARO Utor. Radioaoactive wastHANARO M
IEF
Material Phnology Devntained by nassigned acconsible for agement anuding nucleain charge ovant examinitoring, wat
F are perform
adioactive W
taff membeear Materiament and minization, ntaminationagement, enrelated dep
ombustible
nning in 2er CTO forbustible wabustible wad the UCF.agement, an
Human R
members, theUtilization iactive wastte storage f
Managemen
IE & Rad-velopment onine operaticording to th
operation nd ventilatinar material
of post-irradnation faciliter supply cmed in coop
Waste Trea
rs in The Mals Technolstorage facsolar evapo
n, radioactivnvironmentapartments of
e Waste Tre
2011, the Dr Converge
aste treatmeaste generate. In additionnd QA are
Resources
e HANAROis responsibte generatefacility. Spent Division.
Waste Dispof the KAEing and testheir expertiof supportng equipmeaccounting
diation examities. Radiatcontrol, andperation wit
atment and
Material PIEogy Develocilities, whoration, andve waste foal radiation f the KAER
eatment Fa
Decontaminaence Technent facility wed in the con, radiationprovided th
- 71 -
O Operationble for opered from Hent fuel gen
posal DivisERI operates
t/maintenanise and backting equipment as welland licensi
mination foation safety d nuclear mth related de
d Storage F
E & Rad-Wopment of hich includd compactioorm examinmonitoring
RI.
acility
ation & Denology Devwith five stourse of decn safety manhrough the
n & Mainteration and m
HANARO inerated from
sion under s the PIEF. Tnce staff mekgrounds. O
ment such al as internaing, whereaor spent fue
managemematerial accepartments
Facility
Waste Disposthe KAERI
de equipmeon (for soli
nation and vg, and QA ar
ecommissiovelopment taff membecommissionnagement, support and
enance Divimaintenances stored a
m the reacto
CTO for nThis facilityembers who
Operating stas electricaal and extes examiningels and mannt, environ
counting wiof the KAE
sal DivisionI operate rant related
id waste), cventilation. re performe
oning Technof the KA
ers to reducning researcenvironmend cooperatio
ision under e of the resat the KAEor is manag
nuclear Maty is operateose work sctaff membeal, water quernal inspecg/managingnagement o
nmental radiith regard t
ERI
n under CTadioactive wto evapor
cementationRadiation s
ed in cooper
hnology DivAERI operace the volumch reactors ntal radioacon of relate
CTO search ERI’s ed by
terials d and copes rs are uality ctions g staff of the iation to the
O for waste ation,
n, and safety ration
vision ates a me of 1 and
ctivity ed the
KAE
All fwastegove F.2.3
The KProdnucleRadiMana
RadihealtmateSectiphysestabtechnteamwasteradiafabriequip
AS pto threser
ERI departm
facilities of e storage a
ernment bud
3 Nuclear
KEPCO NFduction Diviear materiaation & Enagement Se
ation & Enth physics, erial and mion consistsical protect
blished on nology for
m consists oe as well as
ation safety cation facipment is pe
per the RWMhe KORAD rving the ma
Financial
Human R
Financial
ments.
the KAERIare in operadget.
r Fuel Fabr
F has the Raision to ovel. The Rad
nvironment ection (Figu
nvironment exposure
managements of seven stion. In addMarch 28treatment a
of nine pers developm
and safe trlity. The orformed wi
MA, the radat the deli
anagement
Resources
Resources
Resources
I for spent fuation with t
rication Fa
adiation & Eersee managiation & EnSafety Sec
ure F.2-4).
Safety Secmanageme
t of envirostaff membedition, Rad, 2011 to and disposasons with rent of decoreatment anoperation ath the suppo
dioactive wivery point expense eve
- 72 -
fuel managethe organiz
acility
Environmengement of rnvironment
ction, Safeg
ction staffeent, transpoonmental raers charged
dioactive Wmanage nu
al of radioacresponsibili
ontaminationnd storage oand maintenort from a r
waste generaof radioact
ery quarter
ement, radiozational proj
nt Managemradiation sat Managem
guards Secti
ed with 18 ort and madiation/radd with nucle
Waste Managuclear wasctive wasteities for man technologof waste genance of raradiation saf
ator should tive waste. for the disp
oactive wastject fund c
ment Departafety, radioaent Departmion, and Ra
persons ismeasurementdioactivity. ear materialgement Secte and to
e effectivelyanagement
gy to ensureenerated in adioactive fety manage
pay a manaThe KEPC
posal of was
te treatmencoming from
tment underactive wastment consisadioactive W
s responsiblt of radioaThe Safegl accountingction was ndevelop re
y. Presentlyand dispos
e managemethe nuclearwaste treatement contr
agement expCO NF has stes generat
t, and m the
r Fuel e and sts of Waste
le for active
guards g and newly elated y, this sal of ent of r fuel tment ractor.
pense been
ed.
F.2.4
The Devethe aFigur
The Kcompoperafacilihave
Figure
4 LILW Dis
KORAD elopment Inannexed agere F.2-5.
KORAD is pletion targating a radity to store been alread
F.2-4. Orga
sposal Fac
is composenstitute), LILency for ma
currently cget of late Ddwaste rece and managdy saturated
anization Ch
cility
ed of the LW Disposanaging the
onstructingDecember 2eipt/storage ge radioactd.
- 73 -
hart of KEP
head officsal Center, ae Radioactiv
g the phase I2014. Since
building thtive waste f
PCO NF (A
ce (three dand Fund Mve Waste M
I of the LILthe end of
hat it consfrom some
s of May 31
divisions anManagementManagement
LW disposalf 2010, the atructed insiNPP storag
1, 2014)
and Researct Center wht Fund as s
l facility witagency haside the dis
age facilities
ch & hich is hown
th the been
sposal s that
The Dispapprorespodispo
The dispothe dtreatmrespoprepacentecomm
The to the
KORAD hosal Centeoximately onsible for osal facility
LILW Disposal facilitydisposal faciment and tronsibility foaredness exers are engmunity coop
RWMA stie KORAD a
Figu
Organizat
Financial
has a total oer and nine50 personsoverseeing
y and 30 or m
posal Centey. The Consility. The Rransport of or radiationxercise in thaged in maperation, QA
ipulates thaat the delive
re F.2-5 Or
tion and Hu
Resources
of 270 staffe in the Fs work in g and suppmore person
er is in chastruction Ma
Receipt & Oradioactive
n safety manhe disposal anagement A, spent fue
t the radioaery point of
rganization
uman Reso
- 74 -
ff members;Fund Mana
the Radioporting consns work in t
arge of conanagement
Operation Ofe waste andnagement, efacility. Otand adminiel managem
active wastef radioactive
Chart of KO
ources
; 189 in theagement Ceoactive Wastruction anthe Research
nstruction aOffice is chffice is resp
d the Radiatenvironmenther workfoistrative sup
ment program
e generator e waste.
ORAD (As o
e head offienter. In tste Managend operatioh & Develo
and operatioharged with
ponsible for tion Safety ntal surveysorces in the pport, publm preparatio
pay manag
of May 31, 2
ice, 72 in Lthe head oement Div
on of the Lopment Insti
on of the Lh constructir receipt, stoOffice take
s and emerg head offic
lic relationson.
gement exp
2014)
LILW office, vision, LILW itute.
LILW ion of orage, es the gency e and
s, and
penses
F.2.5
The whic
The KOR F.2.6
The permgeneradioassur
5 RI Waste
RI waste mch consists o
RWMA stRAD at the d
6 Securinga Radioa
radioactivemanent clos
rator. Accooactive wasred.
Organizat
Financial
e Managem
managementof 8 staff me
ipulates thadelivery poi
g of Finanactive Was
e waste disure, thus iordingly, theste managem
tion and Hu
Resources
ment Faci
t facility is embers, of L
at a RI waint of RI wa
cial Resouste Dispos
sposal faciincurring ce RWMA inment projec
uman Reso
- 75 -
ility
operated anLILW Disp
aste generataste.
urces for Msal Facility
ility requircost shouldncludes posct and base
ource
nd managedposal Center
tor pays ma
Managemy
res institutid be coverest-closure med on which
d by RI Manr.
anagement
ent after t
onal controed by a ramanagementh mandates
nagement O
expenses t
the Closur
ol even afadioactive w
nt in the scos that cost
Office
to the
re of
fter a waste
ope of to be
Eaapan
F.3.
The faciliQA closu The ManafaciliOperFacilopera AccosubmThe const In caoperashou The constauditcontr
F
ARTICLE
ach Contrappropriate qd radioact
1 QAP
NSA stipulity should eactivities a
ure, and pos
NSSC Notagement Faity. Anotheration and lities) also ator for ope
ording to thmit a QAP
applicant truction and
ase that the ator should
uld obtain pr
licensee htruction andt the status ractors acco
F.3 Q
E 23. QUA
acting Parquality assive waste m
lates that thestablish anat the stagest-closure m
tice No. 20acilities) shoer Notice oControl of specifies o
eration and m
his provisiofor construhas the ultd operation
QAP is toreport the a
rior approva
as the respd operationand effecti
ording to the
uality As
LITY ASS
rty shall tsurance prmanageme
he constructnd implemees of site c
monitoring.
13-54 (Quaould be appf the NSSC
f Low and overall requmanagemen
n, an applicction and otimate respof a facility
be amendeamendmental from the N
ponsibility of nuclear
veness of Qe NSA.
ssurance
- 76 -
URANCE
take the nrograms coent are est
tor and opeent QAP, socharacteriza
ality Assuraplied to estaC No. 2013Intermedia
uirements tont of a LILW
cant for CPoperation ofponsibility y.
ed after grat to the NSSNSSC if rel
to abide binstallation
QAP implem
(Article 2
necessary oncerning tablished a
erator of a o as to ensuation, desig
ance Standaablish a QA 3-35 (Technte Level Ro be observW disposal f
P and OL of a radioactof comply
ant of CP aSC, except tlated with c
by the apprns, and the mentation b
23)
steps to the safety
and implem
nuclear waure plannedgn, construc
ards for Rasystem of anical Requi
Radioactive ved by the facility.
of a disposative waste ding with th
nd OL, the the construcchanges in Q
roved QAPregulatory
by the licen
ensure t of spent f
mented.
aste managed and systection, oper
adioactive Wa LILW dis
uirements foWaste Disconstructo
al facility shdisposal facthe QAP d
e constructoctor and opeQA organiza
P in the deauthority sh
nsee and its
hat fuel
ement matic ation,
Waste sposal or the sposal r and
hould cility.
during
or and erator ation.
esign, hould main
- 77 -
F.3.2 Framework of QAP
As for the framework of the QAP applicable to a LILW disposal facility, the NSSC Notice No. 2012-54 (Quality Assurance Standards for Radioactive Waste Management Facilities) stipulates 18 criteria as follows: 1) Organization, 2) QAP, 3) Design control, 4) Procurement document control, 5) Instructions, procedures, and drawings, 6) Document control, 7) Control of purchased items and services, 8) Identification and control of items, 9) Control of special process, 10) Inspection, 11) Test control, 12) Control of measuring and test equipment, 13) Handling, storage, and shipping, 14) Inspection, test, and operating status, 15) Control of nonconforming items, 16) corrective action, 17) QA records, and 18) audit, supervision and business management F.3.3 Implementation and Assessment of QAP
The licensee of a LILW disposal facility, and all contractors participating in site characterization, design, manufacture, construction, commissioning, operation, maintenance, closure, and post-closure monitoring are required to prepare and implement a QAP pursuant to the NSA. The licensee is responsible for establishing an integrated system so that all participants implement the QAP. All contractors participating in the LILW disposal project have conducted QA activities in the applicable areas of site characterization, design, fabrication, construction, commissioning, management and maintenance in operation, closure and post closure monitoring in accordance with detailed procedures based on the QAP. The QAP should be established and implemented for each contractor. Evaluation for implementation and effectiveness of this QAP is periodically conducted by the licensee itself, as well as by the contractors. The method of assessing implementation of the QAP includes quality control inspection, QA audit, QA trend analysis, and effectiveness evaluation of the QAP.
Quality control inspection is conducted by a qualified inspector on the basis of the pre-established inspection plan. Before starting the quality control inspection, the inspector selects inspection points (witness point and hold point) in the inspection plan and then executes the inspection.
QA audits for the licensee and contractors are periodically performed by an auditor independent from the tasks to be audited.
Quality trend analysis is conducted to analyze the trends and causes of conditions adverse to quality such as failures, malfunctions, deficiencies,
- 78 -
deviations, defective material and equipment, non-conformances. Based on the results of trend analysis, measures to prevent recurrence and to incorporate them into the QAP are developed so as to improve QA activities.
Assessment of QAP effectiveness is periodically conducted by the QA organization to maintain the QAP suitable for the characteristics of facilities within the scope of the QAP. Major considerations for assessment of QAP effectiveness are given to incorporate legislation and revision of related laws and regulations, corrective actions or recommendations made by the regulatory body, modifications to the QAP, and revision of applicable technical standards into QAP documents.
The responsible person of the QA organization ensures that important issues resulting from the evaluation of implementation and effectiveness of the QAP are reported to the top management so that proper actions are taken in a timely manner, and if needed, the QAP and related procedures are revised based on the results of assessment of QAP effectiveness to maintain the QAP in the best possible condition. F.3.4 Regulatory Activities
Regulatory control on QA of radioactive waste disposal is conducted through reviews and inspections by the KINS, as entrusted by the NSSC. Reviews of the QAP of the licensee of a disposal facility and inspections of the appropriateness of implementation the QAP are performed. The purpose of regulatory activities for radioactive waste disposal is to ensure that the licensee performs quality related activities in accordance with the approved QAP and each contractor participating in design, construction and/or operation of a radioactive waste disposal facility establishes and implements the QAP properly suitable for the NSA. These regulatory activities are conducted as per provisions of the NSA and subordinate statute, guidance for safety review of the radioactive waste disposal facilities, and the technical standards for QA. The safety review is conducted to verify whether the QAP of the licensee and main contractors complies with the NSA and subordinate statue as well as the safety review guidelines. It also verifies whether the QA procedures for implementation of the QAP are properly established and are practicable. The KINS performs a periodic inspection to confirm the appropriateness of implementation of the QAP with regard to a treatment, storage facility of radioactive waste in the NPPs, and a radioactive waste management facility in the research reactor facility and, QAP of the fuel fabrication facility. In the same manner, same regulations are applied to a LILW disposal facility.
In ovolunOperactivimpleUndethe Kcours
As pregulplan Systequaliqualiqualigove
order to enntarily, the rator’s QAPvities of theemented a ger the “QA KINS, qualises, conduc
part of efforlatory activin accordan
em for Facity managemity are perfoity system,ernment’s nu
Quality M
ncourage thKINS has
P. Accordine operator isgraded apprAuditor Qufied auditor
cts the QA in
rts to improities, the KInce with IAilities and ment systemormed such managemuclear safet
anagemen
he operators developedg to the guis quantifiedroach to regualification rs who havenspections.
ove reliabiliINS has dev
AEA SafetyActivities).
m to ensure as policy, o
ment, assessy regulatory
t System w
- 79 -
r to condud and utilizideline, the d and gradegulatory insp
Program” fe completed
ity and fairnveloped and
y Standards The qualitthat standa
objectives, sment and y policy.
within the R
uct performzed the Insresults of r
ed, and basepection of Qfor regulatod the specifi
ness as an d implemenSeries No.
ty managemardized tasksresponsibiliimproveme
Regulatory
mance-basedspection Guregulatory ined on whichQA activitieory personnefied educatio
organizatioted the qualGS-R-3 (T
ment plan ds regarding ities, qualityent, thereby
Body
d QA actiuidelines fonspection oh, the KIN
es of the opeel establishonal and tra
on entrustedlity manage
The Managedescribes ovregulatory
y plan withiy achieving
ivities or the of QA S has erator. ed by
aining
d with ement ement verall work in the g the
1.
2.
3.
F
ARTICLE
Each Coduring thmanagem
(i) the rafacilitsocia
(ii) no indoseshave prote
(iii) measof rad
Each Codischarge
(i) to keecon
(ii) so thradialimitastand
Each Conthe operaunplanneenvironmto control
F.4 O
E 24. OPER
ntracting Phe operatiment facility
adiation exty shall be al factors bndividual ss which ex due rega
ection; and sures are tdioactive m
ontracting es shall be
eep exposomic and shat no indtion dose
ation whicdards on ra
ntracting Pating lifetimed or unc
ment occursl the releas
perationa
RATIONAL
Party shalling lifetimy:
xposure of kept as loeing taken
shall be exceed natird to inter taken to prmaterials in
Party sha limited:
sure to radsocial actodividual shes which ch have adiation pro
Party shall tme of a regontrolled s, approprse and miti
al Radiat
- 80 -
L RADIAT
l take the me of a s
f the workeow as reason into accoexposed, inonal prescnationally
revent unpnto the env
all take ap
diation asors being tahall be ex
exceed ndue regaotection.
take approgulated nurelease oriate correcigate its ef
tion Prote
TION PROT
appropriatspent fuel
ers and thonably achunt; n normal criptions foendorsed
lanned anvironment.
ppropriate
s low as raken into axposed, innational p
ard to int
opriate stepuclear facilif radioactctive measfects.
ection (A
TECTION
te steps to or radioa
e public cahievable, e
situations,or dose limstandards
d uncontro
steps to
reasonablyaccount; ann normal sprescriptionternational
ps to ensuity, in the eive matersures are
Article 24)
o ensure tactive wa
aused by economic a
, to radiatmitation whs on radiat
olled releas
ensure t
y achievabnd situations, ns for dolly endors
re that durevent that rials into implemen
)
hat aste
the and
tion hich tion
ses
hat
ble,
to ose sed
ring an the ted
F.4.
ReguutilizNSAThesfollo
The powe
The Ematte
1 Regulati
ulations andzation facili
A, its Enforcse regulationws:
NSA prescer utilization
matters quantitireasona
matters materiaoperatio
matters materiautilizati
matters person frequen
matters
Enforcemeners necessar
matters
matters the pubpower u
matters radiatioaccess t
matters in nucl
Nuclear S
ions and R
d requiremenities that gecement Decns and requ
cribes matten facilities,
concerninies of releaably achieva
concerninls and theon of nuclea
concerningls, and the pion facilities
concerningwho is em
nt access to r
concerning
nt Decree ory to implem
concerning
concerningblic from radutilization fa
concerninon workers ito radiation
concerninglear power
Safety Act (
Requireme
nts related tenerate spencree, its Enfuirements m
ers concernas follows:
g protectivased radioacable (ALAR
ng safety me public froar power uti
g establishmpublic froms,
g registratimployed by radiation co
g training an
f the NSA pment the de
g dose limits
g measures diation hazaacilities;
g measuresin nuclear pcontrol area
g medical chutilization
NSA)
- 81 -
ents
to radiationnt fuel and forcement R
meet IAEA
ning radiatio
ve measurective mater
RA);
measures nom radiatioilization fac
ment of excm radiation h
on of dosinuclear po
ontrol area;
nd education
prescribes mlegated mat
s in related
necessary tard that ma
s necessarypower utiliza and reside
heckup and facilities
protection radioactive
Regulation,standards a
on protectio
es against ial, etc. and
necessary ton hazard
cilities;
clusion areahazards, wh
meter readower utilizaand
n of worker
matters deletters as follo
to radiation
to protect hay accompa
y to minimation facilitents in adjoi
exposure cand person
applicable te waste are and Notice
and they are
on to be ap
radiation hd exposure
to protect that may
a to protecthen installin
ding serviceation facilit
rs exposed t
gated by theows:
n exposure (
uman bodieany the oper
mize radiatities, personsining areas
ontrol for rans who fre
to nuclear p specified ies of the Ne summariz
pplied to nu
hazards to dose as lo
human boaccompany
t human bong nuclear p
e provider ties or who
to radiation.
he NSA and
(see Table F
es, materialration of nu
ion exposus who frequof the facili
radiation woequent acce
power in the
NSSC. zed as
uclear
keep ow as
odies, y the
odies, power
for a o has
.
other
F.4-1);
ls and uclear
ure to uently ities;
orkers ess to
- 82 -
radiation control area;
matters concerning measurement of radiation dose and contamination levels for radiation hazard areas of nuclear power utilization facilities, and concerning about performance inspection of dosimeter reading service providers;
matters concerning implementation of protective measures against radiation hazards, such as action or report with regard to a person who are over exposed; and,
matters concerning education and training of a radiation worker and a person with access to radiation control area.
Table F.4-1. Dose Limits
Item Radiation Worker
Person with
frequent access and
engaged in
transport
Public2)
Effective dose limit
100 mSv for five
consecutive years1)
and
not exceeding 50 mSv/y
12 mSv/y 1 mSv/y
Equivalent dose limit – lens of the eye – skin, feet, and hands
150 mSv/y
500 mSv/y
15 mSv/y
50 mSv/y
15 mSv/y
50 mSv/y
1) “Five consecutive years” means the 5-year period from any given year (for example,
1998∼2002). This calculation is not applicable to any period before 1998. 2) As for the general public, the value of over 1 mSv in a single year is acceptable within the
limit of not exceeding 1 mSv per year for the average of values for five consecutive years.
The EReguReguregulnecestand
Enforcemenulations onulations onlations of thssary for imdards thereo
detailedworkers
detailedcontami
detailedRegulat
detailedradiatio(Enforc
details othe NSA
detailedradiatiofacilitieetc.);
detailedcontrol TechnicTechnic
detailedwith freFacilitie
detailedand relaStandar
Ordinance
nt Regulation Technicaln Technicalhe NSSC. Tmplementingof:
d provisionss or persons
d provisionsination leve
d provisionstion of the N
d provisionson workers,cement Regu
of medical A).
d provisionson exposurees (Regulati
d provisionsarea with
cal Standarcal Standard
d provisionsequent accees, etc.); and
d provisionsated facilitierds for Nucl
es of the Pr
on of the NSl Standardsl Standard
These Regulg the NSA a
s on assesss with frequ
s on place el (Enforcem
s on technicNSA);
s on substa, or personulation of th
check-up f
s on radiate in the reacions on Tec
s on the parhin nuclearrds for Nuds for Radia
s on radiatess (Regulatd
s on measures, and nucllear Reactor
rime Minist
- 83 -
SA is the ors for Nucl
ds for Radlations prescand its Enfo
sment and cuent access (
and personment Regula
al capabiliti
ance and dns who hahe NSA);
for radiation
tion protectctor and rechnical Sta
rticulars abr power uuclear Reaation Safety
tion protecttions on Te
res related tlear fuel cycr Facilities,
ter and Reg
rdinance of lear Reacto
diation Safecribes detailorcement De
control of e(Enforceme
nnel for meation of the
ies for dosim
duration of ave access
n workers (
tion equipmelated facilitndards for
out and theutilizationactor Faciliy Manageme
tion for radechnical Sta
to radiation cle facilitiesetc.).
gulations of
f the Prime Mor Facilitieety Managled proceduecree, and d
exposure dont Regulati
easuring radNSA);
meter readin
education to radiatio
(Enforcemen
ment for prties, and nuNuclear Re
e actions takfacilities (ties, etc.; ent, etc.);
diation workandards for
protection s (Regulatio
f the NSSC
Minister, anes, etc. andgement, etcures and medetailed tech
ose for radiion of the N
diation dose
ng (Enforce
and traininon control
nt Regulati
rotection aguclear fuel eactor Faci
ken for radi(RegulationRegulation
rkers, or peNuclear Re
plans for reons on Tech
C
nd the d the c. are ethods hnical
iation NSA);
e and
ement
ng for area
ion of
gainst cycle lities,
iation ns on ns on
ersons eactor
eactor hnical
Noticspeciprinc
The limitleveldose dose ordercorre F.4.2
The constmainappli
ces of the ified in thecipal Notice
Standar
Notice o
Notice o
Radiolo
RegulatService
Regulatetc.
TechnicShips, e
Standards ot values withl, ECL, ann
limits of slimitation
r to preventesponding fa
2 RadiatioNuclear
below radtruction of
ntaining theicable limits
radioactpartition
installatcontaini
Notices of
ALARA Ac
NSSC pre NSA, its
es related to
rds on Radia
on Material
on Uses and
ogical Prote
tion on ReProvider
tion on the
cal Standaretc.
on Radiationh regard to
nual limits oshields, but and workint any envir
facilities are
on Protectir Power U
diation prof nuclear exposure ds:
tive equipmn,
tion of shieling large am
f the NSSC
ctivities for
esent detais Enforcem radiation p
ation Protec
ls exempted
d Capacity e
ction Criter
egistration S
Education
rds on Rad
n Protectionradiation pr
on intake (Aalso the de
ng proceduronmental h
e specified.
ion Frametilization F
otection pripower uti
doses to rad
ment to be
lds to attenumounts of ra
C
Radiation W
- 84 -
iled technicment Decreeprotection ar
ction, etc.
d from RI, e
exempted fr
ria for Long
Standard a
and Traini
diation Safe
n, etc. concrrotection su
ALI), deriveetails of theres in emerghazard, the c
ework at EFacility
inciples areilization fadiation wor
installed s
uate fully thadioactivity
Workers an
cal standare, and Enfre as follow
tc.
rom Radiati
g-term Safet
nd Inspecti
ing for Rad
ety Manage
retely definuch as allowed air concee method togency radiacriteria app
Each Stage
e incorporaacilities, forkers and th
separately i
he radiation y,
nd the Pub
rds of radiforcement R
ws:
ion Generat
ty on LILW
ion of Dos
diation Safe
ement of L
e not only twable surfacentration (Do apply dosation work. plicable to th
e of Manag
ated into or assuringhe general p
in a shielde
from pipin
lic
iation proteRegulation.
ting Device
W Disposal
simeter Re
ety Managem
LILW Tran
the referencce contamin
DAC), and dse limits anAdditional
the design o
gement of
the designg ALARApublic below
ed room w
ng and equip
ection . The
s
ading
ment,
nsport
ce and nation design nd the lly, in of the
f
n and and
w the
with a
pment
Ra
It is contrrelate
Ra
It is rperfoworkradiapersoenvirradiapersogivinwhic
Do
As pmanaand pbeencolleadditmonithosemana
Pe
Expoopera
use of r
installat
installat
radiatio
adiation Pr
required trol area shoed Act and
adiation W
required thaorm a radiatk permit (RWation level, onnel evaluronment anation proteconnel can fng work perch high radia
ose Reduct
part of efagement exprovision o
n implementective dose, tion to a pritor exposue who are agement.
ersonnel Do
osure dose oating limits
Individua
emotely con
tion of vent
tion of a con
on control ar
rotection T
that radiatioould take aSubordinate
Work Manag
at any persotion work sWP). This iand workin
uates the exd characterction traininfurther imprmission. Mation expos
tion
fforts to rxperience, reof radiation ted. In addand managrimary dosi
ure during likely to e
ose Contro
of a radiatio which are
l Dose Con
ntrolled equ
ilation facil
ntinuous rad
rea shall be
raining
on workersappropriate e Statute.
gement
on who inteshould obtas prepared sng area conxpected dosristics of theng and meose special
Mock-up traiures are exp
reduce expesearch andprotection
dition, targeed as indicaimeter, an a work to
exceed 16 m
l
on worker inlower than
trol
- 85 -
uipment and
lities in area
diation mon
established
s and persoradiation p
ends to haveain approvalseparately i
nditions. Fose of an ape workplace
edical checkl conditionsining is conpected.
posure dosed introductitraining to
et doses areators of the electronicensure effe
mSv of exp
n a nuclear legal limits
d automatic
as of potent
nitoring syst
d and access
ons with frprotection tr
e access to rl in advancein consideraor issuance pplicant aftee as well askup. In adds on the RWnducted for
e, incorporon of expoworkers pr
e set for uoptimizatiodosimeter i
fective expoposure dose
power utilis. It is presc
equipment,
ial air conta
tem in react
s control.
requent accrainings by
radiation coe in the foration of radiof RWP, a er due conss records ofdition, the WP applicaspecified r
ration of rsure reductrior to radi
unit work, oon of radiatiis given to osure controe a year ar
zation facilicribed in th
,
amination,
tor facilities
cess to radiy Nuclear S
ontrol area arm of a radiiation work
a radiation ssideration of exposure radiation s
ant if necesradiation wo
radiation stion technoliation work outage doseion protectio
each workol. Furthermre under sp
ity is kept bhe procedur
s, and
iation Safety
and to iation type,
safety of the dose,
safety ssary, ork in
safety logies have
e and on. In ker to more, pecial
below e that
any pany expoopera
Do
Withdosimdosimdosimverifproviaccordosim
RC
The poweThe exporadioRadiManaon Ncentewhicoccufunct
-
--
-
person whomore radia
osed above tation of the
osimeter R
h approval ometer readinmeter, persmeter readfication of ider undergrding to themeter readin
Radiation Wenter for R
number of er utilizationNSSC dev
osure dose, oactive isotoation Safetagement Ce
November 2er operates ch is an intupational extions of KIS
- to prodanalysis
- to feedb- to devel
radiatio- to estab
such asUnited (UNSCOECD/N
se annual eation work the operatinfacility is g
Reading Ser
of the NSSCng, monthlyonal notific
ding resultsdosimeter
goes a perfe internationng.
Workers IRadiation W
radiation wn facilities a
veloped the medical ope facilitiey Foundatienter for R
2002 to manthe Korea
ternet-basedxposures anSOE are as
duce data ns of I indiviback matrixlop quantita
on use; and blish an infs InternatioNations S
EAR), and NEA.
xposure doduring wh
ng limits, ungiven or pro
rvice and Pe
C, the dosimy or quarterlcation of ds to the reader eve
formance innal standard
nformationWorkers
workers contand the dive Radiation checkups,
es compreheon (KORSAadiation Wnage exposua Informatiod expert sysnd lifetime follows:
necessary fodual exposuinformation
ative indica
formation nonal Commcientific CInformatio
- 86 -
se reaches thich said wnless the appoper measur
erformanc
meter readinrly distributidosimeter rgovernmen
ery six monspection fds in order
n System
tinuously inersification
Workers Itraining &ensively anAFe). The
Workers, as pure dose reon System stem that e
tracking o
for optimizaure dose; n on radiati
ators for rad
network sysmission on Committee on System
the operatinworker is eproval of thres are taken
e Inspectio
ng service pion, collectireading resunt and calonths. The from the re
to secure o
and Natio
ncreases wiof radiation
Information& education
d the systemKINS estabpart of natiecords in a
on Occupaenables the of individua
ation of rad
ion dose intdiation cont
stem relatedRadiologic
on the Effon Occupa
ng limits shoxpected to
he person ren.
on
providers peion, and reaults, quarteibration andosimeter
egulatory boobjectivity a
onal Safety
th the expan related indn System (Rn of radiatm is currentblished the onal managmore systeational Expanalysis an
al worker
diation pro
o regulatoryrol accordin
d to internacal Protectifects of Atational Expo
ould not perbe additio
esponsible fo
erform the tading of pererly reportinnd performreading se
ody periodand reliabil
y Manage
ansion of nudustries in KRIS) to mation worketly run by KNational S
gement progematic way.posure (KISnd evaluatidose. The
oduction thr
y activities;ng to the ty
ational dataion (ICRP)tomic Radiosure (ISO
rform onally or the
tasks; rsonal ng of
mance ervice
dically lity in
ement
uclear Korea. anage ers at Korea Safety gram, This
SOE), on of main
rough
ype of
abases ), the iation E) of
Le
The equipinstanuclereleaapproor liqlimitdrain
M
In thunplaradioinstasystethe mradiointerlAddispot,any o
M
Befoformfacilisampgaseo Accounplathe odetaithe erepor
egal Requir
Enforcemepment that
alled in theear fuel cyased exceedopriate couquid radioats such as Enage.
Measures in
he design anned/uncooactive systall a processems. The efmain relea
oactivity exlock functiitionally, in , and to creother path a
Measures in
ore starting mulates an ef
ity, this incpling plannious effluent
ording to thanned and uoperator muiled reports environmenrt the event
Preventive
rements
ent Decree can moni
drainage ycle facilitids establisheuntermeasuractivity con
ECL and rad
the Design
stage for ontrolled retem, non-ras radiation ffluent radiase path, if
xceeds legaion to suspthe design
eate a desigand spot oth
the Operat
the operaffluent mancludes detaing, etc. Nuts according
he Notice ouncontrolleust orally rto the regut from the t to the reg
e Measures
of the NSitor the coand air venies. When ed set poines possible
ncentration dioactive wa
n Stage
implemenelease, theradioactive monitor fo
ation monitof any, and al limits shpend releasstage, there
gn that enabher than inte
tion Stage
ation of a nagement plailed proceduclear poweg to the pre-
of the NSSCed conditioneport the e
ulatory bodyfacility congulatory bo
s for Unpla
- 87 -
SA stipulatoncentrationnts of the the conce
nts, an alarm. Regardingat the EAB
aste must no
ntation of re is necessystem, or
or checking or and sam
the envirohould be cose automatie is a need tbles the preended, durin
nuclear polan in due cdures for eer utilizatio-arranged pl
C, when rans due to eqevent to they within 60 ncerned excody within
anned/Unco
tes that dirn of radioanuclear reantration ofm sets off g radioactivB must be ot be releas
legal requssary to c
potential rthe radioac
pling equiponmental rontrolled thically in cato check eveevention of ng the opera
ower utilizaconsideratioeffluent moon facilities lan.
dioactive mquipment me NSSC witdays. When
ceeds ECL, eight hours
ontrolled Re
rect or indactive mateactor, relatef the radioautomatical
ve effluent cequal to ored in other
uirements tlassify eacradioactive ctivity level
pment shoulrelease of hrough the ase an alarery effluent possible ef
ation of a nu
ation faciliton of the chonitoring an
must relea
materials aremalfunction thin four hon radioactivthe operato
s and subm
elease
direct measerials shouled facilities
oactive matlly, thus mcontrol, airbr less than than air ven
to preventch system
system, anls or leakagld be installeffluents wsecuring o
rm is triggt release patffluent releauclear facilit
ty, the opeharacteristicnd managem
ase all liquid
e released uor human
hours and suvity releasedor likewise
mit reports t
suring ld be s and terials aking borne legal
nts or
t any as a
nd to ge by led in whose of an gered. th and ase in ty.
erator s of a ment, d and
under error, ubmit d into must
to the
- 88 -
regulatory body within 60 days. Information on such unplanned/uncontrolled release must also be included in regular and the quarterly reports submitted to the regulatory body.
F.4.3 Restriction on Release from a Nuclear Power Utilization Facility
The NSA prescribes that CP and OL of a nuclear power utilization facility should be given on the condition that the prevention of radioactive hazards to the public health and the environment is ensured. Accordingly, the Enforcement Decree of the NSA stipulates that the concentration of radioactive materials released from a facility should meet the limits defined by the NSSC. In the Regulation of the NSSC, it is stipulated that the volume of radioactive material released should be minimized with the formulation of the radioactive waste control plan, and that environmental impacts should be controlled to maintain ALARA. The Enforcement Decree of the NSA and the NSSC Notice No. 2013-49 (Standards for Radiation Protection, etc.) prescribe the discharge limits of gaseous and liquid radioactive to be released from nuclear power utilization facilities into the environment, along with annual off-site dose constraints per unit or site. Annual dose limits for gaseous effluents per unit of nuclear power utilization facilities at the EAB are as follows:
– air absorbed dose by gamma rays: 0.1 mGy/y – air absorbed dose by beta rays: 0.2 mGy/y – effective dose from external exposure: 0.05 mSv/y – skin equivalent dose from external exposure: 0.15 mSv/y – organ equivalent dose from internal exposure to particulate radioactive substances, etc.: 0.15 mSv/y
Annual dose limits for liquid effluents per unit of nuclear power utilization facilities at the EAB are as follows:
– effective dose: 0.03 mSv/y – organ equivalent dose from internal exposure: 0.1 mSv/y
Annual dose limits at the EAB of a multi-unit site as follows:
– effective dose: 0.25 mSv/y – thyroid equivalent dose: 0.75 mSv/y
In practice, nuclear power utilization facilities operate with operators’ limits which are stricter than the legal limits. In addition, some facilities also apply the derived limit
- 89 -
based on a small fraction of the dose limits in consideration of convenience in a field application. The compliance of the legal limits is verified with periodic inspection or the examination of regular reports submitted to the regulatory body. Tables F.4-2 and F.4-3 represent the annual release of gaseous and liquid effluents recently generated from NPPs and a fuel fabrication facility, and their off-site dose estimations, respectively. The radiation dose and its effect on the individual around nuclear power utilization facilities are assessed monthly using the Off-site Dose Calculation Manual (ODCM). The assessments are based on the radioactivity of the released liquid and gaseous effluents, atmospheric conditions, metabolism, and social data including agricultural and marine products of the local community within an 80 km radius.
- 90 -
Table F.4-2. Annual Radioactivity in Liquid and Gaseous Radioactive Effluents Released from Nuclear Power Sites and Calculated Off-site Dose
Year
Site / Type of Effluent
2009 2010 2011 2012 2013
Kori
Liquid (TBq) 3.4E-05 4.5E-04 1.8E-04 8.2E-04 4.8E-04
Gaseous (TBq) 2.0E+00 1.7E+00 1.7E+00 1.9E+00 2.8E+00
Annual dose (mSv/y) 2.3E-03 1.5E-03 1.7E-03 4.2E-03 4.6E-03
Hanbit
Liquid (TBq) 8.0E-04 3.3E-05 2.3E-04 4.5E-04 3.5E-04
Gaseous (TBq) 3.5E+00 4.3E-02 1.7E-01 2.1E-01 3.2E-02
Annual dose (mSv/y) 4.3E-03 2.7E-03 2.7E-03 1.6E-02 5.8E-03
Hanul
Liquid (TBq) 1.8E-04 1.1E-04 7.4E-05 2.5E-05 4.7E-05
Gaseous (TBq) 7.1E-02 6.5E-01 8.2E-01 7.1E-01 1.8E-01
Annual dose (mSv/y) 2.1E-03 3.3E-03 3.3E-03 1.6E-02 1.2E-02
Wolsong
Liquid (TBq) 1.5E-03 1.8E-03 1.8E-03 1.6E-03 9.6E-04
Gaseous (TBq) 1.4E+01 9.4E+00 4.5E+00 1.3E+01 5.8E+00
Annual dose (mSv/y) 7.1E-03 7.0E-03 4.9E-03 2.2E-02 2.9E-02 * Annual released radioactivity data do not include tritium release * Off-site dose calculation includes tritium effect
Table F.4-3. Annual Radioactivity in Liquid and Gaseous Radioactive Effluents Released from Non-Nuclear Power Site and Calculated Off-site Dose
Year
Site / Type of effluent
2009 2010 2011 2012 2013
Daejeon
Liquid (MBq) 2.4E-05 3.7E-05 2.6E-05 2.7E-05 1.7E-05
Gaseous (MBq) 2.4E+00 3.1E+00 3.8E+00 5.8E+00 5.8E+00
Annual dose (mSv/y) 1.2E-03 1.1E-03 9.79E-04 1.79E-03 1.09E-03
* The gaseous radioactivity in this table is the sum of radioactivity in the gaseous effluents
released from KAERI’s HANARO, PIEF, and radioactive waste treatment facility, and
conversion facility, KEPCO NF’s fuel fabrication facility, and KORAD’s RI waste
management facility, all of which are located at Daedeok site.
F.4.4
Radiby ththe Nthrourelea
The rfurniradiomeasreporunplasuppnecerelearadiascenapath
4 ImplemUnplannFacility
oactive efflhe EnforcemNotices of tugh samplinase.
radioactive ished with oactive matesures in thert should anned/uncoort of the ssary action
ased amountation monitoario. The exand cause o
Monitorin
Action Pla
entation oned/Unco
luents underment Decreethe NSSC ng, sample
waste treata proper raerial, is subje event that
be madontrolled rel
operator ns should bt of radioacoring and existing actioof the uncon
g Plan
an
of Complentrolled R
rgo monitore of the NSA(concerninganalysis, a
tment facilitadiation moject to formt an uncontde under lease occurand the embe taken af
ctive effluenenvironmenon procedurntrolled/unp
- 91 -
ementary Release fr
ring to keepA (concernig the preveand environ
ty of a nuclonitoring sy
mulate and imtrolled relea
the evenrs, and propmergency fter assessmnts accordinnt radiation res must be planned radi
Measuresrom a Nuc
p the releaseing the geneention of hanmental imp
lear power ystem in thmplement pase of radiont reportiper actionsresponse o
ments for ing to radiolo
monitoringcomplemen
ioactive ma
s against clear Pow
e within theeral public’azards to thpact assessm
utilization fhe expectedprograms to oactive matng schem
s should beorganizationndividuals/pogical data fg system, anted throug
aterial releas
wer Utiliza
e limits specs dose limit
he environmment prior
facility, whd release pa
take appropterials occu
me, when e taken witn. Subsequ/public dosefrom the pr
and a reasogh analysis ose.
tion
cified t) and
ment), to its
hich is ath of priate
urs. A any
th the ently, e and rocess onable of the
1.
2.
F.5.
RadiDisalevelof nu PursuEmerManaand SPrepagoveimpletwo Plan It is be inproviPrepamaintypes
F
ARTICLE
Each Cona spent appropriaemergenc
Each Copreparatiolikely to bfuel or rad
1 Regulati
ological emsters and Sl, the Basic uclear accid
uant to the Argency Prepagement whSafety everyaredness Ex
ernments unement Locanational plaunder the a
specified inncluded in ided in tharedness fo
nly for the ps and conte
F.5 Em
E 25. EMER
ntracting Pfuel or
ate on-sitecy plans sh
ontracting on and tesbe affecteddioactive w
ions and R
mergency pSafety whic
Act on Civdents and rad
APPRE, theparedness Phich is prepy five yearsxecution Pl
nder the jurial Radiologans and the
approval of
n the Enforthe detaile
he NSSC Nor Nuclear particulars oents of eme
mergenc
RGENCY
Party shall radioactive and, if nhould be te
Party shsting of emd in the evwaste man
Requireme
reparednessch addressesvil Defensediological d
e NSSC is rPlan in assopared accords. To implemlan is develsdiction of
gical Emerge licensee pthe NSSC.
cement Deced criteria fNotice No. Licensee).
of emergencergency exe
y Prepar
- 92 -
PREPARE
ensure the waste
necessary, ested at an
hall take mergency pvent of a raagement f
ents
s is based s disasters , and the A
disasters.
responsible ociation widing to the Bment the plaloped in dethe emerge
gency Prepprepares an
cree of the for the Rad 2012-31 The Notic
cy planningercises and
redness (
EDNESS
at before amanagem off-site en appropria
the approplans for itsadiologicalacility in th
on the Basand safety
APPRE whic
for developith the BasiBasic Act oan, a Nationetail and imency planninaredness Pl
nd executes
APPRE thadiological E(Notice one was legisg zones, emtime to sub
(Article 2
and duringment facilit
mergency ate frequen
opriate sts territory inl emergenc
he vicinity o
sic Act on manageme
ch consider
ping a Natioic Plan for
on Managemnal Radiologmplement evng zone (EPlan in accoa Radiolog
at the aboveEmergency n Radiologslated in 19
mergency resbmit the ex
5)
g operationty there plans. Suncy.
teps for nsofar as icy at a spof its territo
Managemeent at a natrs the uniqu
onal RadioloNational S
ment of Disagical Emergvery year. LPZ) developordance witgical Emerg
e matters shPlan whic
gical Emerg996 and response faci
xercise plan
n of are uch
the it is ent
ory.
ent of tional
ueness
ogical Safety asters gency Local
ps and th the gency
hould ch are gency evised lities, s and
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results in August 1998, August 2003, June 2004, April 2008 and September 2009, November 2011, and January 2012.
Emergency planning zone
Duties and organization for emergency preparedness
Emergency response facilities and equipment
Detailed criteria for radiological emergency
Initial response of the accident
Activities to respond to radiological emergency
Recovery from radiological emergency
Emergency preparedness training and education
The APPRE defines a electricity generating reactors, a research reactors, nuclear fuel cycle facilities and a storage, processing and disposal facilities of radioactive waste, facilities using nuclear materials as ‘nuclear facilities’, and those who obtain CP and OL for those facilities as a ‘nuclear business operator’. Accordingly, the operator of facilities related to spent fuel and radioactive waste conducts emergency response activities in the event of emergency according to the Radiological Emergency Plan prepared under requirement in the above Acts. The APPRE was revised in May 2014 to classify the emergency planning zone (EPZ) as the Precautionary Action Zone (PAZ) and the Urgent Protective Action Planning Zone (UPZ). This was to incorporate IAEA standards which recommend designating the PAZ up to 3~5 km from NPP and the UPZ within a 20~30 km radius of a damaged NPP. Accordingly, subordinate statute will be revised to allow the nuclear operator to designate the PAZ and UPZ taking into account characteristics of the site such as road and topography within the framework of the APPRE.
F.5.2 National Radiological Emergency Response
The radiological emergency response scheme involves the Central Safety Control Committee chaired by the Prime Minister, NEMC, Off-site Emergency Management Center (OEMC), the Local Emergency Management Center (LEMC), the KINS-Radiological Emergency Technical Advisory Center, Korea Institute of Radiological and Medical Science (KIRAMS)-Radiological Emergency Medical Center, and KHNP-Emergency Operation Center as shown Figure F.5-1. The central government has the responsibility of controlling and coordinating countermeasures against a radiological disaster. In particular, the OEMC, which
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consists of experts dispatched from the central government, local governments and designated administrative organizations, has responsibility of performing coordination of the management of radiological disaster and decision-making on urgent protective actions (sheltering, evacuation and food restriction, etc.). The OEMC consists of six working groups plus a joint consultative committee on emergency response as a decision making advisory body for the head of OEMC. Separately, the joint information center is in operation to provide accurate and unified information about radiological disasters. Established by the local governments concerned, the LEMC implements the OEMC’s decisions concerning public protective actions. When an accident occurs, nuclear enterprisers are responsible for organizing an Emergency Operation Center and taking measures to mitigate the consequences of the accident, restore the affected installations, and protect on-site personnel. If requested, the nuclear enterpriser is also obliged to dispatch emergency response officers, provide technical consultancy and lend radiation monitoring equipment to local governments, necessary for protecting local residents. In addition, the central government establishes and operates the national radiological emergency medical system for coordination and control of radiological medical services. It consists of the National Radiological Emergency Medical Service Center, which is operated by KIRAMS, and the primary and secondary radiological emergency medical hospitals designated by the region. In the event of a radiological accident, the KINS launches a Radiological Emergency Technical Advisory Center provide technical support necessary for coping with a radiological accident. In addition, the KINS runs an Atomic Computerized Technical Advisory System for a Radiological Emergency (AtomCARE) to perform technical support activities effectively so as to protect the residents and the environment when a radiological emergency occurs in the NPP. The diagram of the home grown system is shown as Figure F.5-2.
Figuree F.5-1. Naational Radio
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ological Emmergency Reesponse Sccheme
· SIDS: Sa· IERNet :· REMDA· AINS: A· STES: So· FADAS:· GIS: Geo· ERIX: Em· KMA: K· GTS: Glo· LEMC: L· NEMC: N· EOF: Em· NSSC: N
Fig
afety Inform: Integrated
AS: RadiologAutomatic In
ource Term Following ographic Infmergency R
Korea Meteoobal TelecoLocal EmerNational Em
mergency OpNuclear Safe
ure F.5-2 Afor the
mation DisplEnvironme
gical Emergnformation N
m EvaluationAccident D
formation SResponse Inorological Aommunicatiorgency Manmergency Mperations Faety and Secu
Atomic Come Radiologic
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lay Systemental Radiatgency ManaNotificationn System Dose AssessSystem nformation EAdministration System
nagement CeManagementacility urity Comm
puterized Tcal Emerge
tion Networagement Dan System
sment Syste
Exchange syion
enter t Committe
mission
Technical Adency (AtomC
rk ata Acquisiti
em
ystem
e
dvisory SysCARE)
ion System
stem
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F.5.3 Training and Exercises
Training and exercises for radiological emergency preparedness should be conducted by emergency preparedness personnel such as nuclear enterprisers, emergency response officers of concerned local governments, radiological emergency medical staff of radiological emergency medical institutes, and the KINS. The training should be delivered by training institutes designated by the NSSC after due consideration of the specialties of the tasks involved in emergency response such as firefighting, emergency rescue, radiological accident management, radiological emergency medical service and resident protection. Currently, the KINS and the KHNP have opened radiological emergency training courses. In accordance with the APPRE that came into effect in February 2004, the radiological emergency training is managed at a central government level. To ensure that the radiological emergency training is delivered in a comprehensive and systematical manner, particulars of the emergency trainings including designation and notification of emergency preparedness personnel, development of training plans, delivery methods of trainings are defined in the NSSC Notice No. 2013-43 (Regulations on Education for Radiological Emergency Preparedness). Emergency exercises that must be participated in by on-site or off-site emergency preparedness organizations must participate, are conducted as follows:
The drill with attendance of each emergency organization should be conducted for a two unit plant at least once every quarter in nuclear reactor facilities.
The on-site emergency exercise with attendance of all emergency organizations should be conducted for a two unit plant at least once a year in nuclear reactor facilities.
The initial emergency exercise should be conducted as an on-site emergency exercise or integrated emergency exercise to verify emergency preparedness before nuclear reactor facilities are used (before an initial rated thermal power of 5%). The integrated emergency exercise is conducted when constructing nuclear reactor facilities on the new site.
The integrated exercise should be conducted at each power site every four years with attendance of all emergency organizations in nuclear reactor facilities, the NSSC, and al1 radioactive disaster prevention-related response organizations.
The unified exercise should be conducted every five years with attendance of all domestic radioactive disaster prevention-related response organizations including central administrative organizations.
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Radiological emergency exercises are conducted for a disposal facility with internal or external emergency management organizations
The drill is conducted with internal emergency organization teams participating partially semiannually.
The on-site exercise is conducted with full internal emergency organization at least once every 2 years.
The initial exercise is conducted before a disposal facility is put to use During exercises, the adequacy of radiological emergency plan and their procedure, emergency communication equipment and network, emergency personnel’s expertise in the tasks and emergency response capability, practicability of emergency plan, and cooperative system among related organizations are reviewed. During on-site, joint, and combined exercises, exercise scenarios that address accidents requiring evacuation and sheltering of residents in the EPZ are established and exercised. F.5.4 Environmental Radioactivity Monitoring
The monitoring of environmental radioactivity around nuclear power utilization facilities is to ensure the health and safety of the residents in adjoining areas of the facilities by making sure exposure dose due to radioactive materials discharged from the concerned facility is under the dose limit specified in the NSA. For this, the constructor and operator of nuclear power utilization facilities must take primary responsibility for preserving the environment around the corresponding facilities and evaluate the environmental impact of radiation due to environmental exposure and the operation of the facilities and report to the NSSC. In such case, the NSSC and KINS conduct the verification and monitoring of environmental radioactivity around the facilities to manage and supervise the environmental radioactivity monitoring activities of the constructor and operator of the facilities. Such government-level independent verification and monitoring make for a QA measure to check whether the monitoring activities of the nuclear power utilization facility constructor and operator are implemented appropriately and also to enhance the reliability of environmental monitoring through technical guidance on the radiation measurement and radiation analysis and evaluation. Moreover, periodic inspections on the environment management facilities of the facility constructor and operator and their management are performed to ensure the efficiency of environment management of the nuclear utilization facility constructor and operator. The legal basis for the environmental radioactivity monitoring of the adjoining areas of
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nuclear utilization facilities is Article 104 (Preservation of the Environment) of the NSA. The constructor and operator of the corresponding facilities must establish an environmental monitoring plan in accordance with the Regulation on the NSSC Notice No. 2013-4 (Regulation on Reporting and Public Announcement of Accidents and Incidents for Nuclear Power Utilization Facilities) and report the plan implementation result to the NSSC. As entrusted by the NSSC, the KINS conducts environmental monitoring independently from the constructor and operator of nuclear utilization facilities and checks the appropriateness of the monitoring activities through the comparison and evaluation of the monitoring data of the corresponding facility constructor and operator and also objectively confirms and evaluates the radioactive contamination of the environment around the facilities through regulatory review. Apart from the above, the KINS monitors the environmental radioactivity and space gamma-ray rate level variation in real time according to Article 105 (Monitoring of Nationwide Radioactive Environment) of the NSA and also continuously measures the radioactive contamination of airborne dust, fallout, rainwater, agricultural products, soil, service water and milk to detect abnormal circumstances or signs due to radioactive impact in the early stages and respond appropriately. The KINS has run a national environmental radiation monitoring network since 1997. On the occasion of the Fukushima accident in 2011, the KINS strived to expand the national network and as a result, the network is established with manned monitoring stations and unmanned monitoring posts which totals 128 locations combined across the country. The KINS also trains monitoring personnel from local monitoring stations every year and routinely conducts a cross analysis of domestic and foreign environmental radioactivity to manage the quality of environmental radioactivity monitoring results.
The KINS also developed and is operating the System for Identifying Radiation in Environments Nationwide (SIREN) which integrates the monitoring networks operated to monitor environmental radioactivity and radiation to combine monitoring results by each monitoring network and enhances domestic and foreign radiological emergency early detection capacity. SIREN which combines the monitoring results of various radiation and radioactivity monitoring networks is effectively used as the system capable of continuously monitoring environmental radioactivity in the entire territory before and after an emergency situation and detects abnormal conditions in its early stages.
F.5.5
The organspeciConv The Nmututhe EResetherenotif
Figure
5 Internat
notificationnizations aified in thevention on S
NSSC and ual consent,Exchange oearch Mattee are inter-fication netw
F.5-3. Natio
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work that pr
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ccident andconcerned
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ntal agreemerovides prom
- 100 -
nmental Ra
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d the requd, are madeEarly Notifr Accidents
a radiologicngement betion and C
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tional edures nd the
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early
- 101 -
The KINS signed the MOC (Memorandum of Cooperation) with the National Nuclear Safety Administration (NNSA) of China to maintain cooperation for emergency measures in preparation to prepare for nuclear accidents and set up the emergency cooperation system with the China Institute for Radiation Protection in accordance with the Agreement on Technological Cooperation for Nuclear Safety and Radiological Protection. Korea, China and Japan also signed an MOC on Top Regulators Meeting (TRM) in August 2009 to enhance nuclear safety capacity in Northeast Asia. Based on that, the three nations have been continuously discussing ways for mutual cooperation such as tri-party system for nuclear accident information exchange and joint exercise for radiological emergency preparedness. The 7th meeting has been recently held in Japan in September 2014.
Eaof
The Nrelatesuch decodecoreguldeco The prepareser To dKRR The immereguldeconucleof deKRR
F
ARTICLE
ach Contradecommis
(i) qualifie(ii) the pr
protecapplie
(iii) the pprepar
(iv) record
NSSC speced Act and
as approvmmissioninmmissioninlations onmmissionin
RWMA reqaredness ofrvation plan
date in KorR-1 and 2 is
decommissediate decolatory conmmissioninear facilitieecommissio
R-1 and 2 ar
F.6 De
E 26. DECO
acting Partyssioning of
ed staff anrovisions oction, dischd; provisions redness ards of inform
cifies the licsubordinate
val of the ng status anng activitien decommng as part of
quires the nf the upco
n to MOTIE
rea, no NPPcurrently u
sioning poliommissionin
ntrol upon ng wastes, (s through th
oning technre shown in
ecommis
OMMISSIO
y shall take a nuclear
nd adequatof ARTICLharges and
of ARTre applied;
mation impo
censing proe statute to decommissnd obligatis. Based o
missioning f nuclear sa
nuclear powoming deco.
P has beenunderway an
cy and strang, (2) unr
completio(4) preparathe developm
niques and Annex C.
ssioning
- 102 -
ONING
e the appro facility. Su
te financialLE 24 withd unplanne
TICLE 25 and ortant to de
ocedures andensure safe
sioning planions for saon the NSA
of KRRafety R&D p
wer reator oommissionin
n decommisnd decommi
ategy for KRrestricted r
on of dection for thement of relaexperience
(Article 2
opriate steuch steps s
l resources respect ted and un
with re
ecommiss
d related arety in nuclean, verificat
afety measuA, the KIN
R-1,2 and projects .
operator to ng of NPP
ssioned, howissioning of
RR-1 and 2release of tommissionie upcomingated technos to indust
26)
eps to ensushall ensur
s are availato operatiocontrolled
espect to
ioning are
rticles in thear facility dtion and inures againstNS is impl
performi
reserve funPs and to s
wever decof UCF has b
2 involve ththe site anding, (3) mg decommisologies, and ries. The c
ure the safre that:
able; onal radiat releases
emergen
kept.
e Nuclear Sdecommissionspection ot the closulementing sing R&D
nd every yesubmit a y
ommissioninbeen comple
he followingd building minimizatiossioning of d (5) transfecharacteristi
fety
tion are
ncy
Safety oning
of the ure of safety
for
ear in yearly
ng of eted.
g: (1) from
on of large
erence ics of
- 103 -
The KAERI is in charge of decommissioning of KRR-1, 2. The KAERI also strives to develop decommissioning technology for the decommissioning of nuclear facilities. In addition, the KHNP conducts a preliminary review related R&D for decomissioning of NPP. The UCF, which is located at the KAERI site in Daejeon, was constructed in 1982 for development of fuel fabrication technologies for PHWR. Its decommissioning plan was approved in July 2004 and the decommissioning of the UCF has been completed in 2012 and its site and building are currently used as a research facility. F.6.1 Regulations and Requirements
The licensee of NPP, the nuclear fuel cycle enterpriser or the licensee of a research reactor, when intending to decommission their facility, should submit a decommissioning plan and obtain decommissioning approval from the NSSC. The decommissioning plan should include the following;
methods and schedule of decommissioning,
methods of removing radioactive materials and decontamination,
radioactive waste treatment and disposal methods,
necessary measures against radioactive hazards,
assessment of environmental impact and measures for its minimization,
QAP with regard to decommissioning,
others, as specified by the NSSC
During the IAEA IRRS mission conducted in July 2011, the following recommendation was identified with regard to decommissioning. Based on the recommendation, the NSA is currently under revision for incorporation of definition of “Decommissioning”, submittal time and periodic renewal of decommissioning plans, and decommissioning inspections.
Recommendation: The regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated. These plans should be updated periodically.
F.6.2
Hu
The centrpermhuma
Fi
The accor
Hu
The KrelateDecomemopera
Fi
All fgove F.6.3
Reguthe Jstatuhumaand r1 and The rStand
2 Human a
uman Reso
decommissral research
manently, a an resource
inancial Re
operator ordance with
uman Reso
KAERI hased technoloontaminatio
mbers with tation.
inancial Re
financial reernment.
3 Radiatio
ulations on rJoint Conveus, radiologan resourceradiation prd 2, and acc
regulations dards for R
Nuclear P
KRR-1 an
and Finan
ources
sioning orgh institute local deco
s involved i
esources
of nuclear h the RWMA
ources
s carried ouogies and don & Decothe support
esources
esources for
on Protecti
radiation prntion are ap
gical condites, estimatedrotection mecording to w
applied to Radiation Pro
Power Reac
d 2
cial Resou
anization hof the K
ommissioninin operation
reactor faA.
ut projects fodemonstratioommissionin
of the KAE
r KRR-1 a
ion
rotection anpplied for thions, and ed dose rate oeasures wer
which, radiat
the decommotection, etc
ctor
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urces
has been seKHNP. In ng organizn of NPPs.
acilities has
for decommon studies. ng TechnolERI retiree
and 2 decom
nd safety mahe decommestimated aof workers
re describedation safety
missioning oc., the Regu
et up both addition, wation is pla
s now bee
issioning KTo do thislogy Divisi
es with exte
mmissionin
anagement amissioning oamount of under norm
d in the decocontrol has
of KRR-1 aulation on th
in the headwhen NPPanned to b
en depositin
KRR-1 and 2, the KAERion consist
ensive exper
ng are prov
as describedf the KRR-waste gene
mal and abnoommissioninbeen condu
and 2 are thhe Packagin
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ing expens
2, and deveRI organizeting of 34 rience in re
vided by K
d in Article -1 and 2. Faeration, reqormal condng plan of Kucted .
he Notices ong and Tran
nd the down using
es in
loped ed the
staff eactor
orean
24 of acility quired itions, KRR-
on the nsport
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of Radioactive Materials, etc., the Regulations on the Preparation, etc. of RER of Nuclear Utilization Facilities, and the Regulations on the Environmental Radiation Survey and Impact Analysis in the Vicinity of Nuclear Facilities.
F.6.4 Emergency Response
In the decommissioning of the KRR-1 and 2, the exposure rate for workers was estimated for several scenarios of plausible accidents, and the highest exposure rate was expected in the event of a fall of equipment which was highly radioactive because of activation by neutrons during reactor operation. Even in this event, however, it was assessed that the exposure rate could be minimized because there would be sufficient time for workers to seek shelter. The guideline for coping with such radiation accidents stipulates that all work be suspended and all workers be evacuated from the working area without a delay. Furthermore, radiation safety control personnel must control access to the working area and take the necessary measures for preventing radioactive materials from spreading.
All decommissioning works are performed within the building, and indoor air is released through a filter installed as part of the building ventilation system even in the case of radiation accident, to eliminate the spread of radioactive materials outside the reactor building. In other words, it is concluded that the need for evacuation of residents around the KRR-1 and 2 doesn’t have to be considered when a radiological accident occurs. Most of decommissioning works have been finished, and the assessment of residual radioactivity is currently being performed.
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F.6.5 Record Keeping
Under the Enforcement Regulation of the NSA, records with regard to operation of nuclear power utilization facilities are to be kept until the decommissioning of the facilities so as to utilize the records for decommissioning. Such records include documents related to reactor design and construction, data on radiation protection, events and corrective actions. Information related to decommissioning of the KRR-1, 2 has been collected by the Decontamination & Decommissioning Technology Division at the KAERI. Such information includes data concerning facility status, radiographic conditions, work hours, input of workforce and equipment for each work, exposure dose of each worker, inventory of radioactive waste generated, major radionuclides, types of radioactive waste, volume of liquid waste treated, and other related information. This information is to be preserved for a period as specified in the decommissioning plan. The database system, named DECOMMIS, was developed and has been operated to collect information on management of decommissioning waste, especially for solid waste, including generation, decontamination, packing, and storage. Thanks to the system, it is possible to identify the amount of radioactive waste accurately which then is transmitted to WACID, a DB system developed and operated by the KINS for managing nationwide safety information on radioactive waste management.
SSpentG. S
t Fue
Safetyel Ma
y of anage
emennt
1.
In
G
ARTICLE
Each Conall stageenvironm
so doing, e
(i) ensuspent
(ii) ensuspentconsi
(iii) take spent
(iv) provienvirmethnatiocriter
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(vi) striveon fugene
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E 4. GENE
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ment are ad
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re that critt fuel manare that tht fuel maistent with into accot fuel manade for efonment, bods as appnal legislatria and staninto accobe associa
e to avoid uture generation; o avoid im
Safety
eneral Sa
RAL SAFE
Party shall nt fuel m
dequately p
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ticality andagement ae generatanagemen the type ount interdeagement; ffective prby applyingproved by tion which ndards; unt the biated with s
actions therations gr
posing und
y of Spe
afety Req
- 109 -
ETY REQU
take the amanagemenprotected a
arty shall ta
d removal oare adequation of rad
nt is keptof fuel cycleependenci rotection og at the n the regula has due r
ological, cpent fuel m
hat imposereater than
due burde
ent Fue
quiremen
UIREMENT
ppropriatent, individagainst rad
ake the app
of residualately addredioactive wt to the e policy ades among
of individunational leatory body,regard to in
chemical amanagemee reasonabn those pe
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el Man
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TS
steps to euals, soci
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ensure thaiety and
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with ble,
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acts rent
- 110 -
G.1.1 Nuclear Criticality, Residual Heat Removal and Harmful Material
Criticality, residual heat removal and other safety factors to be considered are stipulated in Article 33 (Fuel Handling and Storage Facilities) of Regulations on Technical Standards for Nuclear Reactor Facilities, etc. for on-site spent fuel storage facilities of the NPPs, and in Article 90 (Fuel Storage Facilities) and Article 91 (Fuel, etc. Handling, Equipment) of the same regulation for the PIEF. Criticality, residual heat removal and other safety factors to be considered for spent nuclear fuel interim storage facility are stipulated in Article 73 (Structure and Installation of Spent Nuclear Fuel Interim Storage Facilities) of Regulations on Technical Standards for Radiation Safety Management, etc. According to the regulations, major safety factors to be considered in spent fuel management include the following: (1) criticality prevention, (2) residual heat removal, (3) radioactive material block, and (4) radiation shield and protection. There is no regulatory provision on chemically or biologically hazardous materials other than radiological risks with regard to a spent fuel management facility in the NSA and subordinate statue. Therefore, the MOE controls the NPPs, in case that NPPs discharge chemically or biologically hazardous materials. G.1.2 Minimization of Radioactive Waste Generation
Current spent fuel management practices, under which all spent fuels have been stored in the spent fuel storage pool or dry storage facility without separate treatment except for allowing post-irradiation examination of spent fuel for limited test and research purpose, are in compliance with the general safety requirement that the generation of radioactive waste associated with spent fuel management should be kept to the minimum practicable in accordance with the fuel cycle policy adopted. G.1.3 Inter Dependence among the Different Steps in Spent Fuel Management
As described in G.1.2, all spent fuels have been stored in the spent fuel pool or dry storage facility without separate treatment except for allowing post-irradiation examination of small amount of spent fuels for limited test and research purpose. The retrievability of all spent fuels to be stored has been maintained. G.1.4 Protective Actions within the Legal Framework
Regulatory provisions to ensure the safety of spent fuel management facilities and to take necessary safety measures are stipulated in the NSA and subordinate statue. Section G.4.1 provides in detail the structure of the NSA, its subordinate statue and
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technical standards in relation to the control of possible radiological impact caused by spent fuel management facilities. G.1.5 Impacts and Burdens on Future Generations
The potential risk of radiation exposure that spent fuel management facilities pose to future generations should be limited to the level equivalent to the radiation protection of current generations. In relation to this, Article 4 (Protection of the Public Health and the Environment) of the NSSC Notice (Generic Criteria for Deep Geological Disposal Facility of High level Radioactive Waste) which was proposed to the National Assembly in 2012, stipulates that “the hazard to the public health caused by a deep geological disposal facility should be sufficiently below an acceptable level and its possible radiological impact on future generations should not be greater than current acceptable level”. In addition, the expenses required for spent fuel management is collected from spent fuel generators, and deposited and managed in the spent fuel management fund to prevent future generations from bearing the cost of managing spent fuel generated by current generations. The MOTIE imposes and collects spent fuel management fee from operation of NPPs, and the collected fee is deposited into the spent fuel management fund to conduct spent fuel management properly in accordance with Article 15 (Contribution to Spent Fuel Management) of the RWMA.
Eaof enall su
G.2.
Currethe sresidaccorin coinspecondNSA On thhistoNPPmade G.2.
Sincefacili
G
ARTICLE
ach Contraany spentters into fo reasonabch a facility
1 On-site
ently on-sitscope of perdent inspectordance withompliance ection or PSducted for aA.
he occasionory, and majs and the PIe.
2 Spent Fu
e the effectuity has been
G.2 Ex
E 5. EXIST
acting Partyt fuel manorce for thaly practicay.
Spent Fue
te spent fueriodic inspeors. Those fh Article 20with licens
SR, appropra PIEF in ac
n of effectuajor event anIEF in oper
uel Interim
uation of thn granted.
xisting Fa
TING FACI
y shall takenagement fat Contrac
able improv
el Storage
el storage faection of thefacilities are
0 of the Enfse requiremriate correctccordance w
uation of thind maintenration in Ko
m Storage
he Joint Con
acilities (
- 112 -
LITIES
e the apprfacility exi
cting Party vements a
e Facilities
acilities (ARe reactors ae also withi
forcement Rments are itive actions with Article
is Joint Connance recordorea were re
e Facility
nvention, no
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ropriate stesting at th and to enre made to
s of NPP an
R-RS or FRs well as suin the scope
Regulation oidentified ishould be t
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nvention, cuds of on-siteeviewed and
o permit for
5)
eps to reviehe time thensure that, o upgrade
nd PIEF
RA-RS) of Nubject to daie of the PSRof the NSAin the proctaken. PerioEnforcemen
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NPPs are wily inspectioR of the NP. If the casecess of perodic inspectent Decree o
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el interim st
fety tion ary, y of
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PPs in es not riodic tion is of the
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G.3.
TechstipuStandgeolooceanconst ArticPIEFhowe
G
ARTICLE
Each Conproceduremanagem
(i) to evof suc
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(iii) to mmem
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In so doiensure thContractirequireme
1 On-site
hnical standulated in dedards for Nogy, earthqn, impact truction of m
cle 103 (GatF. Informatever, is rele
G.3 Si
E 6. SITING
ntracting Pes are est
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valuate all ch a facility
valuate theety and theake informbers of thensult Cont
hey are like their requ to evaluaory.
ng, each Chat such fang Partiesents of AR
Spent Fue
dards for thetail from
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thering Resion on theased to the
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Party shallablished ay:
relevant sy during its
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mation on e public; tracting Paely to be a
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Contractingacilities sh by being
RTICLE 4.
el Storage
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actor Facilitations on lon-induced cilities on th
sidents' Opine safety of general pub
Proposed
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OPOSED F
take the and implem
site-relateds operatingety impactent; the safet
arties in theaffected b
general dately safety
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of a reactoto Article
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nion) of themajor nuc
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Facilities
FACILITIES
appropriatmented for
factors likg lifetime; t of such a
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hall take thve unacceccordance
s of NPP an
r and a nuc10 of the
Major factoreteorologicafeasibility
e.
e NSA is apclear powerh the NSSC
s (Article
S
te steps to a propose
kely to affe a facility o
a facility
of such a faility, and p to the facif the facilit
he appropreptable effe
with the g
nd PIEF
clear fuel cRegulation
rs to be conal condition
of emerg
plicable to Nr facilities and KINS.
e 6)
o ensure ted spent f
ect the saf
n individua
y available
acility, insoprovide theility to enaty upon th
riate stepsects on ot
general saf
cycle facilitns on Technsidered in
n, hydrologygency plan
NPP but noincluding
hat fuel
fety
als,
to
ofar em, able heir
s to her fety
ty are hnical nclude y and
and
ot to a NPP,
- 114 -
G.3.2 Spent Fuel Interim Storage Facility
Since effectuation of the Joint Convention, no site has been selected for spent fuel interim storage and no permit for a spent fuel interim storage facility has been granted. However, the technical standards for location and site of a spent fuel interim storage facility are already stipulated in Article 67 (Location of Interim Storage Facilities of Spent Nuclear Fuels) of Regulations on Technical Standards for Radiation Safety Management, etc., the NSSC Notice No. 2012-51 (Siting Criteria for Interim Storage Facilities of Spent Nuclear Fuel) and No. 2013-31 (Guidelines for Preparation of Site Characteristics Report for Interim Storage Facilities for Spent Nuclear Fuel). G.3.3 Consideration of Neighboring Countries
The notification of an accident and the request for assistance from international organizations and nations concerned, are made in accordance with the procedures specified in the Convention on Early Notification of a Nuclear Accident (CENNA) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (CANARE) of the IAEA. More details are provided in F.5.5 titled International Arrangements.
Ea
G.4.
The impaconcresidconstArticEnvietc.). No lutilizshouventi(EfflNSSCprevealso
G
ARTICLE
ach Contra
(i) the dprovion indisch
(ii) at theprovisfacilit
(iii) the tespentor an
1 Control
NSA and iact caused entration lim
dents near thtraint that icle 6 (Discronment) o.
local residezation faciliuld be kept ailation or duent ControC Notice Nention, detestipulated.
G.4 De
E 7. DESIG
cting Party
design andde for suit
ndividuals, harges or ue design ssions for ty are takeechnologiet fuel man
nalysis.
of Possibl
its subordinby operatiomit during he facilitiesis set lowercharge Conof the NSSC
ent should ities which at lower tha
drainage (Eol Limit) anNo. 2013-4ection or mi
esign and
GN AND C
y shall take
d constructable meas society a
uncontrollestage, concthe decomn into accoes incorpoagement f
le Radiolo
nate statue on of nucleventilation s caused byr than dose
ntrol StandaC Notice N
be exposedexceed do
an radionucCL). Refernd Article
49 (Standarnimization
d Constr
- 115 -
ONSTRUC
e the appro
ction of a sures to li
and the end releasesceptual plammissioninount; orated in thfacility are
ogical Impa
specify theear power uor drainage
y operation e limit for tard) and A
No. 2013-49
d to radiatise limit for
clide concenrence level 16 (Preventrds for Radof uncontro
ruction of
CTION OF
opriate ste
spent fuemit possib
nvironments; ans and, ang of a sp
he design supported
act
e standards utilization e (ECL) and
of the facithe general
Article 16 9 (Standard
ion from or the generantration limof radiatio
tion of Envdiation Protolled release
f Facilitie
FACILITIE
ps to ensu
el manageble radiologt, including
as necessapent fuel
and consd by experi
for restrictfacilities. Td the radioloilities shoul
public in (Prevention
ds for Radia
operation ofal public, a
mit or dose con is specifvironmental tection etc.e of radioac
es (Article
ES
ure that:
ement facgical impag those fr
ary, technimanagem
struction oience, test
tion of radiThe radionuogical impald meet theaccordance
n of Hazaration Prote
f nuclear pand off-siteconstraint dfied in Arti
Hazards) o). Standard
ctive materi
e 7)
ility acts rom
ical ent
of a ting
iation uclide act on dose
e with ds to ction,
power dose
during icle 6 of the ds for al are
MeasventiinstaTechmoniequipaccorFacilrespe
ArticRadi
ArticStandcontr G.4.
A spaccorfaciliradioradio G.4.3
A spprincfacili In reIAEARegu
suring equipilation or dr
alled in accohnical Stanitoring equpment to prdance withlities) of Reectively.
cle 34 (Radation Safety
cle 87 (Stordards for Rrol of radiol
2 Decomm
pent fuel rdance withitate the deoactive waoactive wast
3 Proven T
pent fuel maciple that thity be the on
elation to thA SSR-2/1ulations on
On-site Sp
PIEF
Spent Fue
pment that rainage at oordance withndards for uipment andprovide prh Article 10egulations o
diation Proty Managem
rage and TRadiation Slogical impa
missioning
managemenh applicablecontaminatastes and tes and cont
Technolog
anagement he technologne proven b
his, revised to ArticleTechnical S
pent Fuel S
el Interim S
can monitoror near outlh Article 20Nuclear R
d drainage otection fr0 (Processi
on Technica
tection Faciment, etc. is a
reatment inSafety Manact caused b
g Planning
nt facility le standardstion of strucontaminatetaminated e
gy
facility shogies incorpoby domestic
bill of legie 12 ParagStandards fo
Storage Fac
Storage Fac
- 116 -
r the concenlet of ventil0 (InstrumeReactor Fa
monitoringrom radiatiing and Disal Standards
ility) of Reapplicable t
n Disposal nagement, by a spent fu
g
should bes. The faciuctures anded equipm
equipment d
ould be desorated into tc and foreign
islation wasgraph 4 (Tor Radiation
cility of NPP
cility
ntration of rlation hood ntation andcilities, etc
g equipmenion exposuscharge) ans for Radiati
egulations oto a PIEF.
Facility) ofetc. stipula
fuel interim
e designedility should
d equipmentment, and during decom
igned and cthe design on experienc
s proposed The Use ofn Safety Ma
P
radioactive or drainage
d Control) oc. In additnt, and radire should d Article 3ion Safety M
on Technic
f Regulatioates mattersstorage faci
d for decod be designt, minimizefacilitate tmmissionin
constructedof a spent fe and tests.
to apply Rf Proven Tanagement,
materials de hole shou
of Regulatiotion, ventiliation protebe installe
34 (ConservManagemen
cal Standard
ons on Techs related toility.
ommissioninned in a we the amouthe remova
ng.
d under the fuel manage
RequirementTechnologie, etc. In add
during uld be ons on lation ection ed in vation nt, etc.
ds for
hnical o the
ng in ay to
unt of al of
basic ement
t 9 of es) of dition,
- 117 -
the provision of new revised bill of legislation (Technical Standards for Structure and Equipment of Spent Fuel Interim Storage Facilities) is included that the interim storage facility should be designed and constructed based on proven engineering practice. If new design and construction methods are applied, these methods should be proven.
Ea
G.5.
SafetPreliReguof Edescrof Nin a s
RERdocuArtic
G
ARTICLE
ach Contra
(i) beforsafetythe hlifetim
(ii) beforand envirneces(i).
1 Safety A
ty assessmeiminary Safulation of N
Enforcementribed in RESA. The saseparate saf
R should be uments that cle 44 of En
G.5 As
On-site Sp
PIEF
E 8. ASSES
cting Party
re construcy assessmhazard preme shall bere the opedetailed
onmental ssary to co
Assessmen
ent of an ofety Analys
NSA) and Ft Regulation
ER in accordafety assessmfety analysis
submitted include the
nforcement R
ssessme
pent Fuel S
SSMENT O
y shall take
ction of a sment and aesented b
e carried oueration of a
versions assessm
omplemen
nt and Env
on-site spensis Report inal Safety n of NSA)dance with ment of an s report (SA
in accordane contents Regulation
ent of Saf
Storage Fac
- 118 -
OF SAFET
e the appro
spent fuel mn environm
by the facut; a spent fuof the sent shall
nt the asse
vironment
nt fuel wet(PSAR) (AAnalysis R
). RadiationArticle 4 Pon-site spen
AR) and FSA
nce with Arof SAR shof the NSA
fety of Fa
cility of NPP
TY OF FAC
opriate ste
managememental asscility and
uel managsafety ass be prep
essments r
tal Impact
t storage faArticle 4 PaReport (FSAn environmParagraph 2 nt fuel dry AR of relev
rticle 35 Paould be sub
A.
acilities (A
P
CILITIES
ps to ensu
ent facility, essment acovering
ement facsessment pared wheferred to
Assessm
facility is inaragraph 3
AR) (Articleental impacof Enforcemstorage faci
vant NPP.
aragraph 3 obmitted in
Article 8)
ure that:
a systemaappropriateits operat
cility, updaand of
hen deem in paragra
ment
ncorporatedof Enforce
e 16 Paragrct assessmement Regulility is desc
of the NSAaccordance
)
atic e to ting
ted the
med aph
d into ement aph 3 ent is lation cribed
A, and e with
SafetRERof En G.5.
A spaccorNSAmatteregul
ty assessmeR and a SARnforcement
2 Supplem
pent fuel rdance with
A, and duriners already latory body
Spent Fue
ent of a speR in accordaRegulation
mentation
managemeh Article 27
ng the periodpermitted o
y or reported
el Interim S
ent fuel inteance with A
n of the NSA
of Safety A
ent facility 7 of the NSd of construor designated to the regu
Storage Fac
- 119 -
erim storageArticle 87 PA.
Assessme
should uSA and Artuction or pred should bulatory body
cility
e facility is Paragraph 2
ent
undergo preticle 63 of reoperationabe made wity.
required toand Article
eoperationaEnforcemenal inspectionth a change
o be describe 87 Paragr
al inspectiont Decree on, any chan permit from
bed in aph 3
on in of the nge of m the
Ea
G.6.
The CP aoperaafter
G
ARTICLE
ach Contra
(i) the liuponconddemodesig
(ii) operaexpedefin
(iii) operaspentestab
(iv) enginavailamana
(v) incideholde
(vi) progrestab
(vii) decoprepadurinregul
1 Operatin
constructionand OL of ation of a sissuance of
G.6 O
On-site Sp
E 9. OPER
cting Party
icense to appropriaitional on onstrating gn and safeational limrience anded and revation, mait fuel manblished proneering anable throagement faents signifier of the licrams to coblished andmmissioninared and g the operatory body
ng License
n and operaNPP (Refespent fuel df an OL for
peration
pent Fuel S
RATION OF
y shall take
operate aate assess the comthat the f
ety requiremits and cd the assevised as nentenance, nagement ocedures; nd technicughout thacility; icant to sa
cense to thollect and ad that the rng plans updated, rating lifetiy.
e
ation of a sper to Articledry storageNPP requir
of Facilit
Storage Fac
- 120 -
F FACILIT
e the appro
a spent fusments as
mpletion ofacility, as
ements; conditions essments, ecessary; monitorinfacility are
cal supporhe operat
afety are ree regulatoanalyses rresults are for a speas necessme of that
pent fuel we 10 and 2
e facility, adres a permit
ties (Artic
cility of NPP
IES
opriate ste
el manage specified
of a comms construc
derived fas specifi
ng, inspece conduct
rt in all sating lifetim
eported in ry body;
relevant op acted upo
ent fuel msary, usingt facility, a
wet storage f20 of the Ndditionally t change (A
cle 9)
P
ps to ensu
ement fac in ARTICmissioning ted, is co
rom testsied in ART
ction and ed in acco
afety-relateme of a
a timely m
perating exon, where aanagemeng informatnd are rev
facility of NNSA). The c
introduced Article 20 Pa
ure that:
ility is basCLE 8 and program
onsistent w
s, operatioTICLE 8,
testing ofordance w
ed fields spent f
manner by
xperience appropriatent facility tion obtainviewed by
NPP are parconstruction
d at a powearagraph 1 o
sed d is me
with
onal are
f a with
are fuel
the
are e; are ned the
rt of a n and er site of the
NSAcondfacili
The the NaccorPIEFand Decr
Articstipuinteri
G.6.
For operaCondFacilTech
For aSectiSpenParag
A). Safety rducted to coity of NPP a
PIEF, run bNSA. Safetrdance with
F can be usperformanc
ree of the N
cle 63 of thulate the reqim storage f
2 Operatin
NPP, operated in accditions for Olities, etc. ahnical Speci
a PIEF, opion 3 (Mannt Fuel Magraph 2 and
PIEF
Spent Fue
On-site Sp
PIEF
review andonfirm wheare in comp
by the KAEty review oh Article 6sed only aftce of the fSA.
he NSA andquirements ffacility.
ng Limit a
ating limit cordance wOperation) and the NSifications fo
perating limnipulation oanagement Fd Paragraph
el Interim S
pent Fuel S
d preoperatether the copliance with
ERI is a deson the cons1 Paragraph
fter completfacility in a
d Article 10for safety re
nd Operat
and operaith Article of Regulati
SSC Noticeor Operation
mits and limof Safety-reFacility) of3 of Enforc
Storage Fac
Storage Fac
- 121 -
tional inspeonstruction h safety requ
signated facstruction anh 2 of Enfotion of preoaccordance
01 of the Eneview and p
ting Limit
ating limit48 (Establ
ions on Tece No. 2013n).
miting condelated Facilif Safety Mcement Dec
cility
cility of NPP
ection (Artand operat
uirements.
cility in accnd operationorcement Doperational with the A
nforcement preoperation
Condition
conditionlishment anchnical Stan3-2 (Standa
ditions for oity) and Se
Manual in acree of the N
P
ticle 27 ofion of a sp
cordance win of PIEF
Decree of thinspection
Article 63
Decree of nal inspectio
should be nd Adjustmndards for
ard Format
operation aection 4 (Saaccordance NSA.
f the NSApent fuel st
with Article is conduct
he NSA, anon construof Enforce
the NSA clon of a spen
establishedment of Lim
Nuclear Reand Conte
are prescribafe Operatiwith Artic
A) are orage
35 of ted in nd the uction ement
learly nt fuel
d and miting eactor ent of
bed in on of le 44
For aoperaSAREnfo G.6.3
Techstipuof Re54 Pengindurinthat operacomm ArticStandworkand d
As pcriter(TechQA r
The sto a s
a spent fueation for sa
R that is reqorcement De
3 Technicamonitor
hnical standulated in Artegulations o
Paragraph 4neering andng operationoperating pation, test mencement
cle 72 (Insdards for Nks that havedrawings.
per Article 3ria to be dhnical Caparequirement
same requirspent fuel in
Spent Fue
On-site Sp
PIEF
Spent Fue
el interim safe operatioquired in aecree of the
al Supporring, inspe
dards for tticle 41 (Teon Technic of the samd professionn. The Articprocedures
and mainof operatio
structions, Nuclear Reae an impact
36 Subparadesignated aability) of Ets applicabl
rements for nterim stora
el Interim S
pent Fuel S
el Interim S
storage facion are presaccordance
NSA.
t for Operection and
test, monitoestability, Mal Standard
me regulational supportcle 56 (Oper
necessary ntenance son.
Proceduresctor Facilitit on quality
agraph 1 of as a PIEF, Enforcemene to NPP ar
technical cage facility.
Storage Fac
Storage Fac
Storage Fac
- 122 -
lity, operatscribed in Swith Articl
rating Procd test) and
oring, inspMonitorabilids for Nucleon requires t o review rating Procfor operati
should be
s and Drawies, etc. stipy should be
f the NSA, and specif
nt Regulatire applied to
capability an
cility
cility of NPP
cility
ting limits aSection 8 (Tle 87 Parag
cedure (opd Safety
ection and ity, Inspectaear Reactor
the establisafety-rela
edures) of tion of NPPprepared
wings) of pulates thate described
securing tecfic details aon of the No a PIEF.
nd QA appl
P
and limitingTechnical Sgraph 3 Sub
peration, m
maintenanability, and
Facilities, ishment of ated issues the same regP includingand provid
Regulationt methods fo
in instructi
chnical capare stipulateNSA. In ad
icable to a P
ng conditionSpecificatiobparagraph
maintenan
nce of NPPMaintainabetc., and Aorganizatiothat may
gulation reqg administrded before
ns on Techfor implemetions, proce
pability is oed in Artic
ddition, the
PIEF are ap
ns for on) of 8 of
nce,
P are bility)
Article on for occur quires ation, e the
hnical enting edures
one of cle 34
same
pplied
- 123 -
G.6.4 Reporting of Events Significant to Safety
All nuclear power utilization facilities including a spent fuel management facility should report and disclose incidents and failures in accordance with Article 97 of the NSA and the NSSC Notice No. 2013-50 (Regulation on Reporting and Public Announcement of Accidents and Incidents for Nuclear Power Utilization Facilities).
G.6.5 Incorporation of Operating Experience
As for on-site spent fuel storage facilities of NPP and PIEF, the requirements for systematic incorporation of operating experience of NPP and nuclear fuel cycle facilities include the following: (1) collection, analysis and management of operating experience data, and (2) incorporation of operating experience analysis results into standards and operating procedures and training on equipment and safety. For a spent fuel interim storage facility, the legislative proposal for the NSSC Notice (Technical Standards for Structure and Equipment of Spent Fuel Interim Storage Facilities) proposes the incorporation of operating experience of spent fuel interim facilities as a stipulated provision.
G.6.6 Decommissioning Plan
The operators of nuclear power facilities including a spent fuel management facility, before permanently terminating their business, are required to take necessary measures for protection against radiation hazards including transfer, safe-keeping, discharge, storage, treatment and decontamination and to make a report to the NSSC. For its part, the NSSC has an authority to order necessary measures including collection of radioactive materials and decommissioning of any and all contaminated facilities (refer to Article 94 of the NSA) to be taken. The operators are required to submit a decommissioning plan to the NSSC at the time of intended decommissioning.
If, Pashdis
All sspentNucl6 ParInstaManaThe Spen
G
ARTICLE
pursuant arty has deall be in
sposal of ra
spent fuels gt fuel has nolear Fuel Mragraph 2 o
allation andagement), acurrent stat
nt Nuclear F
G.7 Di
E 10. DISP
to its ownesignated saccordancadioactive
generated inot been impanagement
of the RWMd Support oand public dtus and specFuel Manage
isposal o
POSAL OF
n legislativespent fuel fce with the waste.
n Korea havplemented ywas launch
MA and the Mof Public Ediscussion ocific informement are d
of Spent F
- 124 -
F SPENT F
e and regfor disposae obligatio
ve been storyet. The Pubhed in OctobMOTIE No
Engagementon ways to mmation on thdescribed in
Fuel (Art
FUEL
ulatory fraal, the dispons of Cha
red in a safeblic Engageber 30, 2013otice No. 20t Commissimanage spehe Public E K.4.
icle 10)
mework, aposal of suapter 3 re
e manner anment Comm3 in accorda013-163 (Noion on Spent fuel is acngagement
a Contractuch spent felating to
nd the dispomission on ance with Aotice Conceent Nuclear ctively unde
Commissio
ting fuel the
sal of Spent
Article erning
Fuel erway. on on
RadiioactH. S
ive W
SafetWaste
ty of e Ma
anageemennt
1.
In
H
ARTICLE
Each Conall stagesenvironmhazards.
so doing, e
(i) ensureradioa
(ii) ensureminim
(iii) take iradioa
(iv) providenviromethonationcriteria
(v) take inbe ass
(vi) strive future genera
(vii) aim to
H.1 Ge
E 11. GENE
ntracting Ps of radioa
ment are a
each Cont
e that criticactive waste that theum practicnto accou
active waste for effnment, by
ods as appal legislatia and standnto accounsociated wto avoid a generatioation; avoid imp
eneral Sa
ERAL SAF
Party shall active wastadequately
racting Pa
cality and e manageme generatcable; unt interdee managemective proy applyingproved by ton which dards;
nt the bioloith radioacctions thatons greate
posing und
afety Req
- 127 -
FETY REQ
take the ate manage
y protected
arty shall ta
removal oment are aion of rad
ependenciement; otection og at the nthe regulathas due re
ogical, chemctive wastet impose reer than t
ue burden
quiremen
QUIREMEN
ppropriateement indivd against
ake the app
of residual adequatelydioactive
es among
of individunational letory body, egard to in
mical and e managemeasonably hose perm
s on future
nts (Artic
NTS
steps to eviduals, soradiologica
propriate st
heat geney addressewaste is
the differ
uals, socieevel suitab in the framnternationa
other hazament; predictablmitted for
e generatio
le 11)
ensure thaociety and al and ot
teps to:
erated dured;
kept to
rent steps
ety and ble protectmework ofally endors
ards that m
le impacts the curr
ons.
t at the her
ring
the
s in
the tive f its sed
may
on rent
- 128 -
H.1.1 Standards for Permit of Construction and Operation
The standards for permit of a disposal facility, etc. designed to provide reasonable assurance that the public health and the environment are protected against radiation hazards during the construction, operation, closure, and institutional control periods of a radioactive waste disposal facility are specified in Nuclear Safety related Act and subordinate statute as follows:
Technical capability necessary for construction and operation of a disposal facility, etc. as provided for in the Enforcement Regulation of the NSA should be available;
The location, structure, equipment, and performance of a disposal facility, etc. should conform to the technical standards as prescribed by the Regulation of the NSSC in such a way that they do not present any impediment to the protection of disasters caused by the radioactive materials, etc. to human bodies, materials and the public ;
The construction and operation of a disposal facility, etc. should conform to the standards prescribed by the Presidential Decree in order to prevent any harm to public health and the environment caused by radioactive materials, etc.; and
It is required to secure equipment and manpower prescribed by the Presidential Decree.
To ensure that the foregoing standards are satisfied, the permit applicant should perform a comprehensive and systematic safety analysis. The analysis results should then be reported to the NSSC in the form of SAR and RER. Specific regulatory requirements are provided in the Notices of the NSSC. H.1.2 Safety Analysis
The licensee of a LILW disposal facility should prepare a SAR in accordance with the provisions of the NSA, and submit the report to the NSSC to secure safety in the overall construction and operation processes of a radioactive waste disposal facility. The Enforcement Regulation of the NSA specifies the items to be included in the SAR, which covers safety-related matters, particularly the outline and description of facility, site characteristics, design, construction, operation and maintenance of facility, site closure and institutional control, safety evaluation and accident analysis, radiation protection, technical guidelines, etc.
H.1.
A radurinTo thLow in rafunctdecay
The utilizwasteshou
Radistagesteps
One facilithe eradiosuboradioliquidfacilisufficshoufacili
3 Safety R
adioactive wng operationhis end, in aand Interm
adioactive tions shouldy heat.
amount ozation facilie treatment
uld be consid
oactive wae of radioacs in radioact
of standardity should nenvironmenoactive wasrdinate stat
oactive mated and gaseity; and (3)ciently belo
uld be no prity resulting
Criticality
Minimizat
Interdepe
Preventio
Requirem
waste disposn and to witaccordance
mediate Levwaste shoud be secure
of radioactiities should t systems dered.
ste should bctive waste tive waste m
ds for perminot be impent. The staste disposaltute are: (1erials releaseous effluen) public heow an acceredicted futg from the p
Safety and
tion of Gene
endencies a
n of Enviro
ents to be
sal facility thstand decawith the NS
vel Radioactuld be limd when the
ive waste be minimizalong with
be managedgeneration
managemen
it of a radioediment to tandards for l facility as) limits reg
sed from a fnts at normealth risks eptable levture impact permanent d
d Thermal S
eration of R
among the
onmental H
- 129 -
e considere
should be ay heat andSSC Noticetive Waste)
mited to maere is a poss
generated zed. Accord
h the introd
d considerinn based on int.
oactive wastthe preventi
preventings determinegarding thefacility; (2)
mal operatiocaused by
vel at the pon the env
disposal of r
Safety
Radioactive
Different S
Hazards
ed
designed tod heat genere No. 2013-), the conceaintain critisibility of o
during opdingly, the iduction of
ng the feasinterdepend
te disposal fion of hazag environmed by Nucle concentraradiation do
on that are radioactive
post-closurevironment iradioactive
e Waste
Steps in Ra
o prevent nated by radi-29 (Acceptentration of icality safeverheating
peration of improvemennew treatm
ibility of ddencies amo
facility is thrds to the p
mental hazaear Safety
ation of liquose constraiapplied to
e waste dise stage. Furn the viciniwaste. Futu
dioactive W
nuclear critidiation irraditance Criterf fissile matety, and cothe waste d
f nuclear pent of radioament techno
disposal fromong the diff
he clause thpublic healthards regardi
related Acuid and gaints pertainithe design
sposal shouurthermore, nity of a disure use of na
Waste
cality iation. ria for terials ooling due to
power active ology
m the ferent
at the h and ing a
ct and seous ing to
n of a uld be
there sposal atural
resou
In acInterpyroprisksto prchemperfo Withshoucorroproceexcludispo
In acinstamoniarea dispoexistisola Withgaseooperalocatto mfaciliFurthmatemana
urces should
ccordance wrmediate Lephoric mate by them ar
revent from mical reactiormance of
h regard to uld be mitigosion; wastessed so as uded or theiosal facility
ccordance walled, and ditor the radiradiation m
osal facilityt in a disposate the releas
h regard to ous or liquations, andtions other t
monitor operity, approprhermore, therials shoulagement fac
Biological
RadioactivUncontro
d not be imp
with the NSevel Radioaerials to bere eliminategenerating
ion which a disposal f
waste to bgated and thte that inclto exclude
ir contents sy.
with the Nodistinction iation levels
monitoring sy. When rasal facility,se automati
a radioactiuid radioac
d such effluthan air venrating condriate samplhe possibilild be fundcilities from
, Chemical
ve Effluentlled Releas
peded by ei
SSC Noticective Waste
e disposed oed. In additigas, vapor,may under
facility or th
be disposed he materialludes toxic,such hazardshould be re
otice of theshould be s of radioacsystems to mdiation levethe system
cally.
ve waste trctive efflueuents shou
nts or drainaditions of aning devicesity of cont
damentally m those desig
and Other
t Control anses
- 130 -
ither radioac
e No. 2013-e), waste coof should bion, the wa, or liquid armine the
he safety of
of, includils should b, perishableds. Chelatinestricted ac
e NSSC, ramade betw
ctive materimonitor theels exceed
ms should h
reatment faent appropr
uld not be ages installend radioacts and monitamination minimized
gned to han
r Hazards
nd Conside
ctive or non
-29 (Accepontaining exbe adequateaste should bas a result of
integrity of workers.
ing corrosivbe packed ine, or contang agents coccording to t
adiation moween radiatials in liquide radiation lthe set po
ave functio
cility, it shriately durreleased in
ed pursuanttivity releasitoring equidue to thby separa
ndle non- rad
rations for
nradioactive
tance Critexplosive, flaely treated be controllef radiolysis,of the was
ve materialsn such a wagious mateontained in the acceptan
nitoring syion monitod and gaseolevels of spints or whens to activa
ould be poing normalnto the ent to CP and sed from a ipment shoue backflowation of radioactive m
Preventing
e contamina
eria for Lowammable, aso that poted in such a, or biologic
ste package
s, corrosionway to witherials shouwaste shou
ance criteria
ystems shouoring systemous effluentpecific areasen abnormaate an alarm
ossible to col and abno
nvironment OL. In addwaste treatuld be inst
w of radioaadioactive w
materials.
g
ants.
w and and/or ential a way cal or e, the
n rate hstand ld be
uld be a for a
uld be ms to ts and s in a alities m and
ontrol ormal from
dition, tment talled. active waste
In acInternonfljudgeintegpress
In acLonga posat anconfi
ccordance wrmediate Leflammable ced by visua
grity under sure increas
ccordance wg-term Safest-closure pn acceptablfirming that
Stability o
Restrictio
with the NSevel Radioacontainer, aal inspectiocircumstan
ses due to ge
with the NSty on Low eriod, the ple level notan undue b
of Waste Pa
n of Effects
SSC Noticective Wasteand the pa
on. Furthermces expecteeneration of
SC Notice Nand Interme
performancet only for urden impo
ackage
s on Future
- 131 -
e No. 2013-e), waste to
acking contmore, the ped in disposf gas within
No. 2012-5ediate Leve
e objective ocurrent but
osed on futu
e Generatio
-29 (Accepo be disposeainer shoulackage shosal conditio
n the packag
55 (Radioloel Radioactiof keeping tt also for
ure generatio
ons
tance Criteed of shouldld be free
ould be ableons, even wge.
gical Protecive Waste Dthe risk of rfuture geneons is limite
eria for Lowd be packedfrom defec
e to maintawhen the int
ction CriterDisposal), dradioactive werations, thed.
w and d in a cts as ain its ternal
ria for during waste ereby
Earev
NuclfacililicenmainthroucondNuclor rep On tmajofacilirevie In adenvirlow lperfosafet
H
ARTICLE
ach Contraview:
(i) the sthe tiand impro
(ii) the rintervmind dose the s
lear power ity are cons
nse/permit pntenance of ugh periodiditions at a lear Safety rporting of m
the occasioor accident ities and mewed and no
ddition, pasronment frolevel radioaormed in a ty standards
H.2 Ex
E 12. EXIS
acting Part
safety of aime the Coto ensur
ovements aresults of vention is that the r should beocial costs
utilization structed andpursuant to these facili
ic and non-specific fac
related Act minor chang
n of the Joand maint
major radioao significant
st practicesom existingactive wastemanner app
s.
xisting Fa
TING FAC
ty shall in
ny radioaconvention re that, iare made tpast prac
needed foreduction ie sufficient s, of the int
facilities id operated athe Nucleaties accordi-periodic incility requirand subord
ge, should b
oint Convetenance recactive wastet finding wa
s such as cg facilities ae were reviepropriate to
acilities a
- 132 -
CILITIES A
due cours
ctive wasteenters intof necessato upgradectices in oor reasons in detrimen to justify ttervention.
in Korea inafter adequaar Safety reing to the conspections. re revision,
dinate statutebe adhered t
ention, currecords of exe-generatingas identified
control of rand recordsewed. It wao domestic
and Past
AND PAST
se take th
e managemo force forary, all re the safetyorder to dof radiatio
nt resultingthe harm a
ncluding a ate safety evlated Act aonditions liIn addition
, permit proe, such as pto.
ent conditioxisting radiog facilities id.
radioactive s on the cleas verified tlaws in com
Practice
T PRACTIC
he appropr
ment facilir that Contreasonablyy of such adetermine on protectiog from theand the co
radioactivevaluations and subordincensed/permn, when peocedures inermit for si
ons, operatoactive wasin operation
effluents rearance appthat past prampliance w
es (Article
CES
riate steps
ity existingtracting Pay practicaa facility; whether aon bearing
e reductionosts, includ
e waste disand issuancenate statutemitted is veermitted/licen pursuant tignificant ch
tion historyste managen in Korea
released intplication ofractices hadwith internat
e 12)
s to
g at arty able
any g in n in ding
sposal e of a
e. The erified ensed to the hange
y, and ement
were
to the f very d been tional
The Nof Locase earthshourevisfaciliexpeassesto vinforrelevof, aimpa
The compthe Nestabinspe
NSSC Notiow and Inte
of an evehquake, floould be re-evsed based onity should brience and ssment. Theerify the srmation andvant performand recordsacts on the p
safety anprehensivelyNSSC, and blished procections.
Safety As
Safety Im
ice No. 201ermediate Lent which aoding and otvaluated, ann the latest dbe constantl
data obtaine NSSC Nosafety of ad data on themance evalus of accidepublic and th
nd performy evaluatedproper act
cedures if th
ssessment
mprovement
3-35 (TechnLevel Radioaaffects the ther naturalnd related data. In addly re-evaluaned from o
otice also stia radioactive facility, siuation concents, safety he surround
mance of ad through rtions shouldhere is any
t
- 133 -
hnical Requiactive Wastintegrity o
l disasters, olicensing d
dition, condated, and suoperating a ipulates thave waste dite and surroerns, total inincluding
ding environ
a radioactiregulatory id be taken finding in s
irements forte Disposal of a LILWor an accidedocuments itions relate
upplementeddisposal fa
at the followdisposal facounding arenventory ofthe radiolo
nment.
ive waste inspectionswithin a s
safety or pe
r the OperaFacilities)
W disposal ent, the safeand proced
ed to the safd, if necessaacility and wings shoulcility prior eas for the pf radioactiveogical and
managemeperiodicall
specified timrformance a
ation and Costipulates thfacility suc
ety of the fadures shoufety of a disary, based oresults of s
ld be reevalto closure
period that oe waste dispnon-radiolo
ent facilityly conducteme accordias a result o
ontrol hat in ch as acility ld be
sposal on the safety luated e: (1) of the posed ogical
y are ed by ng to of the
1.
2.
H.3.
The The ReguNoticLeve(GuidLevebe in
H
ARTICLE
Each Coprocedurewaste ma
(i) to evof sudispo
(ii) to evsocieof the
(iii) to mmem
(iv) to coas thuponthemterrito
In so doiensure thContractirequireme
1 Regulat
site selectiostandards f
ulations on ce No. 201el Radioactdelines for
el Radioactincluded in si
H.3 Si
E 13. SITIN
ntracting Pes are estaanagement
valuate all uch a facilosal facilityvaluate theety and thee site condake informbers of thensult Cont
hey are like their requ to evaluaory.
ng, each Chat such fang Partiesents of AR
ory Requi
on for a LILfor permit fTechnical S
12-50 (Techtive Wastethe Prepara
ive Waste Dite characte
iting of P
NG OF PRO
Party shallablished at facility:
relevant sity during
y after closue likely safee environmditions of dimation on e public; tracting Paely to be a
uest, with gate the like
Contractingacilities sh by being
RTICLE 11.
rements a
LW disposalfor site seleStandards fhnical Stande Disposal ation of SiteDisposal Faeristics repor
Proposed
- 134 -
OPOSED
l take the and implem
site-related its operature; ety impact
ment, takinisposal fac the safet
arties in theaffected b
general dately safety
g Party shhall not hav
sited in ac.
and Perm
l facility is ection of a for Radiatiodards for th
Facilities)e Character
acilities) stiprt.
Facilities
FACILITIE
appropriatmented for
factors likting lifetim
t of such ag into acc
cilities aftery of such
e vicinity oy that facita relating impact of
hall take thve unacceccordance
it Procedu
described idisposal fa
on Safety Mhe Location). The NSristic Reporpulates that
s (Article
ES
te steps toa propose
kely to affee as well
a facility oount possir closure; a facility
of such a faility, and p to the facif the facilit
he appropreptable effe
with the g
ure
n section Eacility, etc.
Managementn of Low aSSC Noticert for Low a
the followi
e 13)
o ensure ted radioact
ect the saf as that o
n individuaible evolut
y available
acility, insoprovide theility to enaty upon th
riate stepsects on ot
general saf
E.2.3 of the Nare stipulat
t, etc. and Nand Intermee No. 20and Intermeing items sh
hat tive
fety of a
als, tion
to
ofar em, able heir
s to her fety
NSA. ted in NSSC ediate 13-30 ediate hould
SafetenvirassesDevePlans
Ra
Undeevaluradiofunda The predienvirconstaccid
Ge
Enviand aoperaanalyEnvienvirsubmMOE
data onfacilitie
data of induced
site mooperatio
ty assessmeronmental issment. Sucelopment Ps, as well as
adiological
er the NSA,uate the imoactive wasamental req
RER contaicted radiolronmental rtruction andents and in
eneral Env
ronmental assessing nation of a dysis in accronment, Tronment, liv
mitted shoulE.
Factors of
n the currenes, major env
site safety d external ev
onitoring aon, and post
ents for theimpact assech safety an
Project Plans for CP and
Environm
, a radiologimpact of raste disposalquisites to o
ains facilityogical imparadiation m
nd operationncidents dur
vironmenta
impact assenon-radiologdisposal faccordance wraffic, Disaving envirold be appro
f Safety An
nt status of vironmenta
analysis suvents, and d
nd surveillt-closure.
e site of a dessment, sanalyses shouns and apprd OL of a L
mental Impa
ical environadiation or l facility obtain CP an
y informatioact on the s
monitoring pn, radiologring a facilit
l Impact A
essment shogical impactcility, separwith the Aasters, etc. Tonment and ved by Min
nalysis
- 135 -
the site sual conditions
uch as the edesign input
lance progr
disposal facafety analysuld be perfroval of Ra
LILW Dispo
act Assessm
nmental impradioactive
on the surrnd OL of rad
on, environurrounding
program to gical impacty operation
Assessment
ould be cont on the en
rately from Act on AsThe assessm
social and nister of M
uch as geogs, natural re
effect of nat data,
rams in th
cility are disis and genformed for aadioactive Wosal Facility
ment
pact assessme materials rounding endioactive w
nmental stats thereof dube implemt on the e
n, and collec
(Non-radio
nducted fornvironment
the radiolossessment o
ment is condeconomic
OTIE in co
graphy, popesources, an
atural disast
he phase o
ivided into neral enviroapproval ofWaste Many.
ment shouldcaused by
nvironment,waste disposa
tus of neighue to operat
mented durinnvironmentcted opinion
ological)
the purposcaused by cgical enviroof Impactsucted in theenvironmen
onsultation w
pulation, mind ecosystem
ters and hu
of pre-oper
the radioloonmental imf Electric S
nagement Pr
d be conducty operation , as one oal facility.
hboring regtion of a facng the perit resulting ns of the pu
se of identiconstructiononmental ims of Worke areas of nant and the rwith Minis
ilitary m,
uman-
ation,
ogical mpact ource roject
ted to of a
of the
gions, cility, od of from
ublic
ifying n and mpact ks on atural report ter of
The the e The the ddesigPlan.the Mheari The Facilas thsame In aresiddispo
The neighagreeprepa
H.3.
A pecondsurveand tan apNSSCthrouapprofacili
Korean goventire stage o
Act on Spedetails of thgnation of t. The NSA
MOE also spings before
Special Ality prescribhe results oe time holdi
addition, thdents and Nosal facility
Korean pehboring couements witharedness. Th
2 Site Sele
erson who duct a safeteys and detthe Site Surpplication foC may granugh an applioval procedity.
Disclosure
Consultat
vernment coof the site s
ecial Cases he project the final sitand the Envpecify that preparation
Act on Supbes that MOf site surveing explanat
he Civil ENGO represey as part of e
eninsula is untries. Theh foreign che contents
ection for
intends to ty analysisailed surveyrvey Report
for a prior apnt a prior aication for Cdure depend
e of Inform
tion with Ne
onsistently mselection pro
Concerningto local reste and apprvironment Tthe opinion
n of the envi
pporting thOTIE make eys and the tory meetin
Environmententatives areefforts to en
surrounde Korean gocountries o of the agre
the Propo
construct a under theys on candit should be pproval for approval toCP and OLding on the
mation
eighboring
- 136 -
maintains aocess of a L
g Electric Ssidents for roval of theTransportatins of the pubironmental
he Local Cpublic theLILW disp
ngs or forum
t Monitorine operated
nsure the tra
d by sea overnment hon site seleeement are d
osed Facil
and operatee provisionidate sites. Bprepared aa construct
o the applicof a dispos
e decision o
Countries
a principle fLILW dispo
ource Devea certain p
e Electric Sion Disasterblic should reports.
County arsite selectioposal facili
ms for the lo
ng Organizduring an o
ansparency o
on three shas not concction, but described in
ity
e of a LILns of the NBased on th
and submittetion site. Afcant. Site sasal facility wof the oper
for securingsal facility.
elopment prperiod befoource Dever Impact Asbe collecte
ound the on plan andty construccal resident
zation consoperation peof informati
sides and icluded specon radiolog
n section F.5
W disposalNSA includhe analysis ed to the NSfter review bafety can alwithout underator of the
g transparen
rescribes to ore the notielopment Prssessment A
ed through p
LILW Disd process asction plan, ats.
sisting of eriod of a Lion disclosu
is isolated cific internatgical emerg5.
l facility shding prelimresults, the SSC when by the KINlso be evalergoing the
e LILW dis
ncy in
open ice of roject
Act of public
sposal s well at the
local LILW ure.
from tional gency
hould minary
RER filing S, the luated prior
sposal
- 137 -
As for the LILW disposal facility currently under construction, On August 2005, Gunsan-Shi, Gyeongju-Shi, Pohang-Shi, and Yeongdeok-Gun applied for the hosting of a LILW disposal facility through public subscription, and all of these sites were evaluated for hosting a disposal facility. Referendums were held by these four local governments. As a result, Gyeongju was finally selected as the site for a LILW disposal facility on November 2005 among counties with the highest number of favorable responses from residents (89.5%).
Ea
H.4.
DesigNoticInterNoticInter A LIfunctconstadditsuch be us
H
ARTICLE
ach Contra
(i) the dfacilitimpacfrom
(ii) at theprovismanaaccou
(iii) at thefacilit
(iv) the teradiotestin
1 Regulat
gn factors tce No. 20rmediate Lece No. 2013rmediate Le
ILW dispostional integtruction of tion, equipmthat they c
sed safely.
H.4 De
E 14. DESI
cting Party
design andty provide cts on indidischargese design ssions for agement funt; e design stty are prepechnologieactive was
ng or analy
ory Requi
to be consid013-28 (Staevel Radioa3-36 (Guidevel Radioac
sal facility sgrity during
a disposal ment and coan be regul
esign and
GN AND C
y shall take
d construc for suitabividuals, sos or unconstage, conc the decacility oth
tage, technpared; es incorposte managysis.
rements
dered for a Landards fo
active Wastelines for Prctive Waste
should be dnormal andfacility sho
omponents arly tested a
d Constr
- 138 -
CONSTRU
e the appro
ction of a ble measuociety and ntrolled releceptual placommissioer than a
nical provis
orated in thement fac
LILW dispoor the Strute Near-Surreparation o
e Disposal F
designed sucd abnormal
ould be baseinstalled at and inspect
ruction of
UCTION O
opriate ste
radioactivures to lim the enviroeases; ans and, aoning of a disposal
sions for th
he design ility are su
osal facilityucture and rface Dispoof Safety A
Facilities).
ch that it ml operationsed on provea disposal
ted to confir
f Facilitie
F FACILIT
ps to ensu
ve waste mit possibleonment, inc
as necessaa radioafacility ar
he closure
and conspported by
y are stipulaEquipmen
sal FacilityAnalysis Rep
maintains thes. Thereforeen engineerfacility sho
rm that they
es (Article
TIES
ure that:
manageme radiologicluding tho
ary, techniactive ware taken i
of a dispo
struction oy experien
ated in the Nnt of Lowy) and the Nport for Low
eir structurae, the designring practicould be desy can contin
e 14)
ent ical ose
ical aste nto
osal
of a ce,
NSSC w and NSSC w and
al and n and es. In igned
nue to
H.4.
The stipuof sit The from
In acminimopera
Ra
–
–
St
–
2 Criteria
radiation exulated by thete selection,
design goalm radiation e
In-opera– effecti– effecti
Post-clo– dose b– hazardacciden
– radiolo
ccordance wmize the raation or in c
adiological
– The desigclosure anpost-closu
– A disposaobjectivesProtectionCriteria foDisposal)
tability of S
– A disposasupplemen
Design Go
Design Cr
of Design
xposure of e NSSC No, design, op
ls for a dispeffects both
ation designive dose of eive dose by
osure designby normal nad by unexpnts: 10-6/y ogical effec
with the NSadiological case of acci
Safety
gn and opernd stabilizature period shal facility ss presented n, etc.) andor Long-term.
Site and Str
al facility snt and impr
oals
riteria
n and Cons
local resideotices. Theseperation, clo
posal facilitduring oper
n goals external expliquid relea
n goals atural pheno
pected phen
t by inadver
SSC Noticeeffects on dents
ation of a dtion plans; thould be meshould be d
in the NSSd the NSSCm Safety on
ructure
should be drove site cha
- 139 -
struction
ents and rade requireme
osure, and p
ty to protecration and p
posure by gase: 0.03 mS
omena: 0.1 nomena tha
rtent intrud
es, major deradiation w
disposal facthus, the peet.
designed in SC Notice C Notice Nn Low and
designed coaracteristics
diation worents should ost-closure
ct local residpost-closure
gas release: 0Sv/y
mSv/y at is come
ers: 1.0 mS
esign criterworkers and
cility shoulderformance
such a waNo. 2013-4
No. 2013-5Intermediat
onsidering ss.
rkers shouldbe considerinstitutiona
dents and rae period are
0.05 mSv/y
from natur
v/y
ria should bd the public
d be complobjectives
ay to meet t49 (Standard5 (Radiolote Level Ra
site charact
d meet the lred at each
al control.
adiation woas follows:
y
ral or man
be establishc during no
lied with thestablished
the performrds for Radiogical Proteadioactive W
teristics so
limits stage
orkers :
nmade
hed to ormal
he site for a
mance iation ection Waste
as to
–
–
The Nfacilienginbe pdispoand Disp
--
-
-
A LIamoureachlongefor cisola
In tedispo
–
– A disposaas geologdisasters.
– A disposaminimal mcontrol pe
Notices of tity in detaineering praproven withosal facilityEquipmentosal Faciliti- The constr- A disposa
natural ba- Regarding
validity shobtained d
- When thecarried oudisposal fa
ILW disposunt considehed the alloer possible
closure and ate radioacti
erms of decosal facility– Regarding
Considera
Considera
Considera
al facility shy, earthqua
al facility shmaintenanceriod.
the NSSC pil. The conctices. Wheh valid ev
y are specifit of Low ies) as folloruction of aal facility srriers is min
g the charachould be cduring conste constructiut in such a acility.
sal facility ered in its dowable limidue to unexstabilizationve waste on
commissiony should takeg liquid ra
ations for C
ations for C
ations for D
hould be deakes, meteor
hould be dee and repa
provides thenstruction oen new conidence. Deed in NSSCand Interm
ows: a disposal fahould be cnimized. cteristics of confirmed ttruction. ion and opway to hav
should be ddesign or thts or when
xpected accin of a dispon a long term
ning, a radie into accoudioactive w
Construction
Closure
Decommissi
- 140 -
esigned consrology, and
esigned to mair activities
e constructif a disposa
nstruction metailed consC Notice Nomediate Lev
acility shoulconstructed
natural barthrough com
peration stave no adver
designed tohe total radi
maintaininidents. Accoosal facilitym basis.
ioactive waunt as followwaste pipin
n
ioning
sidering sited hydrology
maintain ths during th
ion-related fal facility s
methods are struction-reo. 2013-28 vel Radioa
ld adhere tosuch that d
rriers assummparisons w
ages overlarse effect on
o enable itsioactivity ofg their normordingly, a
y as well as
aste managws: ng, their le
e characteriy as well as
heir structurhe post-clos
factors for ashould be bapplied, thelated facto(Standards
active Wast
o QA requiredamage to
med at the dewith on-sit
ap, construcn the operat
closure whf the waste mal functionSAR shouldattendant d
gement faci
ength shoul
istic factorss other man
ral integritysure institut
a LILW disbased on preir safety sh
ors for a Lfor the Stru
ste Near-Su
ements. the functio
esign stage,te measurem
ction shoultional safety
hen the dis disposed o
ons is deemed describe a
design featu
ility exclud
ld be mini
s such nmade
y with tional
sposal roven hould LILW ucture urface
ons of
, their ments
ld be y of a
sposal of has ed no a plan res to
ding a
imum
- 141 -
possible, and care should be taken to prevent contamination of surrounding areas due to leakage of liquid radioactive waste from the connection areas of the piping;
– Care should be taken to prevent accumulation of radioactive materials in relatively inaccessible areas such as curves and turns in pipes and ducts;
– A mechanism by which piping systems containing actually or potentially liquid radioactive materials can be easily flushed and cleaned should be prepared;
– Adequate space should be secured to accommodate remote handling components and safety monitoring components as necessary for future decontamination and decommissioning;
– For large tanks and components, a hoist should be installed for easy decommissioning; and
– Regarding piping systems to transport radioactive liquid waste or potentially contaminated liquid waste, it should be possible to use gravity for drainage.
H.4.3. Implementation of Regulatory Requirements
The KHNP conducted site surveys and environment surveys on the finally selected site and submitted to the Ministry of Science and Technology (at present, NSSC) an application for CP and OL of a LILW disposal facility based on the survey results in January 2007. At the request of the Ministry of Science and Technology (at present, NSSC), the KINS conducted a safety review of the application attached with documents including RER, SAR, and QAP. As a result of the review, it was concluded that the application was in compliance with the standards for permit specified in the NSA, as technical standards for location, structure, component and performance were complied with as well as the radiological impact resulting from operation and closure of a disposal facility was in conformity with the standards for protection of public health and the environment as specified by Enforcement Decree of the NSA. After deliberation and resolution, the NSSC granted the permit to the KHNP on July 31, 2008. The responsibilities of construction and operation of the disposal facility were transferred to the Korea Radioactive Waste Management Corporation (KRMC, renamed as the KORAD) when it was established in January 2009 in accordance with the RWMA. The construction of the disposal facility started in August 2008 and as of late June, 2014, most of the construction works including excavation for construction tunnel, operation tunnel, access shaft, unloading tunnel and disposal storage (silo) and concrete lining have been completed and the final inspection for operation of the disposal facility is currently underway. The LILW disposal facility is divided into surface and underground facilities (see
- 142 -
Figure H.4-1). Surface facilities consist of a receipt and storage building, radioactive waste processing buildings, service buildings and other supporting buildings. Here, radioactive waste is received from waste generators such as NPPs and verified to be consistent with the waste acceptance criteria. On-site treatment or conditioning is done, if necessary.
Underground facilities include construction tunnel, operation tunnel, access shaft, unloading tunnel, and disposal silos. At first, six silos will be constructed approximately 80-130 meters below sea level to dispose of approximately 100,000 waste packages (see Figure H.4-2 Cross section view of the underground facilities). All disposal silos are reinforced with shotcrete and concrete lining. Most waste packages are packed using disposal concrete containers and subsequently disposed of in the disposal silos.
Figure
Fi
e H.4-1. Bird
igure H.4-2
d’s Eye View
. Cross Sec
- 143 -
w of the Wo
ction View o
olsong LILW
of Undergro
W Disposal C
ound Faciliti
Center
es
- 144 -
The operator of a LILW disposal facility should undergo preoperational inspection in accordance with the NSA. The purpose of the preoperational inspection is to check prior to operation whether the construction of a disposal facility satisfies the related design and safety requirements. The disposal facility, etc. should be deemed to have passed the inspection when the construction work has been progressed according to the content of a permit given under the NSA and when the structure, equipment and performance of the disposal facility, etc. is in conformity with the technical standard set by the NSA. The preoperational inspection by the KINS started in September 2008. The preoperational inspection of the LILW disposal facility is conducted for the purpose of confirming the appropriateness of construction and performance and operational readiness, which is composed of four steps: (1) inspection on structure, (2) inspection on system installation, (3) inspection on system performance and (4) inspection before operation. As of late June, 2014, step (1), (2), and (3) are in the final stage and the disposal facility is expected to operate after the step (4) is completed and the success of preoperational inspection is notified by the NSSC.
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- 145 -
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- 146 -
pes, and amnd closure ac
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during the psks for indivl phenomenisk due to estricted to
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- 147 -
dionuclide lof the prewnstream o
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- 148 -
H.5.3 Implementation of Safety Assessment and Radiological Environmental Assessment of the LILW Disposal Facility
In January 2007, the KHNP filed an application for CP and OL of a LILW disposal facility, attached with SAR, RER, QAP, etc., to the Minister of MEST (Currently the NSSC) in accordance with the Nuclear Safety related Act and subordinate statute. The applicant developed scenarios and conducted a safety assessment based on the safety assessment methodology recommended by the IAEA’s Co-ordinated Research Project (CRP) on the Improvement of Safety Assessment Methodologies for Near Surface Disposal Facilities (ISAM). The safety review of the LILW disposal facility was conducted by the KINS to confirm the suitability of the facility site and the environment, appropriateness of the disposal system design and construction methods, and appropriateness of the safety assessment after closure of the facility so as to determine technically whether the legal requirements have been met. Based on the review results, it was recommended that the applicant, after issuance of CP and OL, implement follow-up actions to address issues that require safety demonstration or further confirmation to reduce uncertainty to be identified during the period of construction and operation, and the KINS conduct a review of the results of implementation. The implementation and review of follow-up actions is to reduce uncertainty over safety in the long-term and to secure the objectiveness and transparency of safety of the disposal facility based on the safety review reflecting site characteristics obtained in the process of construction and operation of the disposal facility. By doing so, it is ultimately possible to develop the Safety Case for the construction stage of the disposal facility which is in line with international requirements including the IAEA SSR-5 (Disposal of Radioactive Waste, 2011), that stipulate establishment of Safety Case for each development stage of a disposal facility.
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- 149 -
OF FACILIT
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- 150 -
hnical Requiioactive Waafety durin
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ary for opeds to humane technical ive, handlea disposal fdards descri
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- 151 -
records and keeping. H.6.3 Limiting Conditions of Operation of a Disposal Facility
The limiting conditions of operation of a radioactive waste disposal facility should be documented in the technical specifications or safety management regulations in accordance with the Nuclear Safety related Act and subordinate statute. The limiting conditions of operation of a disposal facility are as follows:
limiting conditions of disposal: type and amount of waste disposed of, total amount of radioactivity, and concentration limit per radionuclide;
limiting conditions of operation: waste handling operation, waste treatment operation, waste disposal operation, ventilation system, fire and explosion prevention, power supply system, and effluent monitoring;
waste acceptance criteria;
radiation control and monitoring;
control in management;
periodic safety review (PSR); and
physical protection. H.6.4 Operating Procedures
The NSSC Notice No. 2013-35 (Technical Requirements for the Operation and Control of Low and Intermediate Level Radioactive Waste Disposal Facilities) stipulates the detailed technical standards described below regarding operation of a disposal facility to ensure safe operation of the facility, prevention of disasters due to the facility, and environmental conservation. In addition, it requires the licensee of the facility to present the relevant content in permit application documents such as SAR, RER, safety management regulations, and QAP:
organization and functions;
zoning and access control;
in-operation disposal facility management standards;
waste management standards;
disposal facility closure standards; and
institutional control standards. For operation and management of a disposal facility, the licensee should establish operating procedures regarding receiving inspection, handling, storage, disposal,
- 152 -
radiation monitoring, and emergency measures for the waste, documented pursuant to QAP. The appropriateness of these procedures is to be confirmed through diverse regulatory inspections. H.6.5 Engineering and Technical Support
The Technology Development Center of the KORAD provides technical support for implementing regulatory follow-up actions and technology developments with an aim to prevent radiological hazards to the public health and the environment during the construction, operation, closure and institutional control period after closure, if necessary, by collaborating with external institutions. H.6.6 Procedure for Characterization and Categorization of Radioactive
Waste
To deliver radioactive waste packages to the licensee of a disposal facility, the generator should submit to the licensee an “Application Form to Request for Receipt of Radioactive Waste” with information on characterization of the waste to be delivered. The information on characterization of waste necessary for application for receipt is as follows:
physical, chemical, biological characteristics, and evaluation methods of the characteristics;
total radioactivity and radionuclide-specific concentrations;
maximum surface dose; and
safety characteristics of waste package and evaluation method.
The NSSC Notice No. 2013-29 (Acceptance Criteria for Low and Intermediate Level Radioactive Waste) limits radioactivity concentrations in each waste disposal package for the following radionuclides: 3H, 14C, 60Co, 59Ni, 63Ni, 90Sr, 94Nb, 99Tc, 129I, 137Cs, and gross alpha. H.6.7 Event Reporting and Record Management
The NSA prescribes that the nuclear enterpriser should immediately take all the necessary safety measures and report to the NSSC under the following cases:
if radiological hazards occur;
if a failure occurs in the nuclear power utilization facility; and
if there is any danger or possibility of danger to the nuclear power facility or radioactive materials due to earthquake, fire or other disaster.
- 153 -
The NSSC Notice No. 2013-50 (Regulation on Reporting and Public Announcement of Accidents and Incidents for Nuclear Power Utilization Facilities) stipulates in detail the event reporting system. It includes the objects and means of and procedures for reporting, and rating of incidents and failures. In particular, the reportable events at a radioactive waste disposal facility are as follows:
fire or leakage of radioactive materials during transport and packing;
surface contamination of areas other than radiation areas of the facility exceeding the limiting values due to the leakage of radioactive materials;
abnormal increase in the local radiation level;
unplanned and uncontrolled release of radioactive materials into the environment; and
release of radioactive materials exceeding the ECLs. The rating of accidents and failures is based on the International Nuclear Event Scale (INES) of the IAEA. Information on storage, treatment, or disposal of radioactive waste should be documented and kept in a disposal facility in accordance with Article 145 of the Enforcement Regulation of the NSA. The main contents are as follows:
radioactive waste records;
radiation safety control records;
disposal facility inspection records;
operation, maintenance, and management records;
disposal facility accident records;
environmental monitoring; and
meteorological records.
H.6.8 Analysis and Incorporation of Operating Experience
The operator of a radioactive waste disposal facility should re-evaluate and complement, if necessary, safety conditions of a disposal facility based on experience and data obtained from operation of a disposal facility and results of safety assessment.
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H.6. 9 Establishment of a Decommissioning Plan and Review of the Regulatory Authority
The operators of nuclear power facilities, before permanently terminating their business, should take necessary measures for protection against radiation hazards including transfer, safe-keeping, discharge, storage, treatment, disposal, decontamination and make a report to the NSSC. For its part, the NSSC may take necessary measures including collection of radioactive materials, decommissioning of any and all contaminated facilities, and other necessary measures. H.6.10 Establishment of a Closure Plan and Review of the Regulatory
Authority
The NSSC Notice No. 2013-35 (Technical Requirements for the Operation and Control of Low and Intermediate Level Radioactive Waste Disposal Facilities) stipulates the requirements regarding closure of a radioactive waste disposal facility. The closure of a radioactive waste disposal facility should be carried out according to a pre-approved closure plan and in a manner that facilitates follow-up institutional control, minimizes the need for continued maintenance, and facilitates follow-up environmental monitoring and surveillance. Prior to closure of a disposal facility, various licensing documents including the safety analysis of the facility should reflect the latest revisions. In addition, the total amount of waste disposed of, records of abnormal events that have occurred during operation and with possible effect on the safety of the disposal, and the radiological and non-radiological impact of disposal on the public and the surrounding environment should be reevaluated to prove the safety of a disposal facility. In addition, the operator should finally confirm the predicted performance throughout the period stipulated in SAR upon at the completion of closure. H.6.11 Implementation of Safety Regulations on Partial Operation of a
Disposal Facility
As part of efforts to resolve the shortage of capacity of on-site radioactive waste storage facilities of NPPs, the KORAD established a plan for partial operation of a disposal facility to store LILW from NPPs before completion of the whole facility including underground disposal silo. Based on the plan, the KORAD obtained a change permit from the regulatory body and completed the construction of some ground facilities like radioactive waste receipt/storage building first. Even though the disposal facility is still under construction, the receipt/storage building has already been put to use where 3,536 drums of radioactive waste from NPPs and 707.2 drums of radioactive wastes from
- 155 -
other places are stored as of late June, 2014. Once the construction of the disposal facility is completed, the radioactive waste stored in the receipt/storage building during the partial operation period is planned to be disposed of after confirmation of appropriateness of disposal. After the Fukushima nuclear accident occurred in Japan, a special safety check of the disposal facility was conducted in areas of construction, operation and disaster prevention focusing on the impact of natural disasters such as earthquake exceeding the design basis of 0.2g, typhoon, heavy rain, fire and radiological impact resulting from loss of all power systems, and it was confirmed that the facility was installed, constructed and operated in accordance with applicable standards. The KORAD transported LILW generated from the Hanul site (by using a ship (named HJ Cheongjeong Nuri)) and the Wolsong Site (by using vehicles) to the receipt/storage building of its disposal facility. For LILW transporting, the KORAD owns containers vehicles for transport containers and disposal containers, etc.
Eaclo recregacres
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ARTICLE
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- 156 -
AL MEASU
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, and
- 157 -
environmental monitoring: sampling location and time/date, analytical method and results; and
meteorological records: direction and velocity of the wind, atmospheric stability, precipitation, and atmospheric temperature.
With regard to a radioactive waste disposal facility, the following records should be maintained on an annual basis: 1) site characteristics investigation documents; 2) facility design and construction-related data; 3) waste receipt requirements and procedures; 4) SAR; 5) radiological environmental impact assessment; 6) data on the characteristics of the waste disposed of; 7) disposal facility and waste locations; 8) other data on the characteristics of a disposal facility; 9) environmental monitoring records; 10) records of unintentional accidents during operation and after closure; 11) closure-related documents; 12) QA documents, and 13) institutional control plan and its results. To preserve the records above, the licensee of a disposal facility should establish an organization, responsibility, and location for maintenance of records and should maintain and store records in a manner that provides a complete and objective description of activities in all stages of disposal. In addition, to ensure the use and maintenance of appropriate information at a post-closure stage, records should be updated and maintained such that they are easily accessible and usable. H.7.2 Institutional Control
In accordance with the NSSC Notice No. 2013-35 (Technical Requirements for the Operation and Control of Low and Intermediate Level Radioactive Waste Disposal Facilities), the operator of a disposal facility should establish and submit an institutional control plan to the NSSC by one year before the commencement of institutional control. In case they wish to revise the control plan, the operator should submit to the NSSC a statement of the reasons for revision and revised the control plan by June of the corresponding year before that when the revision is to take place. The institutional control plan should include the following:
control period;
control organization and responsibility;
characteristics of the waste disposed of, disposal facilities, and relevant site;
control methods (control items, control method per item); and
QAP regarding institutional control.
The institutional control period should be established considering of the characteristics of the waste, engineering design, site characteristics, predicted social activities related to
- 158 -
a disposal facility, records, and historical experience regarding maintenance. After the control period, further control activities should be unnecessary and the risk or dose calculated according to appropriate methods should satisfy the performance objectives for a disposal facility. Institutional control methods should be able to prove that radiation protection requirements are met by reasonably verifying the closure performance of a disposal facility. Institutional control consists of radiological environment investigation, non-radiological environment investigation, maintenance, site monitoring, access restriction, safety evaluation, and record-keeping. However, that detailed control methods may be adjusted according to the results of systematic safety evaluation of a disposal facility or the characteristics of a disposal facility and site. Site monitoring should meet the post-closure site monitoring plan presented in the site characteristics report or SAR for a disposal facility.
H.7.3 Intervention in Case of Unplanned Release
With regard to a radioactive waste disposal facility, the concentration of radioactive materials during ventilation and drainage should be monitored so that the concentration of radioactive materials released from the exclusion zone of the site does not exceed the ECLs. As for ventilation and drainage monitoring system, an alarm and automatic isolation of relief valves should be triggered when the set points have been exceeded. F.4.2 describes in detail actions to be taken in case of unplanned or uncontrolled release of radioactive waste to the environment from sources other than drainage and air vents. During the institutional control of a radioactive waste disposal facility, the unplanned release of radioactive materials into the environment should be prevented or monitored through radiation environment investigation, maintenance, and site monitoring activities.
I. TTrans
s-bou
undarry MMovemment
1.
In
2.
ARTICLE
Each Conthe appromanner cbinding in
so doing:
(i) a Coapproauthoconse
(ii) transto thomode
(iii) a Cotranstechnmanaconsi
(iv) a Cotranswith tsubp
(v) a Coapprotransconfoarran
A Contraradioactivstorage o
I. Tra
E 27. TRAN
ntracting Popriate steconsistent nternationa
ontracting opriate storized andent of the S
boundary ose internaes of transpntracting Pboundary
nical capacage the sistent with ontracting boundary the consenaragraph (ontracting opriate stboundary
ormity witngement ca
acting Partve waste toor disposal
ans-bou
NSBOUND
Party involvps to ensuwith the p
al instrume
Party wheps to ed takes pState of de
movemenational obliport utilize
Party whichmovemen
city, as wspent fuel this ConveParty whimovemen
nt of the S(iii) are me
Party whteps to
movementh this an be mad
y shall noo a destina.
undary
- 161 -
DARY MOV
ved in tranure that suprovisions
ents.
hich is a ensure thaplace only estination;
t through igations wd; h is a Statent only if
well as the or the rention; ich is a S
nt only if itState of det prior to tr
hich is a permit rent is notARTICLE,e.
ot licence tation south
y Move
VEMENT
nsboundaruch movem of this Co
State of at transbo with the
States of hich are re
e of destin it has t regulatorradioactive
State of ot can satisstination thransbound
State of e-entry intt or cann unless
the shipmeh of latitud
ement
ry movemement is undonvention
origin shoundary m prior not
transit shaelevant to
ation shallhe adminy structure
e waste i
rigin shallsfy itself inhat the reqary movemorigin sh
to its tenot be c
an alter
ent of its e 60 degre
(Articl
ent shall tadertaken iand relev
hall take movement tification a
all be subjthe particu
l consent tnistrative ae, neededn a man
l authorizen accordanquirementsment; hall take erritory, if completed rnative s
spent fuelees south
le 27)
ake n a
vant
the is and
ject ular
o a and d to ner
e a nce s of
the a
in afe
or for
3.
ReguEnfoStand(Reg
The ReguincorMateon thCurrerevisin 20 ArticEnfoStandthe N
Nothing
(i) the eair nalaw;
(ii) rightsfor prwaste
(iii) the repro
(iv) rightsreproand State
ulations onorcement Ddards for R
gulation on t
domestic ulations forrporation oerials (ST-1his are appently, Notic
sed in order012) to the t
cles relatedorcement Ddards for R
NSA, Articl
I.1 Do
in this Con
xercise, byavigation r
s of a Conrocessing e and otheright of a
ocessing; s of a Coocessing toother prod
e of origin.
n transport Decree, its Radiation Sa
the Packagi
regulations r the safef the 1996) into the N
plied to theces of the Nr to apply thtransport of
d to transpoDecree, its Radiation Sales 108 thro
omestic T
nvention p
y ships andrights and
ntracting Pato return,
er productsa Contrac
ontracting o return, orducts resu
of radioacEnforceme
afety Managng and Tran
on transpe transport IAEA Reg
NSA was me safety maNSSC relatehe latest verf radioactive
ort of radioEnforceme
afety Managough 114 of
Transpor
- 162 -
rejudices o
d aircraft o freedoms
arty to whor provide
s after treatcting Party
Party to wr provide foulting from
ctive materent Regulagement, etc.nsport of Ra
port of radof radioa
gulations fmade from 1anagement ed to transprsion of the
e materials.
oactive maent Regulagement, etcf its Enforce
rt Regula
or affects:
of all Statess, as provi
ich radioace for the retment to thy to expo
which speor the retu
m reproces
rials are dation and ., and the Nadioactive M
dioactive mactive matefor the Safe999 to 200of transpor
port of radie IAEA Reg
aterials are ation and c. Especiallyement Decr
ations
s, of maritided for in
ctive wasteeturn of, thhe State of ort its sp
nt fuel is rn of, radiosing opera
described inRegulations
Notice of theMaterials)
materials areerials of te Transport1 and the rert of radioaioactive magulations (S
reflected iRegulations
y, Article 7ree, Articles
me, river a internatio
e is exporhe radioact origin;
pent fuel
exported oactive waations to
n the NSAns on Teche NSSC 20
e based onthe IAEA. t of Radioaregulations bactive mate
aterials are SSR-6, publ
in the NSAns on Tech
1 through 7s 98 through
and onal
rted tive
for
for aste the
A, its hnical 13-27
n the The
active based erials. being lished
A, its hnical 77, of h 128
- 163 -
of its Enforcement Regulation, and Articles 89 through 128 of the Regulations on Technical Standards for Radiation Safety Management, etc. stipulate the registration of transporting radioactive materials, criteria of both transporting and packaging for radioactive materials, radiation exposure management of transport workers, action for the accident during transporting, inspection for transporting, and design approval and inspecting of transporting cask. The detailed technical regulations on the safe transport of radioactive materials are described in the NSSC Notice No. 201309-27 (Regulation on the Packaging and Transport of Radioactive Materials) and No. 2013-51 (Regulations for Manufactures and Periodical Inspection of Transport Containers for Radioactive Materials), respectively. In addition, Korea joined the Antarctic Treaty in 1986 and the Protocol on Environmental Protection to the Antarctic Treaty in 1996, it has been observing the obligations stipulated in the treaty and protocol (radioactive waste and radioactive material related articles, etc.) in accordance with the Act on Antarctic Activities and the Protection of Antarctic Environment and its Enforcement Decree.
I.2.1
The expostand I.2.2
The of trpackperfotransrequisame I.2.3
The packas limateof trafissiorespoby trtranssaid
General
general safosure manadards, educa
2 Transpor
safety requiansport con
kage, and pormance reqsportation airements fore as ones sp
3 Transpor
safety requikage, A-typeimit of raderials, manaansportationon materialonsibilities ransport mesport conforIAEA Regu
I.2 Sa
Requirem
fety requiremagement, emation of tran
rt Contain
irements forntainer corrpackages cquirements and transpor transport cecified in th
rt
irements foe package, Bdiological mgement of tn grade, Indls, managemof transpor
eans such arm to the reulations (ST
afety Req
ments
ments for trmergency nsporting w
ers
r transport cresponding containing
and safetyortation acccontainers che IAEA Re
r transport B-type packmaterial amtransport inddication andment of surrter and shipas vehicle, aequirementsT-1).
quiremen
- 164 -
ransport of response, Q
workers, etc.
containers sto the IP-tfissile mat
y test requircident condconform to egulations (
include reqkage and pamount, limidex and nucd labeling orface dose ipper as weairplane, ans which are
nts
radioactiveQA, comp
specify the type packagterials that rements in
ditions. Genthe requirem
(ST-1).
quirements backage contait of mixeclear criticaof loads, isorate and co
ell as safetynd ship. Th, in general
e materials sliance of
safety requige, A-type p
are divideconditions
neral requirments which
by type of laining fissild loading l safety indeolation of loontaminatio
y managemeese safety rl, same as o
specify raditransport s
uirements bypackage, B
ded into geof both no
rements andh are, in ge
load, e.g. IPle materialswith dang
dex, classificoads and nuon of loadsent requiremrequiremenones specifi
iation safety
y type B-type eneral ormal d test neral,
P-type s such gerous cation uclear s, and ments ts for ied in
I.3.1
The matethe IAan apcontainspemanudate I.3.2
As fospecitype be ncommfactotransobey Morepackrequipassiaccorradio I.3.3
Ther1998USAthe s
Design A
approval perial, designAEA Regulpproval forainer, for wection uponufactured coto ensure sa
2 Report o
for B-type pial arrangemof load, a w
notified to tmence, andors detrimensport inspecying transpo
eover, a perkages, B(U)iring speciaing throughrdingly not
oactive mate
3 Cases of
re has been n8, all of the A as soon as
ealed sourc
I.3 Ap
Approval
rescribed inn approval flations for tr design of which a den manufactuontainer in uafety for con
n Transpo
packages, pment approvwritten tranthe NSSC
d the NSSCntal to safetction or perort regulatio
rson who in)-type packal arrangemeh Korean tlater than s
erials.
Trans-bo
no trans-bo299 spent f
s the decomce).
pproval a
n the NSA for transporthe Safe Tratransport csign approv
uring. In aduse at the inntinuous us
ort
ackages conval, the detansport procein five day
C should rey, if any, prriodic inspens.
ntends to hkages contaent approvaerritorial wseven days
undary Mo
undary movfuel rods st
mmissioning
and Adm
- 165 -
includes drt container,ansport of Rcontainer afval is gran
ddition, an interval of evse.
ntaining fisails of transpedures and ays before teview said rior to transections are
have a ship aining largeal upon arriv
waters or aein advance
ovement
vement of Ltored in the g of KRR-1
ministrativ
design appro, and speciaRadioactive fter a safetynted, shouldinspection fvery five ye
ssile materiport includian accidentthe date thedetails, andsport. As foconducted
or an airple radioactivving in anyerial routesto start ope
LILW to or research re
1 and 2 was
ve Action
oval for speal arrangem
Material. Ty review. Ad undergo afor use is coears from th
als, and pacing radioactt response pe transport d issue an or declared l
to check th
ane loaded ve material
y port or airps, should nerations afte
from Koreaeactor were s initiated (r
n
ecial radioaments specifiThe NSSC i
And the trana manufactonducted fo
he manufact
ckages requtive contentprocedure sh
is schedulorder to coloads, indivhe possibili
with B(M)ls and packport in Kor
notify the Ner the loadi
a to date. Insent back t
refer to J.2
active fied in issues nsport turing or the turing
uiring ts, the hould led to orrect vidual ity of
)-type kages ea, or
NSSC ing of
n June to the .3 for
JJ. Dis
used
d Seal
led Sourcces
1.
2.
The estabthe Kfaciliwas respoaccor
RI wfromthe alicenEntru
RI wdirec
J
ARTICLE
Each Conthe approdisposal o
A Contrasealed sothat they the disus
RI waste mblished in OKAERI, RI ity was opetransferred
onsible for rding to the
waste managm the use fac
administratinsing, safetyusted by the
waste has to ctly, or a tra
J. D
J.1 Le
E 28. DISU
ntracting Popriate steof disused
acting Partources if, be returneed sealed
managementOctober 198
waste was erated until d from the
manageme NSA and t
gement is pcilities specive superviy review, ane NSSC.
be collectedansport agen
Disused
egal Syst
USED SEA
Party shallps to ensu sealed so
ty shall allin the framed to a masources.
t business fo9. After concollected bthe end of NSSC to Ment and opthe EBA.
part of storacified in Arision of mand regulato
d and delivent.
d Seale
tem
- 169 -
ALED SOU
, in the fraure that theources take
low for reemework of anufacturer
for the safe nstruction o
beginning A1996. The rMOTIE in peration of
age and trerticle 9 of tanagement
ory inspectio
ered to the w
ed Sour
RCES
amework oe possesses place in
entry into its nationr qualified
treatment aof the RI w
August 1990responsibili
1996, andf the RI w
atment of rhe RWMAof RI was
ons for the
waste mana
rces (A
of its natioion, reman a safe ma
its territoral law, it hto receive
and storage aste manag, the RI waty of RI wa
d currently waste mana
radioactive . MOTIE is
ste. The KIwaste man
gement faci
Article 2
onal law, tanufacturinganner.
ry of disushas accep and posse
of RI wastegement facilaste manageaste manage
the KORAagement fa
waste genes responsibINS implem
nagement fa
ility by a R
28)
ake g or
sed ted ess
e was lity at ement ement AD is acility
erated le for ments acility
I user
J.2.1
DisuusersNSAradiawith the Kin ac J.2.2
In acGeneuse Rprovifrom GenepermgeneobserThe cKOR
The ArticDecr(Regand
J
1 Requirem
used sealed s in the sto
A. Specifyination safety
regard to tKORAD safccordance w
2 Managem
ccordance werating DevRI should oisions of K
m the NSSC.
erally, disumitted stora
rating RI wrved by Racollected R
RAD, after m
KORAD tacle 4 (Radiree of the gulation on Spent Fuel
J.2 M
Procedure
ProcedureFacility by
ments for
sources gerage facility
ng matters oy report is the storage fely stores a
with the NSA
ment
with Article vices) of theobtain a per
KORSAF. T
sed sealed ge facility,
waste, as spdioisotopes
RI waste shomanagemen
akes over diioactive W
RWMA. the Calculal Managem
anageme
es for Wast
es for Opery KORAD
Facilities
enerated froy which paon safety scompulsorycapacity of
and manageA. The facil
53 (License NSA, RI urmit for use
The use of d
sources ar, and then ecified in th
s Seller), maould be transnt cost is pai
isused souraste DeliveIn accord
ation Standament Fee), th
ent of Dis
te Managem
ration & Ma
- 170 -
and Hand
om RI userassed a facisuch as shiey includingf the facilityes RI wastelity is annua
e for the Ususe facilitiee of RI fromdomestic R
re stored tedelivered
the NSSC Nay entrust thsferred to thid as provid
rces of decaery Procedudance with ard for Radhe KORAD
sused Se
ment by RI
anagement
dling
s are tempility inspectelding, was
g their safety, and to k
e in its manaally inspecte
se, etc. of Rs who wishm the NSSC
RI requires o
emporarily to the KO
Notice No. he collectiohe RI wasteded in the R
ayed radioaure and Me
the MOTdioactive WD operates
ealed Sou
I User
t of the RI
orarily mantion in accote managemty managemeep them sagement faced by the re
Radioisotopeh to import fC and meetonly a perm
in a sourceORAD. Dom2013-33 (R
on of RI wae manageme
RWMA.
ctivity fromethod) of t
TIE Notice aste Managthe RI wa
urces
Waste Man
naged by thordance witment, etc. iment regulaafely. Currcility in Da
egulatory bo
es and Radifrom abroat the import
mit for use
e containermestic RI
Regulations aste to RI seent facility o
m RI users uthe Enforce No. 2013
gement Expaste manage
nagement
he RI th the in the ations ently,
aejeon ody.
iation d and tation of RI
r at a users to be
ellers. of the
under ement 3-128
penses ement
faciliThe n
J.2.3
CurreBasemanuOn th60Coreturof diimpothen
ity and safenational RI
3 Return
ently, the seed on a saufacturer, sohe other han, when they
rn the disuseisused seal
ort requiremdelivered to
ely stores awaste mana
Figure
ealed sourcales contracome of the nd, in case oy are expored sealed soled sources
ments set foo the KORA
nd manageagement sy
e J.2-1. RI W
es used in Kct betweendisused seaof the sealerted to foreources, they requires arth in the N
AD RI wast
- 171 -
s RI waste ystem is show
Waste Man
Korea are mn a domestaled sourcesed sources meign countriy can be retuappropriate NSA. The dte managem
that has bewn in Figur
nagement S
mostly impotic licenseds are returnemanufactureies and if aurned to theprocedures
disused sealment facility
een receivedre J.2-1.
ystem
rted from fod RI sellered to a foreied in Korea a foreign RIe seller in Ks that inclued sources .
d from RI u
foreign counr and a foign manufacsuch as 192I
RI user wishKorea. The rude meetinfrom abroa
users.
ntries. oreign cturer. Ir and hes to return g the
ad are
KK. Saafety
Imp
proveementt Acttivitiees
In thand gove - Th
manstak
- EnhNP
- Com- Sol Diveare decofaciliwill LILWstorapowe The nucleas a teamcyclebasisaccidindicearththis shortwors
K
he 4th reviewon the Saf
ernment con
he national nagement keholders; hancement Ps; mmissioninlutions for p
erse activitiedescribed mmissioninity is in the commence
W disposal age capacityer site or sp
governmenear facilitiefollow-up
m was organe facilities. s of extremedents and emcated that thhquake and country so t-term imprst natural dis
K
K.1 MPr
w meeting ofety of Rad
ntinues to ad
policy on options, re
of the regu
ng Wolsong providing en
es and efforin K.4 an
ng of NPPsfinal stage its operatifacility are
y for spent ent fuels ar
nt decided ts in Korea to the Fuku
nized to conThe inspec
e natural dimergency rehe NPPs in tsunami prefar. Howe
rovements fsasters in vi
K. Safe
easures revious R
of Joint Condioactive Wddress with
SF managesults of R
ulatory fram
LILW Dispnlarged stor
rts to formund the im
s is describas of Auguon in late 2e describedfuel, high e transferre
o conduct aat the Nuclushima Dainduct inspection team isasters, preesponse. ThKorea wer
edicted basever, the gofor guarantiew of the a
ty Imp
Taken toReview M
- 175 -
nvention onWaste Manhigh interes
gement to bR&D proje
mework and
posal Centerage of SF
ulate a natiomprovemented in F.6.
ust 2014 and2014. Deta
d in Chaptedensity sto
ed to the nei
a comprehelear Safety Ciichi NPP aections of Nconducted
evention of he results ofre safely deed on seismovernment hteeing a colaccident at t
provem
o ChallenMeeting
n the Safety nagement, cst were iden
be developects and c
d technologi
er in 2014
onal policy t of the rThe constru
d it is expecails of constr H. As parage racks ghboring un
ensive specCommittee accident. ThNPPs, HAN27 inspecti
f severe accf the speciaesigned and
mological inhas identifild shutdowthe Fukushim
ment Ac
ges Iden
of Spent Fuchallenges tntified as fo
ed consideronsensus a
ies for deco
for spent fregulatory uction of a
cted that thetruction and
art of effortare installenits.
ial safety in(NSC) on M
he special sNARO and ion items didents, mitil safety insp
d operated avestigationsed a total n of the Nma Daiichi
ctivitie
tified at t
uel Managethat the K
ollows:
ering variouamong inv
ommissioni
fuel manageframework
a LILW dise disposal fad operationts to expaned in the nu
nspection oMarch, 21, safety inspethe nuclear
derived fromigation of spection for against the s and researof 50 long
NPPs even iNPP. The s
es
the
ement
Korean
us SF olved
ing of
ement k for sposal acility n of a nd the uclear
on the 2011
ection r fuel m the severe those worst rch in - and in the safety
- 176 -
of the temporary storage facilities of spent fuel at NPP has also been checked in terms of the cooling ability and a loss of the spent fuel pool cooling function at the emergency situation. In order to enhance the safety of the temporary storage pool at NPP, the ‘Ensuring Countermeasures against Loss of the Spent Fuel Pool Cooling Function’ has been identified among the 50 long- and short-term improvements. As a result of this item, an external emergency cooling water injection path to the storage pool of spent fuel has been installed at all NPPs. The 50 improvements have been consistently revised in order to adopt the various kinds of the countermeasures and the recommendations from the stress test by IAEA and other countries. Additionally, the MOTIE and the KORAD conducted the special safety check of the disposal facility in areas of construction, operation and disaster prevention focusing on the impact of natural disasters such as earthquake exceeding the design basis of 0.2g, typhoon, heavy rain, fire and radiological impact resulting from loss of all power systems. The result of the safety check of the disposal facility confirmed that the facility was installed, constructed and operated in accordance with applicable standards. Pursuant to the Guidelines regarding the Form and Structure of National Reports (INFCIRC/604/Rev.3), the Korean government has made public the results of internal peer review mission and implementation of the Joint Convention. The results of IAEA IRRS mission to the republic of Korea is described in K.6. For greater openness and transparency of information about the results of implementation of the Joint Convention, the national report and the results of the Review Meeting are made public through the website of the KINS.
The wasteparticIAEAresearegulincorinto lare u - IAE- IAE- IAE Thansyste
K
Korean rege and spencular, the reA safety starch findinglations. Buirporated intlaws, after d
under analys
EA GSR PaEA SSR-5 DEA SSG-15
nks to thoseems for radi
K.2 Tefo
gulatory bodnt fuel andegulatory botandards reggs into the ilt upon reto NSA, andue considesis for incor
art 5 PredispDisposal of Storage of
e efforts, it ioactive was
echnologor the Rad
dy strives tod to advancody conductgarding the
regulatorysearch find
nd legislateseration of Krporation int
posal ManagRadioactive
f Spent Nucl
is expectedste and spen
gy Improvdioactive
- 177 -
o improve tce the relats policy re
e safety of y frameworkdings, the rs regulatory
Korean situanto Korean r
gement of Re Waste lear Fuel
d that the snt fuel will b
vement oe Waste M
the safety mted systemsearches to radioactive
k and lawsregulatory by requiremeation. The beregulatory re
Radioactive
safety manabe improve
of the RegManagem
managemens for safetyanalyze the
e waste ands of Koreanbody identients and tecelow IAEA equirements
Waste
agement and significan
gulatory ment
nt for radioaty regulatioe recent trend to incorpn nuclear sifies items chnical stan
A safety stans.
nd the regulntly.
Systems
active on. In nds of porate safety to be
ndards ndards
latory
s
As Nforesin va The Ndecoperiosubo The decoinstitdecoformdecotechnBesidRadirecal The decobasedresuldecowaste As dinstitregulimpr
K
NPPs exceeseeable futuarious ways
NSSC and mmissionin
odic revisiordinate statu
KHNP hmmissionintute in 20mmissionin
mulated andmmissioninnology will des, the KHoactive Walculated eve
KAERI isntaminationd on its explts of the ntaminatione with uran
described abtutes are platory framroving the e
K.3
eding its dure, the Kor.
the KINS ang, submittaon of the ute and rela
has establing policy an013 and wng organizad implemenng since 201
be availabHNP has raste Manageery two year
s currentlyn technologperience ofresearch, t
n system, reium.
bove, the Kopreparing f
mework and fficiency an
design life rean govern
are workingal of a decodecommiss
ated technic
ished a tnd technolowhen decoation will bnted a tec13 and it is le in 2027 weserved a fement Act ers by decom
y conductingy and intef decommisthe KAERemote contr
orean regulafor decomm
to developnd safety of
- 178 -
is expectednment is pr
g on to revisommissioninsioning placal standards
team chargogy both in ommissioninbe launchedchnology dexpected thwhen the 3fund for fuevery year
mmissioning
ng a decomegrated assssioning res
RI will devrol of high l
atory body,missioning, p decommisf decommiss
d to be shueparing for
se the NSAng plan at t
an. When ts will be rev
ged with the head ofng commed on site. Fdevelopmenhat a comme3rd stage of ull decommand the res
g cost calcul
mmissioninessment of
search reactvelop technload materia
the NPP opand curre
ssioning tecsioning in th
ut down pedecommiss
A to specify he time of the revisionvised or dev
developmeffice and itsnces in e
Furthermorent road mercialized dthe road ma
missioning aerved fund lation comm
g research f decommistor 1 and 2nologies sual and dispo
perator and ent effort chnology whe future.
ermanentlysioning of N
the definitiCP and OLn is compveloped.
ent of nus central researnest, a e the KHNP
map for nudecommissio
map is compaccording tis reviewe
mittee memb
h on high ssioning pr
2. Built upouch as cheosal of com
nuclear resto improve
will contribu
in a NPPs
ion of L, and leted,
uclear search
local P has uclear oning leted.
to the d and bers.
level rocess on the mical bined
search e the ute to
In thLILWfaciliconsipubli Accoreviesubm It waspentfor pthe b Thus2009a connext projeverifat hofuel m In thdecidwhicManapubli AccoManapubliKoreaccor
K
he 253th meW disposal ity and to pideration ofic consensu
ordingly, thew and discmitted a Pub
as recommet fuel mana
public discubest proven
s, the gover9 to carry ounsulting pro
21 monthsect, the satfied and theome and abrmanagemen
he 2nd meetded on the ch was outliagement, asic engagem
ording to thagement wiic engagemean governmrding to wh
K.4 Sp
eeting of Afacility in
push forwarf domestic aus.
he governmcuss public
blic Engagem
ended in thagement, hossion in themethod for
rnment revut public enoject attendes to reviewturation time status of sroad was annt in Korea
ting of Nuc“Executionined to forms an indepe
ment process
he Plan, thill continue
ment recommment will d
hich, prepare
pent Fue
AEC held inthe first pld with a naand internat
ent ran a P engagemement Repor
e public enowever, to pe first place,
final spent
ised the Rangagement ed by exper
w methods me of spentspent fuel mnalyzed andwere review
clear Promon Plan for Em a Public endent advis.
he Public Eto carry ou
mendation develop a ed the Basic
l Manage
- 179 -
n Decembeace, separa
ational polictional techn
Public Engaent in spentrt to the gov
ngagement rput a metho, given that fuel manag
adioactive Wactivities efrts in nuclefor spent
t fuel tempmanagementd short-, miwed.
otion CommEstablishme
Engagemensory body i
Engagementut activities report. Basnational poc Plan for R
ement Po
r 2004, it wately from acy for spentology devel
agement Tat fuel manavernment in
report to deod for interit would ta
gement.
Waste Manffectively, aar power anfuel manag
porary storat policies and- and long
mittee held nt of Spentnt Commissin the 1st ha
t Commissito collect p
sed on the olicy for sp
Radioactive
olicy
was decidea spent fuelt fuel managlopment as
ask Force oagement andApril 2008
etermine a mrim storage ake significa
nagement Aand subseqund radioactigement inteage facilitiend technolog-term altern
in Novembt Fuel Manasion on Spealf of 2013
ion on Speublic opiniooutcome ofpent fuel mWaste Man
ed to constrl interim stgement aftewell as bas
on Spent Fund the task 8.
method formanageme
ant time to s
Act in Deceuently condive waste foensively. Ines of NPPsogy developnatives for
ber 2012, iagement Poent Nuclear to speed u
ent Nuclear ons and subf the repor
managemennagement.
ruct a orage
er due ed on
uel to force
r final ent up select
ember ducted or the n this s was pment spent
t was olicy” r Fuel up the
Fuel bmit a rt, the t and
The undethe pnear- SincedispoSafetprojeprogrverif As pprincfaciliadditto adwhic Currethe sthe dasses
K
KORAD perground silplan to cons-surface dis
e the undeosal facilityty Case proect to ensureram consist
fication in a
part of efforciples of thity by assigtion, variouddress uncech will be, in
ently, the Kafety assessdisposal fassment and
K.5 En
plans to oplo type dispstruct the 2posal metho
erground siy exist togeogram devele the safetyts of strategccordance w
rts to increhe Safety Cgning safety
us events anrtainties imn turn, incor
Korean regusment of the
acility whicways for ap
nhancem
erate the 1posal metho2nd stage of od.
ilo type diether in the loped in conof the so-c
y, outline, bwith the saf
ease the safCase will bey functions
nd process wmportant to
rporated int
latory bodye combined
ch includes pplication o
ment of Sa
- 180 -
st stage of od after thef LILW disp
sposal faci same site,nsideration
called combbasis for assfety principl
fety of the e applied fs to each cwhich affecsafety, therto the desig
y is workingd disposal sy the basic f safety stan
afety of a
LILW dispe safety reviposal facili
ility and th the Koreaof IAEA stined dispossessment, sales of comb
combined from the deomponent o
ct the disposreby quantifn of the disp
g on to deveystem suitab
direction ndards.
a LILW D
posal faciliiew. The Kty based on
he engineeran governmtandards to al facility. Tafety assessined dispos
disposal facesign stage of the disposal facility wfying and oposal facilit
elop the reguble for the cand metho
isposal F
ity based oKORAD alsn the engin
red near-sument will ap
the construThis Safetysment, and ssal facility.
cility, the se of the disosal systemwill be ana
optimizing sty.
ulatory guidcharacterist
od of the s
Facility
on the o has
neered
urface pply a uction y Case safety
safety sposal ms. In alyzed safety
de for tics of safety
The Koreframstand The moduThe Matestand The technKoreComcoord AmoregulKorenatiohas icompcodeinforcertaguidereact The implemadecarryprote
K
IAEA's Intea was con
mework for dards.
IRRS Missules concernKorean go
erial (ARMdard questio
IRRS revinically capea's respon
mmunicationdination wit
ong the goolatory bodyea strongly onal and inteimplementeprehensive s and me
rmation andain issues wes to addretors.
follow-up ementation e by the IRy out the reection, radio
K.6 Int
egrated Regnducted in
nuclear s
ion team toning NPPs,
overnment pM) and docuons and the
ew team cable and ese to the
ns with theth internatio
d practices y of Korea h
supports ternational l
ed an effectisafety asses
ethods; thed data mana
warranting atess decomm
mission status of
RRS Revieweview in thoactive wast
tegrated
gulatory ReJuly 2011
safety regu
o Korea cona research
provided thumentation results of se
oncluded theffective nu
accident ae public, donal stakeho
identified bhas a clear athe global level; the Kive human ssment usine KINS hagement systtention or i
missioning,
will be caction plan
w Team. Duhe areas thate managem
Regulato
- 181 -
eview Servi1 to evaluulation obj
nsisting of 2reactor, andhe IRRS re
including elf-assessm
that the Kouclear safetat Fukushimdevelopmenolders was o
by the IRRand structurnuclear sa
KINS has a hcapital prog
ng a broad rhas a comstem. Howein need of iand QA p
conducted ns to addreuring that peat were not ment and nu
ory Revie
ice (IRRS) ate the effectively ag
21 experts fd radiologiceview teamanswers toent report.
orean goverty regulatorma has bent of actioof high qua
RS Review Ted national fety regimehigh level ogram; the Krange of det
mprehensiveever the IRRimprovemenlan for lice
in Decemess recommeriod, the focovered p
uclear cycle
ew Servic
Mission to fectiveness gainst inter
from 14 coucal emergenm with Advo as many
rnment has ry programeen promptons for imlity
Team are thapproach fo
e and provof technical KINS perforterministic ae integratedRS Review nt includingensing of re
ber 2014 mendations follow-up mreviously sfacility.
ce Missio
the Repubof the K
ernational s
untries revincy preparedvance Refeas 1,250 I
s implemenm and espe
t and effemprovement
he followingfor nuclear svides trainicompetenc
rms detailedand probabd computeTeam iden
g regulationesearch and
to reviewand sugges
mission teamsuch as radi
on
lic of Korean
safety
iewed dness. erence IAEA
nted a cially ctive. t and
g: the safety; ng at e and d and ilistic erized ntified ns and d test
w the stions
m will iation
A
Anneex
Anne
Sh
Sh
H
H
H
H
H
H
W
W
W
W
Shin
Wol
* : exc
An
ex A-1. Spe
Plant
Kori Unit 1
Kori Unit 2
Kori Unit 3
Kori Unit 4
hin-Kori Uni
hin-Kori Uni
Hanbit Unit
Hanbit Unit
Hanbit Unit
Hanbit Unit
Hanbit Unit
Hanbit Unit
Hanul Unit
Hanul Unit 2
Hanul Unit 3
Hanul Unit 4
Hanul Unit 5
Hanul Unit 6
Wolsong Unit
Wolsong Unit
Wolsong Unit
Wolsong Unit
n-Wolsong U
lsong Dry Sto
cept for emerge
nnex A
ent Fuel Sto
L
G
2
3
4
it 1
it 2
1
YongJeo
2
3
4
5
6
1
UGye
2
3
4
5
6
t 1
GGye
t 2
t 3
t 4
Unit 1
orage
ency cores
List of S(As of M
rage Facilit
Location
ijang-gun, Busan
ggwang-gunollanam-do
Ulchin-gun,ongsangbuk-
do
Gyeongju, ongsangbuk-
do
Spent FuMarch 31
- 185 -
ties for NPP
StorageType
Wet
n,Wet
- Wet
-Wet
Dry
uel Manag, 2014)
Ps
Inventory[MTU]
124.1
293.6
821.5
748.0
108.8
25.4
645.0
406.3
351.6
357.7
235.3
206.3
395.4
373.7
366.8
369.0
182.9
160.3
558.4
649.7
753.5
680.2
27.1
4,583.5
gement F
Total Capa[MTU
164
313
888
888
219
219
888
420
470
470
535
535
404
382
552
552
535
535
801
801
801
801
219
6,237
Facilities
acity (*) U]
ReT
4
P
3
8
8
9
9
8
P
0
0
0
5
5
4
P
2
2
2
5
5
PH
9 P
7
eactor Type
PWR
PWR
PWR
HWR
PWR
-
- 186 -
Annex A-2. Spent Fuel Storage Facilities for Research Facilities
Facility Location Storage
Type Fuel Type
Total
Capacity
(MTU)
Inventory
[MTU]
HANARO
spent fuel
storage
pool
Yuseong-
gu,
Daejeon
Wet
HANARO 36
element
fuel assembly
1.3 0.6
HANARO
18 element
fuel assembly
0.6 0.2
PIEF
spent fuel
storage
pool
Yuseong -
gu,
Daejeon
Wet PWR spent
fuel assembly10.5 3.3
Anne
F
Kobuil
Kobuil
Kobuil
Kobuil
Shin-buil
RCAf
Wolsbuil
RCAf
Hanbuil
Hanbuil
RCAf
Hanbuil
Hanbuil
RCAf
An
ex B-1. LILW
Facility
ori storage lding No. 1
ori storage lding No. 2
ori storage lding No. 3
ori storage lding No. 4
-Kori storage lding NO. 1
A and other facilities
song storage lding No. 1
A and other facilities
nbit storage lding No. 1
nbit storage lding No. 2
A and other facilities
nul storage lding No. 1
nul storage lding No. 2
A and other facilities
nnex B
W Storage f
Location
Gijang-gun,Busan
Gyeongju, Gyeongsang
buk-do
Yonggwang-gun,
Jeollanam-do
Ulchin-gun,Gyeongsang
buk-do
List of R(As of M
facilities for
Temporadioactiv
from K
Temporadioactivfrom Shin
Kori T
g
Temporadioactiv
froU
Wolson
g
Temporadioactiv
from Ha
Temporadioactiv
from Ha
Hanbit
g
Temporadioactiv
from Ha
Temporadioactiv
from Ha
Hanul
Tot
RadioactMarch 31
- 187 -
NPPs
Purpose
orary storage ve wastes geneKori Units 1 to
orary storage ve wastes genen-Kori Units 1
-
Total
orary storage ve wastes geneom WolsongUnits 1 to 4
-
ng Total
orary storage ve wastes geneanbit Units 1 &
orary storage ve wastes geneanbit Units 1 t
-
t Total
orary storage ve wastes geneanul Units 1 &
orary storage ve wastes geneanul Units 1 t
-
Total
tal
tive Wast, 2014)
OperY
of erated o 4
19
19
19
19
of erated 1 & 2
20
of erated 19
of erated & 2
19
of erated to 6
20
of erated & 2
19
of erated to 6
19
te Manag
ration ear
Capa[200 L
Dru
978 10,0
979 6,0
987 11,2
993 23,0
011 10,0
- -
983 900
- -
986 133
002 100
- -
989 740
997 100
- -
gement Fa
acity Liter um]
Inven[200 L
Dru
000 9,31
00 5,99
200 10,1
000 15,2
000 27
- 1,14
42,1
00 9,65
- 18
9,84
300 11,4
000 8,72
- 2,29
22,4
00 5,770
000 5,770
- 5,47
17,0
91,4
acilities
toryLiter m]
19
99
66
273
8
49
84
59
1
40
439
20
94
453
0.5
0.5
75
016
493
- 188 -
Annex B-2. Radioactive Waste Treatment Facilities for NPPs
Reactor
Type
Characterist ics
Gaseous Liquid Solid
PWR
Treatment by gas
decay tank or charcoal
delay bed for effluent
processing
Treatment by filtering,
evaporation or ion
exchange method
Treatment by sorting,
compacting, drying or
solidification method
PHWR
Treatment by charcoal
delay bed for effluent
processing
Treatment by filtering,
or ion exchange method
Treatment by sorting,
compacting, or drying
method
* Radioactive effluent from buildings is treated through HEPA and/or charcoal filter.
Annex B-3. Radioactive Waste Storage Facility for Research Facilities
Facility Location Purpose Organization
Capacity
[200L
drum]
Inventory
[200L
drum]
Storage
building
Yuseong -gu,
Daejeon,
LILW generated in
research facility KAERI 25,618 20,033
Annex B-4. Radioactive waste Treatment Facility for Research Facilities
Facility Location Purpose Operation
Year
Facility Feature
Process Throughput
Radioactive
waste
treatment
facility
(RWTF)
Yuseong -gu,
Daejeon
Treatment of
radioactive
waste
generated from
research
facilities
1991
Bituminization 0.03 m3/h
Evaporation 1 m3/h
Compaction 60 ton
Solar
evaporation 0.6 m
3/h
- 189 -
Annex B-5. Combustible Waste Treatment Facility
Facility Location /
Organization Purpose
Operation
Year
Treatment
Capacity
Combustible
waste
treatment
facility
Yuseong-gu,
Daejeon /
KAERI
Incineration of
Combustible waste
generated from the
KAERI
2011 Combustible
waste 20 kg/h
Annex B-6. Radioactive Waste Storage Facilities for Nuclear Fuel Fabrication Facilities
Facility Location Purpose OperatorOperation
Year
Capacity
[200L
drum]
Inventory
[200L
drum]
2nd floor
of storage
building
No. 1
Yuseong-
gu,
Daejeon
Storage of
radioactive
waste
generated in
KEPCO NF
KEPCO
NF
1993 3,000
3,872 1st floor
of storage
building
No. 1
2004 1,900
Storage
building
No. 2
1998 4000 3,169
Total 7,041
- 190 -
Annex B-7. Radioactive Waste Treatment Systems at KEPCO NF
Facility Location Purpose OperatorOperation
Year
Characteristics
Throughput Main Process
PWR liquid waste
treatment system
in Plant 1
Yuseong-
gu,
Daejeon
Liquid
waste
treatment
KEPCO
NF
1988 18 m3/d
Lime
precipitation
and
centrifuge PWR liquid waste
treatment system
in Plant 2
PHWR liquid
waste treatment
system in Plant 2
Flocculation
Solid waste
treatment system
in Plant 1 Solid
waste
treatment
1988 -
Shredding
&
compaction
Solid waste
treatment system
in Plant 2
1998 -
Cutting
&
compaction
Annex B-8. RI Waste Management Facility
Facility Location Purpose OperatorOperation
Year
Capacity
[200L
drum]
Inventory
[200L
drum]
RI waste
management
facility
Yuseong-
gu, Daejeon
RI waste
temporary
storage
KORAD 1993 9,750 3,192.3
- 191 -
Annex B-9. LILW Disposal Facility (Radwaste Receipt/Storage Building)
Facility Location Purpose Operator Operation
Year
Storage
Capacity
[200-Liter
Drum]
Inventory
[200-Liter
Drum]
LILW
disposal
facility
(radwaste
receipt /
storage
building)
Gyeongju,
Gyeongsang
buk-do
Radioactive
waste receipt
/ storage
KORAD 2010 7,000 4,243.2
Fac
KR
KR
An
cility Loca
RR-1
Now
gu
Seo
RR-2
nnex C
ation Licen
won-
u,
oul
KAE
List of N(As of D
nsee Specifi
tion
RI
TRIGA
Mark-I
(250
kWth)
TRIGA
Mark-I
(2 MWt
Nuclear FDecembe
- 192 -
ica
Y
Operation
A
II
h)
1962
A
III
th)
1972
Facilitieser 31, 201
Year
n Closure
1995
1995
under D4)
Status
Under
decommiss-
ioning
ecommis
Estimat
Radioact
Waste
Weight
[ton]
T
R
a
[
28.1 3
115.2 1
ssioning
ted
tive
e
Total
Radio-
ctivity
[TBq]
3.7E-1
.5E+0
Reco
and i
the p
have
1. T
2. T
3. T
4. T
5. T
6. T
7. T
8. T
An
ognizing tha
improveme
people and p
the first an
To maintain
To release i
To reflect th
To assure th
To strength
To abide sin
To complem
To promote
nnex D
at the peace
nt of the qu
preservation
nd foremost
n the highes
information
he public op
he independ
hen research
ncerely by n
ment and im
e nuclear sa
Nuclear
ful use of n
uality of th
n of the env
priority ove
st standards
n regarding n
pinion in fo
dence and fa
h and develo
national laws
mprove the n
fety culture
r Safety C
- 193 -
nuclear ener
he people's
vironment t
er others, w
s of safety in
nuclear safe
ormulating n
fairness in nu
opment of te
s and interna
nuclear safet
e and incorp
Charter
rgy contribu
life, and co
through saf
we pledge ou
n the use of
ety promptl
nuclear safe
uclear safet
echnologies
ational agre
ty-related le
porate it in o
utes to natio
onfirming th
fe control o
urselves:
f nuclear ene
y and transp
ety policies;
ty regulation
s on nuclear
ements on n
egal system
our workpla
Se
onal develop
hat protecti
of nuclear en
ergy;
parently;
n;
r safety;
nuclear safet
continuous
ace.
eptember 6,
pment
on of
nergy
ty;
sly;
2001
1. In The nuclegrowStateactivthe G As dthrouin Juenergnucleorgansafet KorenuclenucleThernuclethey issue As aconc38th Isafetthat eeach The a higinternoverrdeve
An
ntroductio
following dear safety th
wing public ement is to vities by notGovernment
declared inugh the Yeauly 1994, Kgy for peaceear safety snizations anty principles
ea public’s ear accidenear movemrefore, peopear safety sshould dev
es.
a matter of ern. The “NIAEA Genety. Its objeceach contracontracting
Governmengh level of nationalizatriding priorlopment of
nnex E
on
declares thehrough the concern fo
improve thetifying the pt's basic pol
n the reportar 2030”, wKorean nucleful purpos
should be gnd individus as top prio
distrust of nnt. Sometimment, particple in the nuso that muchvote more ef
course, nucNuclear Saferal Conferectives are toacting party g country ha
nt of the Renuclear saftion and rarity should
f the nuclear
Nuclear
e Korean gsettlement o
or nuclear se consistencpublic and clicies regard
t titled, “Dwhich was alear policy es and impriven first puals engageority.
nuclear safemes we are ccularly in ruclear field h-needed puffort to com
clear safety fety Convenence is one o establish nfulfills its o
as an interna
epublic of Kfety throughtionalizatio
d be given r industry.
r Safety P
- 194 -
governmentof nuclear rsafety and cy, adequacconcerned pding nuclear
Directions oapproved at
is aimed aroving publ
priority in thed in nucle
fety has groconfronted regions whshould haveublic’s trus
mmunicating
is not a mntion” signeexample of
national meobligations ational resp
Korea will ch the enhanon of the re
to the ass
Policy Sta
’s major poregulatory gthe environ
cy and ratiopeople in anr safety.
of Long-terthe 234th A
at establishilic welfare. he developmear power
own significwith a voc
here nucleae a more prst and config with the p
matter for oned by IAEAf world-wideasures on nunder the sa
ponsibility f
continue to pncement of egulatory sysurance of
atement
olicies for tgoals and prnment. The onality of nund out of the
rm NuclearAtomic Enering the safeTherefore,
ment of nucactivities sh
cantly due tal and oftenar facilitieso-active attdence can bublic to res
ne country bA member sde efforts to nuclear safeaid Conven
for nuclear s
pursue its gsafety technystem, reco
nuclear sa
the assuranrinciples to purpose ouclear regule nuclear fie
r Energy Prgy Commi
fe use of nuthe assuran
clear powerhould adhe
to the Chernen powerfuls will be titude in assbe obtained
solve outstan
but a worldstates durinenhance nu
ety and to ention. As a rsafety.
goal of achinologies an
ognizing thaafety befor
nce of meet f this latory eld of
Policy ission uclear nce of r, and ere to
nobyl anti-built.
suring d, and nding
dwide ng the uclear ensure result,
eving nd the at the re the
- 195 -
2. Safety Culture The Korean government reaffirms that nuclear safety takes top priority in the development of nuclear energy and that it should be of foremost concern to organizations and individuals engaged in nuclear activities. The Government also develops safety culture, which was presented by the IAEA, recognizing that nuclear safety issues are more closely related to human factors rather than to technical ones, as demonstrated by two nuclear accidents of TMI and Chernobyl. The safety of nuclear facilities can be secured through dedication to common goals for nuclear safety by organizations and individuals at all levels by giving a high priority to safety through sound thought, full knowledge and a proper sense of safety responsibility. The Government recognizes that nuclear safety is achieved not only by safety systems and strict regulations throughout the stages of design, construction, operation and maintenance of nuclear power plants, but also by the spread of safety culture. In meeting this commitment, the Government strives for strict regulations through the development of clear safety goals and regulatory policies. It will actively encourage safety-related research and technical developments to achieve technical expertise in regulatory activities and will ensure regulatory independence and fairness by minimizing any undue pressure and interference. Nuclear utilities establish management policies, giving high priority to nuclear safety, and foster a working climate in which attention to safety is a matter of everyday concern. Managers encourage, praise and provide tangible rewards to employees for commendable attitudes and good practices concerning safety matters. On the contrary, when errors are committed, individuals are encouraged to report them without concealment and to correct them to avert future problems. For repeated deficiencies in or negligent attitudes toward nuclear safety, managers take firm measures in such a way to prevent the same errors from occurring again. In this way, safety culture can be achieved through sound safety policies and full understanding of safety culture by senior management and through proper practices and implementation by individuals engaged in the nuclear industry. 3. Regulatory Principles The ultimate responsibility for safety of nuclear facilities rests with the licensee. This is in no way diluted by the separate activities and responsibilities of designers, suppliers, constructors and regulators.
- 196 -
The Government has an overall responsibility for ensuring the protection of the public health and the environment from radiation hazards that may occur in the development of nuclear energy. It inspects and ensures the appropriateness of the licensee's safety practices through nuclear regulations and establishes a high level of safety assurance in order to achieve safety goals on a government level. To effectively regulate, the Government sets forth the following five principles to encourage high-safety performance.
A. Independence
The Government establishes the legal framework for the independent regulatory organization responsible for nuclear regulatory activities. It takes proper measures to ensure the independence of the regulatory organization, which is functionally separated from other organizations and systems involved in the development of nuclear energy. It also ensures that the regulatory organization acts on its own objectives and technical judgment without any political interference and influence from external sources. The regulatory organization should maintain an extensive program of research and sufficient staff resources to review and audit licensee’s submittals so that it can independently verify the validity of a licensee’s assertions, which are critical to regulatory decisions. The regulators do their work seeking to achieve the highest standards of ethical performance and professionalism. Regulators’ decisions and judgments must be based on objective, unbiased assessments, considering possible conflicting interests of those involved, and their work must be documented. Based on safety culture, the regulatory organization should support and guide the licensee in solving its problems, but only to the extent that the regulatory organization's independence is not impeded.
B. Openness
The purpose of nuclear regulations is to protect public safety and to ensure that all activities are legal and public. The Government maintains an open channel with the public for regulatory information so that the public can understand and rely on the regulatory process. The Government is also devoted to establishing a sound social stand on nuclear safety by making an effort to inform the public properly and openly of nuclear activities, including safety matters. The Government also develops nuclear policies based on public consensus, paying attention to the public's right to know about the regulatory process. To accomplish this, the Government extends an opportunity to the public to participate in regulatory processes and publicizes related information under the principle titled, “Openness and Democratization of Nuclear Administration”.
- 197 -
However, restricted information from industries or concerned individuals is protected and kept in confidence, and treated according to the provisions concerned. The Government objectively informs the public of its activities so that it may collect public opinions more soundly and properly, and it strives to get public consensus through constant communication and interaction with regulators, licensees and the public.
C. Clarity
Nuclear regulations should be enforced through clear regulatory policies, which are based on safety goals on a national level. There should be a coherent nexus between regulations and agency goals and objectives. Agency position should be documented to be readily understood and easily applied. The Government endeavors to ensure that the licensee is fully informed about regulators’ policies so that the licensee can prepare for new policies in advance in order to achieve nuclear safety effectively upon implementation. In a case where new or revised regulations are expected, the Government informs the licensee of the regulatory policies and provides guidance in advance and establishes regulatory practices to minimize the licensee’s process of trial and error caused by the revision of regulatory requirements. The licensee should thoroughly observe the NSA, technical standards and regulatory guidance, and if there is a need to revise them or there are any unreasonable acts or technical standards, the licensee should communicate its view with the regulatory organization in order to initiate revisions.
D. Efficiency
The regulatory organization has the responsibility to provide the licensee and the public with the best possible management and administration of regulatory activities. To accomplish this, it must make constant efforts to evaluate and upgrade its regulatory capabilities. The regulatory organization should possess a sufficient number of staff that is capable in performing regulatory activities, which are closely connected with many technical areas, and regulatory activities must be performed efficiently to contribute to the achievement of the goal of “Nuclear risk reduction”. Regulatory decisions must be made with the best use of all resources invested in the regulatory process to minimize undue impediments. Before regulatory decisions related to the improvement in nuclear safety are made, the nuclear risk reduction scale and economic benefits that can be gained from the improvement should be reviewed first. To efficiently perform regulatory activities with limited capabilities and time,
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appropriate prioritization of regulatory activities must be made based on risks, costs, and other factors. Regulatory alternatives, which minimize cost, are adopted unless they increase the degree of risk, and in all cases resources should be used effectively for the improvement of nuclear safety.
E. Reliability
The regulatory organization endeavors to eliminate public distrust and fear of nuclear activities and to obtain the public’s trust and support through fair regulations based on technical and professional judgments. Regulatory decisions must be made promptly and fairly, and reliably based on the best available knowledge from research and operational experiences. The Government obtains up-to-date technical information on nuclear safety and applies this information to regulatory activities. When regulatory requirements need to be either newly established or changed, the most suitable option is adopted after the effectiveness of its implementation and technological difficulties resulting from any changes are sufficiently reviewed. The Government does its best to run its regulatory system efficiently and systematically, and to thoroughly enforce the regulations in order to secure the public's trust on nuclear safety systems.
4. Directions of Nuclear Safety Policy To quickly realize the establishment of safety culture and a safety assurance system, each organization prepares its “Implementation Program of Safety Culture” and the regulatory body provides a systematic basis to evaluate the results of its implementation. Nuclear power plants in operation or under construction are supplemented with regulatory requirements consistently and systematically to achieve an international level of nuclear safety, taking into account the possibility of severe accidents. For newly constructed nuclear power plants, factors which may increase the total risk caused by the construction of an additional nuclear power plant at the same site of existing plants are to be mitigated by improving the safety level at each grade as compared with that of existing nuclear power plants. For nuclear power plants in operation, maintenance, repair, inspection, and monitoring of components are to be strengthened. “Periodic Safety Reevaluation” is established and implemented to reassess and supplement safety deficiencies which may be caused by the aging of facilities and application of old technical standards.
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In accordance with regulatory requirement changes in and out of the country, the existing atomic energy law system is to be revised and supplemented, and related technical standards and regulatory guidance are to be maintained in order to efficiently perform regulatory activities. In consideration of the technical expertise required for nuclear regulatory activities, safety research should be continuously strengthened to meet the growing demand of regulatory requirements due to technical advancements in the nuclear field. Solutions for unresolved safety issues, including generic safety issues of nuclear power plants, are promptly found and reflected in policy. Operating records and accident and failure data are analyzed to determine factors that affect the safety of nuclear power plants, and efficient safety supplementary measures are also established. The regulatory organization reviews the introduction of “Optimum Assessment & Probabilistic Assessment” for safety analyses, and encourages the licensee to introduce new technologies when and if they are considered to be reasonable safety assurance measures, as proven by their application. An “Overall Safety Assessment” is performed using probabilistic safety assessment and “Nuclear Regulation based on Risk” is done through sound safety regulations in consideration of cost-benefit factors. Quantitative safety goals and regulatory guidelines for the examination, prevention and mitigation of severe accidents are established and improved to be gradually applied to advanced nuclear power plants as well as to existing facilities. In addition, design and operational safety of nuclear power plants are achieved through these measures in order to minimize human error. Radiation protection is achieved by the concept, “Radiation exposure should be kept as low as reasonably achievable (ALARA)”, taking into account economic and social circumstances, and for individual exposure dose, the introduction of radiation protection standards based on the new ICRP 60 recommendations are being favorably reviewed. In response to growing public concern about nuclear safety, nuclear safety-related information and regulatory activities are open to the public through the publication of the “white paper on nuclear safety” and through the periodic release of information about accidents and failures at nuclear power plants.
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5. Conclusion The nuclear community strives for the public’s proper understanding of nuclear energy and the establishment of safety culture by hearing and addressing the public’s concerns with understanding and by using the collected wisdom of those involved to solve any problem together. Nuclear safety cannot be achieved in a day, but rather it is secured through the licensee’s constant efforts to improve nuclear safety and through the regulator’s thorough enforcement activities. The basic concept of nuclear regulations is to protect the public from radiation hazards and to pursue a “better safety performance” as allowed by circumstances. To this end, the Government is devoted to developing a higher level of nuclear safety technology and regulatory system, and to achieving an international level of nuclear safety through participation in the “Nuclear Safety Convention”. In conclusion, the Government reaffirms that the assurance of nuclear safety is the highest duty of the regulatory organization and ensures that such an important role is performed faithfully to secure nuclear safety on behalf of the public.
September 10, 1994
Regu(No. The ensurEnfo
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active Wa
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- 201 -
ansport of R
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- 202 -
Quality Assurance Standards for Radioactive Waste Management Facilities (No. 2012-54, NSSC.waste.010)
This criteria purpose to define the necessary details on QAPs for the LILW disposal facilities and spent fuel interim storage facility. The criteria applies to the site characteristics investigation, design, operation, closure and institutional control of the LILW disposal facilities and site characteristics investigation, design, construction and operation for spent fuel interim storage facility, respectively.
Radiological Protection Criteria for Long-term Safety on Low and Intermediate Level Radioactive Waste Disposal (No. 2012-55, NSSC.waste.011)
The criteria purpose to define the necessary details for preventing radiological risks to human health or the environment in relation to the disposal facilities of the LILW and to establish performance objectives to secure the long-term safety in the case of the permanent disposal of radioactive waste. The performance objectives will indicate that after the closure of a disposal facility, risks caused by radioactive waste disposal which should be within the acceptable level both in the present generation and in future generations, and it will also be applied to review and evaluation of radiological safety.
Guidelines for the Preparation of Site Characteristic Report for Low and Intermediate Level Radioactive Waste Disposal Facilities (No. 2013-20, NSSC.waste.013)
The regulation defines the matters regarding site characteristics report for the LILW disposal facilities. This regulation will be applied to near-surface disposal and rock-cavity disposal for the LILW in the regions of land, seashore, or islands. As these regulations include only minimal technological matters pertaining to each disposal form or method, technological details might be added or excluded in part.
Guidelines for Preparion of Site Characteristics Report for Interim Storage Facilities for Spent Nuclear Fuel (No. 2013-31, NSSC.waste.014)
The regulation aims to define the matters regarding site characteristics report for spent fuel interim storage. This regulation will be applied to wet-type of spent fuel interim storage on surface of ground.
Acceptance Criteria for Spent Nuclear Fuel (No. 2013-32, NSSC.waste.015)
The criteria aim to provide the general requirements for delivering spent fuel as generated from the NPPs to operator of the Away From Reactor (AFR) spent fuel interim storage facility. This criteria purpose to define delivery methods, plan and procedures and other necessary details needed upon consignment of the delivery of
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spent fuel to operator of the AFR spent fuel interim storage facility.
Regulations on the Clearance of Radioactive Waste (No. 2013-33, NSSC.waste.016)
The regulation purposes to define clearance level for deregulation of very low level radioactive waste and procedures, methods, and other necessary details for deregulation application of very low level radioactive waste below the clearance level in the Enforcement Decree of the NSA.
Incineration Criteria for Low and Intermediate Level Radioactive Wastes (No. 2012-60, NSSC.waste.018)
This criteria purpose is to provide technical details for incinerator facilities of the LILW in order to secure the operational safety at the time of incineration treatment of radioactive waste.
Regulations for Manufactures and Periodical Inspection of Packaging for Radioactive Materials (No. 2013-51, NSSC.waste.019)
The regulation purposes to provide technical details for inspection of manufacture/use of radioactive material transport containers, especially standards in respect of the items, methods for inspection by type of transport containers.
Technical Standards for the Structure and Equipment of Radioactive Waste Treatment Facilities (No. 2013-62, NSSC.waste.020)
The criteria stipulate the detailed technical requirements on structure and equipment that must be considered in relation to the design and operation of various treatment facilities of the LILW.
Technical Standards for the Operation, Etc. of Low- and Intermediate-Level Radioactive Waste Disposal Facilities (No. 2013-35, NSSC.waste.021)
The regulation purposes to manage disposal facilities safely, prevent disasters due to disposal facilities, and protect the environment by defining detailed technical standards regarding the management of disposal facilities for the LILW. This regulation will be applied to the management, closure, and institutional control of disposal facilities of the LILW and their safety assessment on normal and abnormal events which are likely occurred during the operation, closure, and institutional control of disposal facilities.
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Guidelines for Preparation of Safety Analysis Report for Low- and Intermediate-Level Radioactive Waste Disposal Facilities (No. 2013-36, NSSC.waste.022)
This guide purposes to define the matters related to the composition of the safety analysis report for the LILW disposal facilities. This guide will be applied to the safety evaluation and accident analysis for the design, construction, and management of the disposal facilities for the LILW and of their accompanying facilities, and for problems anticipated during the institutional control period.
Regulations for the Inspection on Disposal of Low- and Intermediate-Level Radioactive Waste (No. 2012-65, NSSC.waste.023)
The Regulation aims to establish requirements needed to inspect the disposal of the LILW at waste disposal facilities. Operators who wish to undergo disposal inspection must submit inspection application form for each batch of waste to the NSSC up to one month before in which disposal is to be implemented.
Technical Standards for the Radiation Safety Management, etc. of the Transport Vessel for Low- and Intermediate-Level Radioactive Waste (No. 2012-66, NSSC.waste.024)
The regulation purposes to provide technical details for radiation safety management of the LILW transport ships.
Radiation
Standards for Radiation Protection, Etc. (No. 2013-49, NSSC.radiation.001)
The purpose of the standards lies in establishing standards related to radiation protection according to the regulations for radiation protection in the NSA. Especially included is classification of radioactive waste, definition of effluent control limits, and radiological design limits to prevent human and environments from radiation hazards, which applies to the design of the radioactive waste management facilities.
Reactor Facilities
Standard Format and Content of Radiation Environmental Report for Nuclear Power Utilization Facilities (No.2013-03, NSSC.reactor.006)
The regulation purposes to describe the necessary matters regarding items of report, its preparation method and others related to the composition of the radiological environmental report for assessment of the radiological impacts that may occur in the environment due to construction and operation of the nuclear facilities as well as of the draft radiological environmental report for public consultation/hearing of residents
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nearby. This regulation will be applied to the draft radiological environmental report for the NPPs, the LILW disposal facility and spent fuel interim storage facility, and to the radiological environmental report for research reactor with 100kW thermal, and other waste management facilities and Etc.
Regulation on Survey of Radiation Environment and Assessment of Radiological Impact on Environment in Vicinity of Nuclear Power Utilization Facilities (No. 2013-04, NSSC.reactor.007)
The regulation purposes to describe the necessary details regarding the implementation of a survey of radiation environment and assessment of the radiological impacts on the surrounding environment of nuclear facilities which should be carried out by their installers and/or operators.
Regulation on Reporting and Public Announcement of Accidents and Incidents for Nuclear Power Utilization Facilities (No. 2013-50, NSSC.reactor.019)
The regulation purposes to describe the necessary details regarding reporting items, their procedures and impacts assessment on events and accidents of reactor facilities. Especially this regulation will be applied for items of events and/or accidents which should be reported to the NSSC and release the related information to the general public during operation of nuclear facilities.
ReguExpeThe wastedeco ReguFundThe mana ReguThe and LILW NoticSpenThe Engaenganeutr
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- 206 -
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- 207 -
ational Radi
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uclear Facilities
Head
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Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Korea InstituteNuclear Safety
Nuclear Safety aCommission
Nuclear Safety aCommission
Korea Institute Nuclear Safety
Korea Hydro anNuclear Power
Korea Radioact
KEPCO Nuclea
Korea Atomic EResearch Institu
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Korea Institute Nuclear Safety
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KIM, Sung-Il
PARK, Jinyong
EO, Eun-Jin
ONG, Min-Chu
YOO, Song-Jae
YUK, Dae-Sik
LEE, Kwan-Hee
LEE, Youn Keun
LEE, Jeongken
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Director of DProtection &Safety EvaluRadiation SManager
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Editors
orea Institute of uclear Safety
orea Institute of uclear Safety
orea Institute of uclear Safety
orea Institute of uclear Safety
orea Hydro and uclear Power Co
orea Radioactivegency
EPCO Nuclear F
orea Atomic Eneesearch Institute
on BAEK
KIM,
on Waste
LEE B
eral KIM,
rector KIM,
ment SEOL
n & gy
MOO
afety JUNG
rotection y
JUNG
LEE,
LEE,
JEON
JUNG
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BANG
e Waste SEON
Fuel KAN
ergy LEE,
K, Min
, KiTae
Byung Soo
, Kyung-Deok
, Hyung-Joon
L, Jeung Gun
ON, Jei-Kwon
G, Hwanjong
G, Haiyong
, Jungjoon
, Ho Jin
NG, Jae-Hak
G, Hyosook
G, Soo-Il
NG, Ki-Yeoul
NG, Hyun Gyu
, Ki-Won
Date of issue 2014.10.
Issuer LEE, Unchul
Editor Nuclear Safety and Security Commission
Published by Korea Institute of Nuclear Safety
62, Gwahak-ro, Yuseong-gu, Daejeon, Korea 305-338,
Tel: +82-42-868-0296
http://www.kins.re.kr/
ISBN Korean National Report 978-89-93507-26-3 (printed)
Korean National Report 978-89-93507-29-4 (e-book)
English National Report 978-89-93507-28-7 (printed)
English National Report 978-89-93507-27-0 (e-book)
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