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Joint Research Centre the European Commission's
in-house science service
8th International Summer School
on Nuclear Decommissioning and
Waste Management
ISPRA – 14.09.2016
Waste management and
clearance:
JRC approach in
compliance with the
Italian legislation
2
Giovanni Macchi
Clearance Coordinator
European Commission
Joint Research Centre
Nuclear Decommissioning Unit
Via E. Fermi 2749, TP 400
I-21027 Ispra (VA), Italy
+39 0332 78 5218
Waste management and clearance:
JRC approach in compliance with the
Italian legislation
3
1. Definition And Criteria
2. Italian Legislation
3. JRC Situation
4
1. Definition And Criteria
2. Italian Legislation
3. JRC Situation
5
Waste management and clearance:
JRC approach in compliance with the Italian legislation
Definition And Criteria
6
Waste management and clearance:
JRC approach in compliance with the Italian legislation
Definition And Criteria
7
Waste management and clearance:
JRC approach in compliance with the Italian legislation
Definition And Criteria
8
Definition And Criteria
9
Definition And Criteria
10
Definition And Criteria
11
Definition And Criteria
12
Definition And Criteria
13
Definition And Criteria
14
Definition And Criteria
15
Definition And Criteria
16
Definition And Criteria
Clearance is defined as the removal of radioactive materials or radioactive objects within authorized practices from any further regulatory control by the regulatory body“ (IAEA RS-G-1.7)
17
Definition And Criteria
CRITERIA FOR CLEARANCE I.10. The general criteria for clearance are that:
(a) Radiation risks arising from the cleared material are
sufficiently low as not to warrant regulatory control, and there is no appreciable likelihood of occurrence for scenarios that could lead to a failure to meet the general criterion for clearance; or
(b) Continued regulatory control of the material would yield no net benefit, in that no reasonable control measures would achieve a worthwhile return in terms of reduction of individual doses or reduction of health risks.
18
International Regulations – IAEA RS-G-1.7
• Dose for a member of the public in the range of 10 μSv/a
• Single events with low likelihood can be accepted if < 1 mSv/a
effective dose and < 50 mSv/h skin dose
• 1 man Sv/a collective dose
• No mass restriction
• 100% exhaustion of the clearance levels assumed; all applications
• Values are based on several international studies, the lowest
values for every nuclide were chosen to ensure universal
applicability
• Up to the tenfold of the given level, the national regulator may
decide not to apply any regulation (graded approach)
• Application of guide is not mandatory – "may be used"
Definition And Criteria
19
International Regulations – EU
Council Directive 96/29/Euratom on Exemption and clearance
• RP 89 : “Recommended radiological protection criteria for
the recycling of metals from the dismantling of nuclear installations ”, 1998.
•RP 113 : “ Recommended radiological protection criteria for the
clearance of buildings and rubble from the dismantling of nuclear
installations ”, 2000.
•RP 122 part I: “Practical use of the concepts of exemption and clearance
– guidance on general clearance levels for practices”, 2000.
Definition And Criteria
Revision of EU-BSS 96/29/Euratom:
COUNCIL DIRECTIVE 2013/59/EURATOM of 5 December 2013
Harmonisation with International BSS
20
Definition And Criteria
• EU – RP 122 4. GENERAL CLEARANCE LEVELS
Isotopes contribution to 10 μSv/a
𝑐𝑖𝑐𝐿𝑖
𝑛
𝑖=1
≤ 1.0
𝑐𝑖 is the total activity in the structure per unit mass of radionuclide 𝑖(Bq/g), 𝑐𝐿𝑖 is the clearance level of radionuclide 𝑖 (Bq/g), is the number of radionuclide in the mixture. 𝑛
21
1. Definition And Criteria
2. Italian Legislation
3. JRC Situation
22
Italian Legislation
Laws
Ministerial
Decrees
Technical Guidelines
from Control Authority
National Standardisation
Association:UNI, Cei
23
Italian Legislation
Laws
• Act 230/1995 as amended on Implementation of the directives 89/618/Euratom, 90/641/Euratom, 92/3/Euratom and 96/29/Euratom in the field of ionizing radiation. • §30 Specific clauses for clearance of wastes. • §154 Specific clauses for exempt wastes
• A general exemption criterion is in force in Italy, which can also be
used for clearance: – activity concentration ≤ 1 Bq/g, and – half-life < 75 days • If compliance with either of the two is failed, clearance
requires an authorization on a case-by case basis.
24
Regulatory
Sistem (D.L 230 …)
SUBJECTION CLEARANCE < 10µSv/a A posteriori
EXEMPTION: < 75d and < 1 Bq/g A priori
EXCLUSION (cosmic radiation, NORM)
Italian Legislation
Laws
25
Controlled Area
Supervised Area
Free area
Workers Classification
Population CLEARANCE Plant fence
10 μSv/a
< 20 mSv/a < 6 mSv/a
Laws
Italian Legislation
26
Italian Legislation
Ministerial decrees
New Waste classification
(G.U 191 – 19 August 2015)
EW
VSLW
VLLW
LLV
ILW
HLW
27
Italian Legislation
Ministerial decrees
SGRR Authorisation
(D.I 191 – 23 September 2008)
𝑐𝑖𝑐𝐿𝑖
𝑛
𝑖=1
≤ 1.0
28
Italian Legislation
Technical guidelines from Control Authority
Old Waste classification
(Technical Guide 26)
29
Italian Legislation
(UNI 11458-2012) - 1
National Standardisation Association: UNI, Cei
30
Italian Legislation
(UNI 11458-2012) - 2
National Standardisation Association: UNI, Cei
31
1. Definition And Criteria
2. Italian Legislation
3. JRC Situation
32
JRC Situation
Ispra 1
33
JRC Situation
INE-Essor
Ispra 1
34
JRC Situation
Faro
INE-Essor
Ispra 1
35
JRC Situation
Faro
SGRR
INE-Essor
Ispra 1
36
JRC Situation
Faro
SGRR
LMA
INE-Essor
Ispra 1
37
JRC Situation
STRRL
Faro
SGRR
LMA
INE-Essor
Ispra 1
38
JRC Situation
STRRL
Cyclotron
Faro
SGRR
LMA
INE-Essor
Ispra 1
39
JRC Situation
1) Period: 2005 – 2010
2) Six projects: INE, FARO/ECO, ISPRA-1, STRRL, LCSR, RCHL
3) Internationally recognised characterisation approach:
a. Historical site assessment
b. Implementation of calculation methods
c. Structural and radiometric surveys
d. Non-destructive radiological analyses
e. Destructive radiological analyses
f. Data and sample management (MiRadIs,
characterisation sample archives)
Historical plant characterisation
40
INE ISPRA
1 LCSR STRRL FARO RCHL Bioshields
Total in
all
facilities
Number of
measurements
for NDA
Gamma-ray imaging
29 34 66 15 - 1 - 145
HRGS object counting
589 195 151 151 461 550 - 2.097
LRGS object counting
1.381 620 324 208 - 70 - 2.603
LRGS scanning
78 85 77 134 49 1 - 424
Contamination measurement
by smears 737 92 302 136 179 25 - 1.471
Total number of NDA measurements
2.814 1.026 920 644 689 647 - 6.740
Number of
samples for
DA
Metal 48 54 10 7 37 9 - 165
Concrete 33 13 8 17 10 21 6 108
Other material 11 5 6 27 12 10 - 71
Total number of DA samples 92 72 24 51 59 40 6 344
Number of
laboratory
determinations
for DA
Alpha emitters 434 311 101 183 175 189 52 1.445
Beta emitters 805 583 165 332 243 281 174 2.583
Gamma emitters
158 98 38 69 79 93 66 601
Weak gamma and X-ray emitters
308 236 53 133 82 37 72 921
Total number of DA determinations
1.705 1.228 357 717 579 600 364 5.550
Total number of pages in plant
characterisation documentation 7.799 4.315 2.297 2.125 2.817 2.617 257 22.227
Total number of objects
(components, structures) in the
MiRadIs database
9.382 3.340 2.494 1.392 2.714 2.828 - 22.402
JRC Situation
41
MIRADIS Database:
• 1. Physical characterization - structural
survey (22.400 objects)
• 2. Characterization of hazardous materials
• 3. Radiological pre-characterization (470.000 radiometric values)
MiRadIs Structures
WITS Waste Tracking and System Information
JRC Situation
42
JRC Situation
43
𝑐𝑖𝑐𝐿𝑖
𝑛
𝑖=1
≤ 1.0
JRC Situation
2008 2012
𝑐𝑖𝑐𝐿𝑖
𝑛
𝑖=1
≤ 1.0
44
JRC Situation
𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎
𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎
𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎 𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎
𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎
𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎
𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎
𝒄𝒊𝒄𝑳𝒊
𝒏
𝒊=𝟏
≤ 𝟏. 𝟎
45
JRC Situation
46
THANK YOU
FOR YOUR KIND
ATTENTION!
47
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