DESIGN DATA AND SAFETY FEATURES OF COMMERCIAL NUCLEAR POWER PLANT.pdf

7/24/2019 DESIGN DATA AND SAFETY FEATURES OF COMMERCIAL NUCLEAR POWER PLANT.pdf

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DE SIG N DATA A N D SAFETY FEATURES

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COMMERCIAL NUCLEAR POWER PLANTS

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Design Data and Safety Features of Commercial Nuclear Power Plants,

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C o n t r a c t No. W-7405-Eng-26

N u c l e ar S a f e t y I n f o r m a t i o n C e n t e r

DESIGN DATA

AND SAFETY

FEATURES

OF

COMMERCIAL WCLEAR

POWER

PLANTS

VOl. I

Do c k e t

No.

50-3 T hro ugh 50-295

Fred A . He d d le s o n

R e a c t or D i v i s i o n

DECEMBER

1 9 7 3

ORNL-NSIC-55

V O l .

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iii

TABLE OF CONTENTS

PAGE

INDEX BY DOCKET NUMBER........ ... ................................. i v

INDEX BY NUCLEAR POWER PLANT NAME............

.....................

v i

INDEX BY UTILITY

N A M E . . . . . . . . . . . . . . .. . . . . . . . . . . .. . . . . . . . . . . . .. . . . .

v i i i

FOREWORD.......................... ................................ i x

A B S T ~ C T . . . ....................................................... x i

I N T R O D U C T I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

x i

ORGANIZATION OF INFORMATION......... ............................ x i i i

ACCURACY OF DATA.....

...........................................

xv

ACKNOWLEDGEMENT....... xv

GLOSSARY OF T E R M S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

m i

..........................................

DOCKET

50-3

THROUGH

50-295

(SEE

INDICES ABOVE)

..............................................

1-224


6/250

iv

INDEX BY DOCKET NUMBER

PAGE

50-3

50-10

50-29

50-133

50-155

50-206

50-213

50-219

50-220

50-237

50-244

50-245

50-247

50-249

50-250

5 0 - 2 5 1

INDIAN POINT NUCLEAR. UNIT 1 ............................. 1

DRESDEN NUCLEAR POWER STATION. UNIT

1

.................... 8

YANKEE ATOMIC ELECTRIC POWER STATION ..................... 1 5

HUMBOLDT BAY POWER PLANT, UNIT 3

..........................

22

BIG ROCK POINT NUCLEAR PLANT

.............................

29

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 ............ 36

CONNECTICUT YANKEE ATOMIC POWER PLANT .................... 43

OYSTER CREEK NUCLEAR GENERATING STATION...................

50

NINE MILE POINT NUCLEAR STATION. UNIT 1 ................... 57

DRESDEN NUCLEAR POWER STATION. UNITS 2 & 3.................. 6 4

GINNA NUCLEAR POWER PLANT

.................................

7 1

MILLSTONE NUCLEAR POWER STATION. UNIT

1

..................

7 8

INDIAN POINT NUCLEAR GENERATING, UNIT 2

...................

85

DRESDEN NUCLEAR POWER STATION. UNITS 2 & 3

..................

6 4

TURKEY POINT STATION. UNITS 3&4

...........................

9 2

50-254 QUAD-CITIES NUCLEAR POWER STATION. UNITS 1 & 2

..............

99

50-255 PALISADES NUCLEAR POWER STATION

...........................

1 0 6

50-259

BROWNS FERRY NUCLEAR POWER PLANT. UNITS 1.2.&3

............

1 3

50-260

5 0 - 2 6 1

ROBINSON STEAM ELECTRIC PLANT. UNIT 2

.....................

1 2 0

50-263

MONTICELLO NUCLEAR GENERATING PLANT

......................

1 2 7

50-265 QUAD-CITIES NUCLEAR POWER STATION. UNITS 1 & 2

..............

99

50-266

POINT BEACH NUCLEAR PLANT. UNITS

1&2

......................

1 3 4

50-269

OCONEE NUCLEAR STATION. UNITS 1.2.&3

......................

1 4 1

50-2

70

5 0 - 2 7 1

VERMONT YANKEE GENERATING STATION

......................... 1 4 8

50-272

SALEM NUCLEAR GENERATING STATION. UNITS

1 & 2

...............

55

.


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V

50-285

50-286

50-287

50-289

50-293

50-295

50-296

50-301

50-304

50-306

50-311

50-320

50-323

FORT CALHOUN STATION ..................................... 190

INDIAN POINT NUCLEAR GENERATING. UNIT

3

...................

197

OCONEE NUCLEAR STATION. UNITS

1.

2. &3

....................

1 4 1

THREE MILE ISLAND NUCLEAR STATION. UNITS 1 6 2

..............

04

PILGRIM NUCLEAR STATION NO

.

1 ............................ 2 1 1

ZION STATION. UNITS 1&2

...................................

218

BROWNS FERRY NUCLEAR POWER PLANT. UNITS 1 . 2 . &3 ...........113

POINT BEACH NUCLEAR PLANT. UNITS

1 & 2

.....................

134

ZION STATION. UNITS

1 & 2

..................................

218

PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNITS 1 & 2

....... 83

S ALm NUCLEAR GENERATING STATION, UNITS 1 & 2 .............. 55

THREE MILE ISLAND NUCLEAR STATION. UNITS 1 & 2

.............

04

DIABLO CANYON NUCLEAR POWER PLANT. UNITS 1 & 2 ............. 62


8/250

vi

INDEX BY NUCLEAR POWER PLANT NAME

PAGE

BIG ROCK POINT NUCLEAR PLANT, 5 0 - 1 5 5 . ............................. 2 9

BROWNS FERRY NUCLEAR PLANT,

UNITS 1 2 , & 3 , 5 0 - 2 5 9 1 2 6 0 1 2 9 6 . . ................................ 1 1 3

CONNECTICUT YANKEE ATOMIC POWER PLANT,

5 0 - 2 1 3

...........................................................

4 3

UNITS

1

& 2 , 5 0 -2 7 51 3 23 .......................................... 1 6 2

5 0 - 1 0 - ........................................................... 8

2 6 3 , 5 0 - 2 3 7 1 2 4 9 ................................................ 6 4

DIABLO

CANYON

NUCLEAR POWER PLANT,

DRESDEN NUCLEAR POWER STATION, UNIT

1,

DRESDEN NUCLEAR POWER STATION, UNITS

FORT CALHOUN STATION,

50-285....................

..................

1 9 0

ROBERT EMMETT GINNA NUCLEAR POWER

PLANT, 5 0 - 2 4 4 .................................................... 7 1

HUMBOLDT BAY POWER PLANT, UNIT 3 ,

5 0 - 1 3 3 ........................................................... 2 2

INDIAN

POINT NUCLEAR UNIT 1 5 0 - 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

INDIAN POINT NUCLEAR UNIT 2 ,

50-247 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. 8 5

INDIAN POINT NUCLEAR UNIT 3 , 5 0 - 2 8 6

...............................

1 9 7

MILLSTONE NUCLEAR POWER STATION,

UNIT 1

5 0 - 2 4 5

...........................................................

7 8

5 0 - 2 6 3 ........................................................... 1 2 7

UNIT 1 5 0 - 2 2 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7

MONTICELLO NUCLEAR GENERATING PLANT,

NINE MILE POINT NUCLEAR STATION,

OCONEE NUCLEAR STATION, UNITS

1

2 ,

&

3 , 5 0 - 2 6 9 1 2 7 0 1 2 8 7

..............................................

1 4 1

OYSTER CREEK NUCLEAR GENERATING

STATION, 5 0 - 2 1 9 . ................................................. 5 0

PALISADES NUCLEAR POWER STATION,


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vi i

PRAIRIE ISLAND NUCLEAR GENERATING PLANT,

UNITS

1

&

2,

50-282/306

183

..........................................

QUAD-CITIES NUCLEAR POWER STATION, UNITS

1

& 2, 50-254/265 99

UNIT

2 ,

50-261.. . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . ..........

120

................................................

H. B. ROBINSON STEAM ELECTRIC PLANT,

SALE11 NUCLEAR GENERATING STATION, UNITS

1 & 2 , 50-2721311.. .............................................. 155

UNIT

1, 50-206... 36

50-280/28l ....................................................... 176

UNITS 1 &

2, 50-289/320 204

50-250/251 92

SAN ONOFRE NUCLEAR GENERATING STATION,

................................................

SURRY POWER STATION, UNITS 1 & 2 ,

THREE MILE ISLAND NUCLEAR STATION,

..........................................

TURKEY POINT STATION, UNITS 3 & 4 ,

.......................................................

VERMONT YANKEE GENERATING STATION,

50-271 ........................................................... 148

YANKEE ATOMIC ELECTRIC POWER STATION,

50-29 ............................................................

15

ZION STATION, UNITS

1

& 2, 50-295/304

.............................

218


10/250

v i i i

INDEX BY UTILITY NAME

PAGE

BOSTON EDISON COMPANY

......................

. P i l g r i m

..............

2 1 1

CAROLINA POWER AND LIGHT COMPANY

............

o b i n s o n

2 ...........

120

COMMONWEALTH EDISON COMPANY ................. r e s d e n 1 ........... 8

D r e s d e n

2 & 3

......... 6 4

Q u a d - C i t i e s 1 & 2

. . . . . .

99

Z i o n

162

.............

218

CONNECTICUT YANKEE ATOMIC POWER CO .......... o nn . Y a n k e e ......... 4 3

............. i l l s t o n e 1 ......... 78

ONNECTICUT LIGHT

AND

POWER CO

.

HARTFORD ELECTRIC LIGHT COMPANY

CONSUMERS POWER COMPANY ..................... B i g R o c k

P o i n t

....... 29

Pa l i sad es ............

106

In d i an

P o i n t

2

.......

85

I n d i a n

P o i n t 3

.......

1 9 7

1 4 1

FLORIDA POWER AND LIGHT CO

..................

urkey P o i n t

3&4

..... 92

JERSEY CENTRAL POWER AND LIGHT CO ........... y s t e r C r e e k......... 50

METROPOLITAN EDISON COMPANY 1 T h r e e M i l e I s l a n d

JERSEY CENTRAL PWR & LIGHT CO

. #2 ' 1 & 2 ................

204

NIAGARA MOHAWK POWER CORP

...................

i n e M i l e P o i n t 1

...

5 7

NORTHERN STATES POWER COMPANY

............... o n t i c e l l o

...........

1 2 7

P r a i r i e

I s l an d

1 & 2 .. 183

OMAHA PUBLIC POWER DISTRICT................. o r t C a l h o u n ..........

190

P A C I F I C

GAS

AND ELECTRIC CO

.................

i a b l o C a n y o n 1 & 2..... 162

H u m b o l d t B a y ..........

2 2

PHILADELPHIA ELECTRIC CO ....................

Peach

B o t t o m 2&3 .....

169

P U B L I C S E R V I C E E L E C T R I C & GAS CO

............

a l e m

1 & 2

............

155

ROCHESTER GAS & ELECTRIC COMPANY

............

i n n a . . . . . . . . . . . . . . . . . 7 1

................ an

O n o f r e

1 ......... 36

OUTHERN CALIFORNIA EDISON

SAN DIEGO

GAS

& ELECTRIC CO .

CONSOLIDATED EDISON CO . OF NY. IN C .......... ndian P o i n t 1 ...... 1

DUKE POWER COMPANY .......................... O c o n e e 1 . 2 . &3 .......


11/250

ix

FOREWORD

The N u c le a r S a f e t y I n f o r m a t i o n C e n t e r , e s t a b l i s h e d i n M arc h

1 9 6 3

a t

t h e Oak R id g e N a t i o n a l L a b o r a t o r y u n d e r t h e s p o n s o r s h i p of t h e U . S .

At omi c Ene r gy Commi s s i on , i s a f o c a l p o i n t f o r t h e c o l l e c t i o n , s t o r a g e ,

e v a l u a t i o n , a n d d i s s e m i n a t i o n o f n u c l e a r s a f e t y i n f o r m a t io n . A s y s t e m

of ke ywor ds i s u s ed t o i n d ex t h e i n f o r m a t i o n c a t a l o g e d by t h e C e n t e r .

The

t i t l e ,

a u t h o r , i n s t a l l a t i o n , a b s t r a c t , a n d k ey wo rd s f o r e ac h docu-

m e n t r e v i e w e d are r e c o r d e d

a t

t h e c e n t r a l c om nu te r f a c i l i t y i n Oak

R i d ge . T he r e f e r e n c e s a r e c a t a l o g e d a c c o r d i n g t o t h e f o l l o w i n g cate-

g o r i e s

:

1.

2 .

3 .

4 .

5.

6 .

7 .

8 .

9 .

10.

11.

12.

13.

1 4 .

15.

16.

17.

18.

19.

20.

G e n e ra l S a f e t y C r i t e r i a

S i t i n g o f Nu c le a r F a c i l i t i e s

T r a n s p o r t a t i o n a nd H a n dl in g o f R a d i o a c t i v e M a t e r i a l s

A e ro s p ac e S a f e t y

Heat T r a n s f e r a nd T h er ma l T r a n s i e n t s

R e a c t o r T r a n s i e n t s , K i n e t i c s , a n d S t a b i l i t y

F i s s i o n P r o d u c t Release , T r a n s p o r t , a n d R em ov al

S o u r c e s o f E n e r g y Release U n de r A c c i d e n t C o n d i t i o n s

N u c l ea r I n s t r u m e n t a t i o n , C o n t r o l , a n d S a f e t y Sy st em s

E l e c t r i c a l Power Sys tems

C o n t a i n m e n t o f N uc le a r F a c i l i t i e s

P l a n t S a f e t y F e a t u re s - R e a c t o r

P l a n t S a f e t y F e a t u re s - N o n r e a c t o r

R a d i o n u c l i d e Release a n d Mo ve me nt i n t h e E n v i r o n m e n t

E n v i r o n m e n t a l S u r v e y s, M o n i t o r i n g , a n d R a d i a t i o n Ex p o su r e

of Man

M e t e o r o l o g i c a l C o n s i d e r a t i o n s

O p e r a t i o n a l S a f e t y a n d E x p e r i e n ce

S a f e t y A n a l y s i s a nd D e si g n R e p o r t s

R a d i a t i o n D os e t o Man f ro m R a d i o a c t i v i t y Release t o t h e

E f f e c t s o f T he rm al M o d i f i c a t i o n s o n E c o l o g i c a l S y st em s

E n v i r o n m e n t


12/250

X

( 2 )

make r e t r o s p e c t i v e s e a r c h e s o f t h e s t o r e d r e f e r e n c e s , a nd ( 3 ) d i s t r i -

b u t e s c o p e an d p r o g r e s s i n f o r m a t i o n o n R&D c o n t r a c t s f r om t h e P r og ra m an d

P r o j e c t I n f o r m a t i on F i l e (P PIF )

.

Services o f t h e N S I C

a re

a v a i l a b l e t o g ov er nm en t a g e n c i e s , r e s e a r c h

and e d u c a t i o n a l i n s t i t u t i o n s , a nd t h e n u c le a r

i n d u s t r y on

a

p a r t i a l c o s t

r e c o v e ry b a s i s d e s i g n ed

t o r e g a i n

a

p o r t i o n o f t h e e xp e ns e a s s o c i a t e d

w i t h d i s s e m i n a t i n g t h e i n f or m a t io n

t o

t h e u s e r .

A m i ni m al i n q u i r y re-

s p o n s e i s a v a i l a b l e f r e e .

N S I C

r e p o r t s ( i . e . , t h o s e w i t h t h e O W- NS IC

n u m b e r s ) may b e p u r c h a s e d

f ro m t h e N a t i o n a l T e c h n i c a l I n f o r m a t i o n S e r v i c e

( s e e i n s i d e f r o n t c o v e r ) w h i l e d o c u m e n ts i n d e x e d by NSIC may b e e x am i ne d

a t

t h e C e n te r by q u a l i f i e d p e r s o nn e l . I n q u i r i e s c o n c e r n in g t h e c a p a b i l -

i t i e s a n d o p e r a t i o n of t h e C e n t e r may b e a d d r e s s e d t o :

J . R . B uc ha na n, A s s i s t a n t D i r e c t o r

N u c le a r S a f e t y I n f o rm a t i o n C e n t e r

P o s t O f f i c e B ox Y

Oak R i d g e N a t i o n a l L a b o r a t o r y

O a k R i d g e , T e n n e s s e e 3 7 8 3 0

Te l e pho ne 615- 483- 8611, Ex t . 3 -7253

FTS number i s 615-483-7253


13/250

xi

D E S I G N DATA

AND

SAFETY FEATURES

OF

COMMERCIAL

NUCLEAR

POWER PLANTS

V O l . I

Do cke t No. 50-3 T hrou gh 50-295

ABSTRACT

D es ig n d a t a , s a f e t y f e a t u r e s , a nd

s i t e

c h a r a c t e r i s t i c s

a r e

s um m ar iz e d f o r t h i r t y - t w o c o m m er c ia l n u c l e a r po we r p l a n t s i n t h e

i r n i t e d S t a t e s . S i x p a g e s of d a t a a r e p r e s e n t e d f o r e a ch p l a n t

c o n s i s t i n g of T h e r m a l- H y d ra u l ic a nd N u c l e a r F a c t o r s , C o n t ai n m e n t

F e a t u r e s , E me rg en cy C o r e C o o l i n g S y s t e m s,

S i t e

F e a t u r e s , C i r c u l a -

t i n g Water Sys t e m Data, a n d M i s c e l l a n e o u s F a c t o r s . An a e r i a l p e r -

s p e c t i v e

i s

a l s o p r e s e n t e d f o r e a c h p l a n t . T ho se c ov e r ed i n t h i s

volume are I n d i a n P o i n t 81, Doc ke t Number 50-3 , and a l l s u b s e q u e n t

p l a n t s f i n i s h i n g w i t h Z i o n , D o c k e t Number 5 0- 29 5.

INTRODUCTION

The d a t a s u mm ar ie s f o r t h i s r e p o r t

were

t a k e n f r om t h e P r e l i m i n a r y

S a f e t y A n a l y s i s R e p o r t s (P SA R), F i n a l S a f e t y A n a l y s i s R e p o r t s (FS AR ), a n d

t h e E n v i r on m e n ta l R e p o r t g e n e r a t e d f o r t h e U . S . Atomic Energy Commiss ion

l i c e n s i n g a u t h o r i t i e s by a p p l i c a n t s w i s h i ng t o b u i l d a nd o p e r a t e n u c le a r

power p l a n t s . T h es e r e p o r t s c o n s i s t o f

800

t o 2000 p a g e s o f i n f o r m a t i o n

w hic h d e s c r i b e t h e r e a c t o r , t h e r e a c t o r s i t e , t h e po we r g e n e r a t i o n s y s te m ,

a u x i l i a r i e s , a nd o t h e r a s p e c t s of i m po r ta n ce i n t h e s a f e t y as s es s me n t

of

r e a c t o r d e s i g n , c o n s t r u c t i o n , a nd o p e r a t i o n . U n l es s a p e r s o n i s f a m i l i a r

w i t h t h e o r g a n i z a t i o n of t h e r e p o r t s , f i n d i n g s p e c i f i c i n fo r ma t io n t h e r e i n

c an b e v e r y

t i m e

c o ns u mi n g. E ve n w he n t h e o r g a n i z a t i o n

i s

u n d e r s t o o d ,

i t

c a n s t i l l b e d i f f i c u l t t o f i n d d a t a be c a us e of v a r i a t i o n s i n t h e s t y l e of

t h e r e p o r t s . T h e r e f o r e , t h i s c o m p i l a t i o n of summary d a t a sh o u l d b e us e-

f u l .


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x i i

111.

I V

.

V .

V I .

V I I .

V I I I .

IX

X.

X I .

X I I .

X I I I .

X I V .

xv

.

X V I

.

X V I I .

Design of Structures, Components, Equipment and Systems

Reactor

Reactor Coolant System

Enginee red S a fe t y Fea tur es

I n s

r

umen

t

at

i

n and Con

t r

o1s

E l e c t r i c Power

A u x i l i a r y

Sys e m s

S t e a m

and Power Conversion System

Radioac t ive Waste Management

Ra d i a t i o n P r o t e c t i o n

Conduct of Opera t ions

I n i t i a l T e s t s and Opera t ion

S a f e t y A n a ly s i s

T e c h n i c a l S p e c i f i c a t i o n s

Qua l i ty Assurance

I n 1967, t h e Advisory Committee on Reac tor Sa fe ty (ACRS) re qu es te d

t h a t t h e Nu c le a r S a f e t y I n f or m a ti o n Ce n t e r c om p il e d e s i g n d a t a o n l i g h t -

water power r e a c t o r s i n

a

c o n ci s e t a b u l a r f o rm a t f o r u s e by t h e i r

C o m m i t -

t e e . S i n c e t h a t time, t a b l es have been prepa red fo r each power re ac to r

and made av a i l ab le on

a

l im i te d d i s t r i b u t i o n b a s i s

t o ACRS, severa l USAEC

Headquarters Of f i ce s, and th e NSIC st a f f . The da ta summaries, which con-

t a i n a b o u t 1 5 0 of

t h e m os t i m p o rt a nt r e a c t o r f a c t s , h av e pr ov en t o b e

q u i t e u s e f u l t o t h e s e g ro up s

and numerous re qu es t s have been rece iv ed f o r

summaries f rom o th e r o rg an iz a t io ns th a t became aware of t h e i r e x i s t e n c e .

Consequent ly , a d e c i s i o n w a s made t o i s su e t h e sum ma ri es i n r e p o r t f o r m

s o

t h a t they would become more wide ly av ai la b le . Volume I1 w a s publ i shed

i n January 1972 cover ing commerica l power re ac to rs w i th d ocket numbers

la rg er t han and in clu din g 50-296 (Browns Fe rry No.

3 ) .

Volume

I ,

t h i s

p u b l i c a t i o n ,

w i l l

cover power re ac to rs up t o and in c lu d in g docke t number

50-295 (Zion S ta t i on ) . In th e ind ex by seq ue nt i a l docke t number, some


15/250

x i i i

Organ iza t ion of In fo rmat ion

Reactor sunimaries appear se qu en t i al ly ac cor din g t o docket number.

Some general information such as name, s i z e , l o c a t i on , u t i l i t y ,

e t c .

i s

l i s t e d a t t h e t o p of t h e f i r s t p ag e , fo l l o wed b y i nfo rm a t ion o rg ani zed

as

A.

B.

C .

D .

E .

F.

G .

Eollows :

Thermal-Hydraulic

Data

-T ab u l a t i o n s of d a t a v a lu es on t h e

thermal-

h y d r a u l i c d e s i g n c h a r a c t e r i s t i c s

of

t h e r e a c t o r c o r e and c o o l a n t

systems.

Nuclear Data - T ab u la t i o n s o f d a t a v a lu es on n u c l ea r a s p ec t s o f t h e

r e a c t o r c o r e .

Safety-Related Design C r i t e r i a - L i s t i n g of d a t a on e x c l u si o n d i s -

tanc e , popu la t ions , des ign wind speed ,

se ismic

d es ig n , e t c .

E n ginee red Sa fe ty Fea tu r e s

-Da ta

on con ta inment des ign va l ues , con-

ta inment sys tem des cr ip t ion s , emergency core coo l ing sys tems .

Other Safe ty -Rela ted Fea tu r es - D e s c r ip t i on s of a u x i l i a r y s a f e t y

f e a t u r e s s u c h as l ea k de te c t i on , long- te rm emergency coo l ing , f low

r e s t r i c t o r s , f a i l e d f u e l d e t e c t i o n , emergency power,

e t c .

Genera l - Other impor tan t in fo rmat ion such as

s i t e

f e a t u r e s , e m e r -

gency p la ns , env i ronmenta l moni to r ing , radwas te t rea tment ,

waste

h e a t

system, e t c .

S i t e Data

- Information on

s i t e

t o p o g rap h y , p o p u l a t i o n , ev a lu a t i o n s ,

co o l i n g

w a t e r

s o u r c e , c i r c u l a t i o n

r a t e ,

coo l ing towers , e t c .

The seven th page of each re po rt i s a n a e r i a l p e r s p ec t i v e s k e t c h o f

t h e p l a n t .

Parameters are r e l a t e d t o r a t e d power o u t p ut f o r

a

s i n g l e u n i t un-

Fo r i n s t an ce , i n

a

case

w he re t h e r e a c t o r r e p o r te s s o th e rwi s e n o t ed .

co v e r s two o r t h r ee r ea c to r s of t h e

same

r a t i n g a t one s i t e , a l l d a t a

v a lu es g iv en w i l l b e f o r o ne u n i t .

d e s c r i p t i o n o f t h e r e a c t o r a n d s i t e fea tu res . The t e r m s a n d f e a t u r e s

Aer ia l p e r s p e c t i v e p r e s e n t s

a

g r a p h i c


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xiv

LEGEND

-

Parameters re fe r t o each s in gle re ac to r un i t except as noted.

3783 popula t ion in

a 5

mile

rad ius

, ,oo A C R E S

1100

acres

i n t h e

property owned by

ilI LLY

PaoPaRw

L I N E the utility

Boundary lines

of the proper ty

MOUNTAINOUS

,Normal

water

l e v e l

//"ailroad (Highways /::;; o r

~

&>Wooded Area

Landesign se io n s

W O O D E D

IN

DUST K I AL

' ooling \Reactor 6 \\Condenser Tempera ture lowi s end

Tower Turbine

buildings


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w

Accuracy of

Data

A l l i n fo r m at i on p r e s e n t e d i n t h i s p u b l i c a t i o n h a s b e en t a ke n f ro m

th e P re l im in a ry o r F in a l Sa fe ty An a ly s i s Rep o r t s , t h e ap p l i ca n t ' s E nv i-

ro n m en ta l Rep o r t , o r t h e A EC Environmental Impact Statement .

I n

some

c a s e s , a da ta v al ue may be pre sen ted which has changed or i s i n v a l i d

fo r some o ther reason .

If v a lu es a re found which a r e n o t c o r r e c t , N S I C would l i k e t o b e

informed

.

Acknowledgement

The con t r ibu t ion o f

D r .

Car lo s

B e l l ,

fo rmer ly o f

ORNL

but now with

t h e U n i v e r s i ty of North Caro l ina

a t

C h a r l o t t e , i n co mp il in g t h e o r i g i n a l

d a t a c o l l e c t i o n s f o r many of t h e r e a c t o r s i n t h i s volume

i s

g r a t e f u l l y

acknowledged.

Thanks a r e a l s o du e t o t h e f o l l ow i n g u t i l i t y p e r s on n e l who c o n t r i -

b u te d d a t a an d u pd at ed t h e c om p i la t i on s f o r t h e i r p a r t i c u l a r p l a n t :

James E . Fer l an d , M i l l s t o n e

C . J .

Hartman, Big Rock Point

Char les E .

P l a t t ,

Ginna

L.

0 .

Mayer, Monticel lo

He rb er t Au ti o, Yankee Rowe

Arthur W. Flynn , Ind i an Po in t ill

B . B . Stephenson, Quad-Cit ies

Alber t Bur t , Nine

M i l e

P o i n t

W. P. Worden, Dresden

Ivan

R .

Fin f ro ck ,

J r . ,

Oyster Creek

Pa ul Matthew, Humbolt Bay


18/250

GLOSSARY OF TERMS

The fo l lowing terms a n d a b b r e v i a t i o n s are used i n the da ta summaries

i n t h i s r e p o r t . T hi s g l os s ar y

i s

p r ov i de d t o

a s s i s t

t h e u s e r i n u nd er -

s t a n d i n g t h e c o n t e x t i n w hic h t h e

terms

are a p p l i e d and t o i d e n t i f y t h e

a b b r e v i a t i o n s .

--E - A r c h i t e c t - En g i n e e r f o r t h e p l a n t .

s u l t a n t s t o t h e u t i l i t y who do t h e i r own de s i g n an d d r a f t i n g .

Somet imes t he f i rm serves as con-

Accumulato r Tanks -Tan ks th a t co n t a i n bor a te d

w a t e r

under p ressure (usu-

a l l y a bo ut 600 p s i g ) f o r i n j e c t i o n i n t o t h e p ri ma ry s ys te m i n t h e e v e n t of

a

l o s s of co o l i n g acc id e n t . When co o l a n t sy s tem p re s s u r e d ro p s t o t an k

p res s u re , ch eck

valves

open al lowing water f l o w t h a t w i l l f l o o d t h e c o r e .

Act ive

Eieat

T ran s fe r Su r f Area - T h e s u r f a c e a rea of

a l l

f u e l r o d s , mea-

s u r ed on t h e a c t i v e f u e l - p o r t i o n of t h e r o d s .

Auto-Depressurizat ion System

-

The s ys te m t h a t u s e s p r e s s u r e r e l i e f

valves

t o v en t

steam t o pu r p os e l y lo we r r e a c t o r p r e s s u r e s o o t h e r c o r e c o o l i n g

sys tems can opera te .

Average Discha rge Exposure, MWD/ton -Av era ge burnup of f u e l upon removal

from s e r v i c e , expressed i n megawat t days per metr ic t o n of f u e l .

Avg Fi lm Coeff -An average over t h e

a c t i v e

c o r e of t h e c o n v ec t i ve f i l m

h e a t - t r a n s f e r c o e f f i c i e n t , h , d e f i ne d f ro m

Q/AAtlm E h

where

Q i s

t h e h ea t r emoved p e r u n i t

t i m e

from f u e l s u r f a c e

area A ,

and

A t l m i s th e log-mean tempera tu re d i f f e r en ce be tween th e coo lan t and t h e

s u r f a c e .

Avg F i lm Di f f -T h e av e rag e d i f f e re n c e b etween t h e l o ca l co o l an t b u lk

mean t e m p er a t ur e a nd t h e l o c a l f u e l c l a d s u r f a c e t e m p e r a tu r e .

Avg Power Den si ty -T he power gene rate d i n the

a c t i v e

co re d iv id ed by t h e

co re volume.

Average Power Range Monitor

(APRM) -

S e l e c t e d a m p l i f i e r s f r om t h e L o c a l

Power Range M on it or in g (LPRM) sys te m are a ve ra ge d i n t h e APRM.


19/250

x v i i

Burnable Poison - Neutron absorbing

mater ia ls

of r e l a t i v e l y h i g h m ic ro -

s c o p i c a b s o r p t i o n c r o s s s e c t i o n w hi ch

are

co n v er t ed t o l ow ab s o rp t i o n

iso to pe s by neu t ron ab sor p t io n and which

a r e

i n co r p or a te d i n t o r e a c t o r s

t o c o mp en sa te f o r p a r t o r a l l

of t h e r e a c t i v i t y d e c r e a s e t h a t w ould

o t h er w i s e r e s u l t f ro m f u e l e xp os ur e.

Chemical Shim - Supplementary c on t r o l o f

t h e c o r e r e a c t i v i t y by t h e u se of

chemical poisons (such

as

b o r i c a c i d ) i n t h e c o ol a n t.

C le an - T h e r e a c t o r a n d / or f u e l e le m e nt s are s a i d t o b e c l e a n if f u e l

e le-

ments a r e non rad ioa c t i ve and uncon taminated by th e p roducts o f nuc lea r re -

a c t i o n .

Closed-Loop Cooling - System where cool ing towers , co ol in g ponds, e tc .

a r e

u se d f o r c o o l i n g w i t h

a l l

he at removed by th e tow ers , e t c .

Water

i s

re -

c i r c u l a t e d i n t h e c l os e d l o op .

C i r c u l a t i n g Water System - System which provides cool ing

w a t e r

t o t h e m ain

condensers .

Cold

- A t

ambient temperature.

Containment Atmospheric Control System - A s ys te m u se d t o i n j e c t n i t r o g e n

i n t o c on ta in me nt f o r i n e r t i n g . O th er a s p e c t s of a tm os ph er ic c o n t r o l l i s t e d

as a p p l i c a b l e .

Containment Constructor - The c o n t r a c t i n g f i r m w hic h e r e c t s o r f a b r i c a t e s

th e p r im ary co nt a in m en t s t ru c t u r e . In most cases, t h e a c t u a l c o n t r a c t o r ' s

name

i s

n o t a v a i l a b l e . I n t h e s e cases, t h e r e s p o n s i b l e p a r t y s uc h as t h e

u t i l i t y o r

A-E

w i l l be g iven .

Containment Cooling System - Sp ray co o l i n g s y s t em f o r r ed u c in g d ry we l l

p r e s s u r e f o ll ow i ng l o s s of c o ol a nt ; o r f a n c o i l c o o l i ng u n i t s t h a t re-

c i r c u l a t e t h e

a i r .

Conta inment I so la t i on Sys tem - A s y st em th a t p ro v id e s t h e m etho d f o r

sea l -

ing a l l open ings i n th e con tainment sys tem. Each pe ne t r a t io n has two i so -

l a t i o n v a l v e s , o ne on t h e i n s i d e and on e

on

t h e o u t s i d e

o f

the p r imary

containment w a l l . I n

case

of an a c c i d e n t , t h e i s o l a t i o n v a l v e s c l o s e

automat i c a11y .

Control Rod - A de vi ce made of neut ron abso rbin g mate r i a l cap ab l e

of

be in g moved i n t o or o ut of t h e c o r e t o r e g u l a t e p ow er.


20/250

x v i i i

Contro l-Rod Veloci ty

L i m i t e r - An

i n t e g r a l p a r t o f

a

c o n t r o l r o d w hich

l i m i t s

t h e f r e e - f a l l v e l o c i t y of

a

c o n t r o l r od .

Co nt ro l Rod Worth Minimizer -E le c tr on ic computing devi ce which

i s

used

t o m on it or t h e c o n t r o l r od p a t t e r n i n t h e r e a c t o r c o re . I n t e r l o c k s

a r e

provided which prevent

th e wi thd rawal o f a c o n t r o l r od w i t h a worth

a bo ve t h e e s t a b l i s h e d v a l u e .

Core Average Void With in Assembly -T he perc en t of vo i ds i n th e coo l an t

w i t h i n

a

fue l as sembly .

Core Reflooding System

-

High f l ow s y st em t o r a p i d l y f l o o d t h e r e a c t o r

c o r e f o ll o w in g l o s s o f c o o l a n t .

Core Spray System

- A

water s ys te m, a c t i v a t e d i n t h e event of l o s s of

c o r e c o o l i n g , w h ic h s p r a y s

water

on t h e t o p o f t h e c o r e t o rem ove r e a c t o r

c o r e d ec a y h e a t .

C r i t i c a l

Heat F l ux - T h e h e a t f l u x

a t

w hich t r a n s i t i o n f i l m b o i l i n g

s t a r t s

t o r e p l a c e n u c l e a t e b o i l i n g.

s u r f a c e h e a t t r a n s f e r c o e f f i c i e n t .

I t i s

c h a r a c t e r i z e d by

an

a b r u p t c ha ng e i n

Cu r t a in Worth - T h e r e a c t i v i t y w o r th of t h e p oi s on c u r t a i n .

Design Basis Ear thquake

-

That ea r thquake which p roduces t he v ib ra to ry

g round mo t ion fo r which th ose f ea tu re s of th e p la n t nec essa ry to shu t down

t h e r e a c t o r a nd m a i n t a in t h e p l a n t i n

a

s a f e c o n d i t i o n wi t h ou t undue r i s k

t o t h e h e a l t h a nd s a f e t y of t h e p u b l i c

are

d e si g ne d t o r e m ai n f u n c t i o n a l .

Design

C r i t e r i a

- A l i s t

of requi reme nts of th e

U.S .

Atomic Energy Commis-

s i o n t h a t g o v e r n r e a c t o r d e s i g n .

D i s c ha r g e S t r u c tu r e - T h e m ea ns of d i s c h a r g in g

w a t e r

i n t o

the l a ke ,

r ive r ,

ocean, o r c oo l i ng pond.

I t

c a n b e v e r y s im p le s u c h

as

a

s h o r t c a n a l r u n-

n in g i n t o t h e

w a t e r

body, or

i t

can be

a

c om plex d i f f u s e r s ys te m t h a t d i s -

p e r s e s t h e

water

throu gh many openings o r j e t s .

Docket

No.

-T he number ass ig ned by th e

AEC

Div is io n of Reac to r L icens ing

t o

a

p a r t i c u l a r r e a c t o r .

D op pler Co e f f i c i e n t - T h e r e a c t i v i t y c ha ng e d u e t o D op ple r b r o ad e n in g of

n8U

r e so n a nc e a b s o r p t i o n c r o s s s e c t i o n p e r d e g r e e

F

change

i n

t empera tu re .

DNBR,

Nominal

-

Depar tu re f rom Nuclea te Bo i l in g Ra t io , th e minimum va lu e

of t h e r a t i o of h e a t f l u x r e q u i r e d f o r

DNB as

c a l c u l a t e d f ro m th e W e st in g-


21/250

x i x

E ff F lo wra t e f o r

H e a t

T ran s fe r - T ha t p o r t i o n o f t h e c o o l a n t fl o w t h a t

p a s s e s d i r e c t l y t hr ou gh t h e a c t i v e c o r e f o r c o o l i n g t h e f u e l e le m en ts .

Emergency Power -U su al ly supp l ied by d ie se l -ge ner a to r se t s i f o f f - s i t e

power supply i s l o s t .

en g inee red s a fe ty f e a t u r e s an d o th e r n ecess a ry eq u ip m en t.

Emergency a l t e rn a t i n g cu r r en t i s a v a i la b l e f o r

Engineered Sa fe ty Fe at ur es (ESF) - S p e c i a l s y st em s d e s ig n ed t o o p e r a t e

i n

a

n u c l ea r p o wer p l an t s o

as

t o p r e ve n t o r m i t i g a t e t h e c o n se qu e nc e s

of a n a c c i d e n t .

co nt a in m ent s p r ay s , f i l t e r s y st em s , emerg en cy co r e co o l i n g s y st em s , and

t h e l i k e .

E n gin ee red Sa fe ty Fea tu r e s i n c lu d e co n ta inm en t

vesse l s ,

Environmental Monitoring - Co l l ec t io n and an a l ys i s of samples o f t he en-

v i r o n m e n t ( a i r , w a t e r , s o i l , a q u a t ic l i f e ,

t e r r e s t r i a l ,

e t c . ) t o e v al u at e

e f f e c t s t h a t might r e s u l t as

a

consequence of p la n t ope ra t ion .

E v ap o ra t i v e Loss - The l o s s of water f rom th e coo l ing tower t h a t evapo-

r a t e s i n t o t h e c o o li n g

a i r t h a t p a s s e s t h ro u gh t h e co o l i n g t ower. T h i s

w a t e r i s con t inuous ly rep lac ed by th e makeup water system.

Exclus ion Dis tance - The d i s t a n c e f ro m t h e c e n t e r l i n e of t h e r e a c t o r t o

th e n ea re s t ex c lu s io n f en ce b o u n d a ry .

F lo w Res t r i c t o r

- A s t a t i c

d e v i ce p l ac e d i n a

steam

o r water l i n e f o r t he

purpose of r e s t r i c t i n g th e blowdown

r a t e

i n t h e e v e n t of

a

m a j o r l i n e

break .

The d e v i c e a f f o r d s p r o t e c t i o n f o r t h e c o r e , r e du ce d l o a d on t h e

containment system,

a n d a d d i t i o n a l

t i m e

f o r t h e i n i t i a t i o n of t h e

emer-

gency systems.

Fuel Assembly -Assembly o f f u e l ro ds , sp ac er s , and re la te d hardware .

Fuel Channel - The long square tube o r box enc lo s in g the f u e l assembly and

prov id ing a coo lan t f low pa th th rough th e assembly .

Fuel Element -

See

Fuel Assembly.

Fu e l Rods -Ass emb ly of fu e l p e l l e t s , f u e l c l ad d in g , an d r e l a t e d h a rd ware

we ld ed i n to

a

s e a l e d u n i t .

Fue l Rod Cl ad di ng - The m a t e r i a l e n c l o s i n g t h e U O 2 f u e l p e l l e t s .

Ful l Power X e and Sm - The equ i l ib r iu m conce n t r a t i ons of th e Xenon and

Samarium p o i s o n s p r e s e n t a t f u l l pow er.


22/250

xx

High Pr es su re Coolan t - In jec t io n Sys tem - High pressure pumps, valves , pip-

i n g , e t c . , used t o p rov ide emergency co re co o l in g i n t h e e v en t of f a i l u r e

of

a

small

p r oc e ss l i n e .

-

ot

- A t

t em p era tu re s co r res p o nd in g t o f u l l power

o p e r a t i o n .

Hydrogen Recombiner - Equipment t h a t combines f r e e oxygen and f r e e hydrogen

to p roduce

w a t e r .

The purpose i s t o e l i m i n a t e f r e e h yd ro ge n f ro m t h e g as -

eous systems.

I n t a k e S t r u c t u r e - The s t r u c t u r e t h a t ho us es c i r c u l a t i n g pumps, t r a v e l i n g

s c r een s , b a r s c r een s , an d o th e r d ev i ces us ed i n m oving

water

f rom the

water

s o u rce t o t h e p l an t . In some

cases,

t h e i n t a k e s t r u c t u r e w i l l i n c l u d e t h e

p i pe s t h a t r u n o u t i n t o t h e water body an d t h e r em ot e s t r u c t u r e f o r i n t a k e .

I s o l a t i o n Co ol ing Sys tem -Hig h p re s s u r e sy s tem fo r r e j e c t i o n of co r e decay

h e a t when t h e r ea c to r

i s

i s o l a t e d fr om t h e main condenser.

e f f - T h e e f f e c t i v e m u l t i p l i c a t i o n c o ns t a n t of t h e c o r e .

-

-

OCA - L o s s of c o o l a n t a c c i d e n t .

Loc al Power Range Mo ni to r (LPRM) - In -core ion chambers f o r monito r ing lo -

c a l n eu tr on f l u x i n t h e r e a c t o r c or e .

Low-Head S af et y I n j e c t i o n System - See Low-Pressure Coolant In je ct io n Sys-

t e m .

Low-Pressure Coolant In je ct io n System

- A

sys tem of pumps,

valves ,

p i p i n g ,

e t c . , t h a t pumps q u a n t i t i e s of

water

i n t o t h e c o ol a nt s ys te m t o r e f l o o d t h e

co re a f t e r blowdown.

Low Popula t ion Zone Dis tan ce -T he ra d i us t h a t c i rcumscr ib es an area

imme-

d i a t e l y s ur r o un d in g t h e e x c l u s i o n

area

w hich c on t a i n s r e s i d e n t s , t h e t o t a l

number and d e ns it y of which a re s uc h t h a t t h e r e i s a r e a s o n a b l e p r o b a b i l i t y

t h a t a p p r o p r i a t e p r o t e c t i v e m ea su re s c ou ld b e t a ke n i n t h e i r b eh a lf i n t h e

e v e nt of s e r i o u s a c c i d e n t .

MCHFR - See Xinimum C r i t i c a l Heat F l u x R a t i o .

E

Metr ic t on of uranium.

One metr ic t o n = 1000 kg

=

2205 l b .

-WD - Energy i n megawatt-days.


23/250

x x i

M e t r o p o l i s - T h e n e a r e s t c i t y to t h e p la n t t h a t i s c l a s s i f i e d

as

a

U.S.

c i t y w i t h S t a n da r d M e tr o p o l i t an

S t a t i s t i c a l

Areas

as

compiled from the

Bureau

of

th e Census by the World Almanac. Pop ula t io n f i gu r es

a r e

t h e

1 970 t o t a l m e t r o p o l i t a n

area

census.

Minimum

C r i t i c a l

Heat

F l u x R at io (MCHFR) - T h e smal les t r a t i o o f

c r i t i c a l

h e a t f l u x d iv i d ed by t h e l o c a l h ea t f l u x e x i s t i n g i n t h e r e a c t o r c or e

a t

any p o in t i n t i m e .

Modera tor Coef f i c i en t -

A

combina t ion of modera tor vo id c oe f f i c i e n t and

m o d e r a t o r t e m p e r a t u r e c o e f f i c i e n t .

M o de ra to r P r e s s u r e Co e f f i c i e n t - T h e c ha ng e

i n

c o re r e a c t i v i t y p er u n i t

change

i n

modera tor p ressure .

Modera tor Tempera ture Coef f i c i en t - The ch an ge i n c o r e r e a c t i v i t y l e v e l

f o r a u n i t t e m p er a t ur e c ha ng e i n t h e m o d er a to r .

M od er ato r Void C o e f f i c i e n t - T h e c ha ng e i n t h e c o r e r e a c t i v i t y l e v e l f o r

a u n i t c h an ge i n mo d er a to r v o id c o n t e n t .

NSS

Vendor - S u p p l i e r of t h e n u c l e a r

steam

supply system.

Normal Level -Normal pool e le va t i on i n mean

sea l e v e l

(MSL) measurement

of th e body of co ol in g

water.

Once Through - The c oo l ing cy c le where

water i s

removed from t h e n e a r b y

w a t e r sou rce , pumped th rough th e condense r fo r co o l in g and then d i scha rg ed

b ack i n t o t h e

r i v e r ,

l a k e , o r o c e a n .

Open-Cycle Coo l i ng - The system t h a t uses

water

i n t h e c i r c u l a t i n g s ys te m

f o r once- through coo l ing .

Water i s

t a k e n f ro m t h e r i v e r , l a k e , o r o c ea n

and used t o coo l t h e condense r . I t

i s

t h e n d i sc h ar g e d b ac k t o t h e same

body of

water

w i t h t h e a d d e d h e a t .

Opera t ing

Basis

Earthquake

-

Tha t ea r thquake which produces the v i br a t o r y

ground motion f o r which those fe a t ur es of t h e p l a n t n e c es s a ry f o r c o nt in u ed

o p e r a t i o n w i th o u t undue r i s k t o t h e h e a l t h a nd s a f e t y o f t h e p u b l i c

are

d e si g ne d t o r em a in f u n c t i o n a l .

PWR - P r e s s u r i z e d w a t e r r e a c t o r .

Peak Enthal py on Rod Drop - M el ti n @ of U02 occurs between 220 and 280

cal/gm,

and f u e l ro d r u p t u r e

w i l l

occur about 400 cal /gm.

Thus the

280


24/250

x x i i

P e n e t r a t i o n - A p i p e o r

sleeve w h i c h p e n e t r a t e s t h e c o n t a i n m e n t w a l l -

p i p e s f o r f lo w of f l u i d s , steam, o r g a s e s , a nd s p e c i a l s l ee v e -p l u gs f o r

e l e c t r i c a l d i s t r i b u t i o n .

Pe rc en t Enrichment -Atoms of uranium

235

p e r 100 atoms of

a

uranium

mixture o f

235U

nd 238U

This q ua n t i t y may a l s o mean a toms of f i ss io n-

a b l e n u c l i d e p e r 1 00 a to ms o f

m e t a l

f u e l m i xt ur e.

Plant Operating Mode

-

Load-fol lowing o r base- loaded p la nt .

P r e v a i l i n g Wind D i r e c t i o n - T h e d i r e c t i o n f ro m w hi ch

t h e w in d u s u a l l y

blows.

Pr imary Conta inment (System) -Housing f o r th e re ac to r primary system de-

s i gn e d t o pr e v en t t h e r e l e a s e of r a d i o a c t i v e mate r i a l s t o the env i ronment

i n t h e r em o te e v e n t of a c c i d e n t .

t h e p r e s s u r e s u p p re s s io n p o o l c o n t ai n ed i n t h e t o r u s an d t h e v e n t p i p e s .

The poo l provides a h e a t s i n k f o r r a p i d r e d u ct i o n of p r e s su r e f o l l o w i n g

a

l o s s

o f c o o l a n t a c c i d e n t . I n

a PWR,

t h e c o n t a i n m e n t sy s t e m i n c l u d e s t h e

containment v e s s e l ,

i t s

i s o l a t i o n sy s t em , a nd t h e sp r a y sy s te m w hic h c o o l s

th e atmosphere and reduces th e p res su re .

I n a

BWR

t h e sy s t e m i n c l u d e s t h e d r y w e l l ,

P r o t e c t i v e S ys te m

-

The in s t ru men ta t i on sys tem which handles a l l f u n c t i o n s

of c o n t r o l r e l a t i v e t o o p e r a t i o n of e n gi ne er e d s a f e t y f e a t u r e s o r o t h e r

e qu ip me nt o r f u n c t i o n s d e s ig n e d f o r p r o t e c t i o n of t h e p l a n t .

Radwaste - Con t rac t ion of t he words " r ad io ac t i ve1 ' and "was te" , used to

d e s c r i b e

w a s t e

su b s t a n c e s wh ic h may c o n t a i n r a d i o a c t i v e mate r i a l s .

Radwaste System

-

S ys te m f o r h a n d l i n g , t r e a t i n g , o r s t o r i n g s o l i d , g as eo u s,

o r l i q u i d wastes w hich c o n t a i n r a d i o a c t i v e mater ia l s .

R e ac to r - T h e p r e s s u r e v e s s e l , t h e p r e s s u r e v e s s e l i n t e r n a l s , a nd t h e con-

t r o l r od d r i v e s i n wh ich t h e f i s s i o n p ro c e s s oc cu r s. I n power r e a c t o r s

t h e f i s s i o n e n e r g y

i s

removed f rom t he r ea c t or by a f l u i d sy s t em w h ic h

u t i l i z e s t h e e ne rg y.

Re a c t o r Bu i l d i n g

-

L e a k t i g h t h ou s in g f o r

t h e r e a c t o r , r e a c t o r a u x i l i a r y

sy s te m s , a n d t h e p r im a r y c on t ai n me n t sy s te m , g e n e r a l l y r e f e r r e d t o

as

secondary conta inment .

Reactor Core Isola t ion Cool ing System (RCICS) - P r o vi d e s c o re c o o l i n g i n

case

t h e r e a c t o r i s i s o l a t e d f r o m i t s n o r m a l h e a t s i n k . I t i s a l s o u s ed

i n case

of lo ss-of-f low from th e feedwater sy stem and du rin g shutdown by


25/250

x x i i i

River Flow

-

The ave rage f low pa s t

t h e

s i t e

i n c f s ( cu bi c f e e t

p e r

second) .

Rod-Block Monitor - T h i s su b sy s te m h i n d e r s c o n t r o l r o d w it h d r aw a l e r r o r s

t o pr ev en t f u e l damage. Two RBM moni tor ing channe l s

a re

provided. Out-

pu t s i g n a l s from s e l e c t e d group s of Low-Power-Range Mo nit ori ng (LPRM) sub-

sy s t e m a m p l i f i e r s

are

averaged t o con tr ol rod movement. Computer system

p e r fo r m s t h e a v er a g i n g f u n c t i o n .

Secondary Conta inment -R ea cto r bu i ld in g which i s d e s i g n e d

t o b e f o r low

leakage

i n o r d er t o f u n c t io n

as

c o nt a in m en t f o r r e a c t o r r e f u e l i n g o p e r a ti o n s

and as a backup con tainment dur ing power ope ra t i on or ho t s t andby .

Seismograph -An i n s t r u m e n t u se d f o r t h e m ea su rem en t of v i b r a t i o n , o f p a r t i -

c u l a r i n t e r e s t i n m ea sur i ng g ro un d m o ti o n an d / o r b u i l d i n g m o ti on d ue t o a n

ea r thquake ; sometimes ca l l ed a s t r o n g mo ti on a c c e l e r o m e t e r .

S e r v i c e

Water

System - System which suppl i e s p rocess water f o r

coo l ing

p u r p ose s t h r o u g ho u t t h e p l a n t f o r o t h e r t h a n t h e ma in c o nd e nse r c o o l i n g .

"Shutdown" - A c o n d i t i o n of t h e r e a c t o r

i n

w hi ch t h e c o r e

i s

s u b c r i t i c a l

and power

i s

n o t b e i n g g e n e r a t e d .

Shutdown Boron, ppm - The grams of bo r i c ac i d

H 3 B 0 3

pe r mi l l i on grams of

w a t e r

r e q ui r ed t o ac h ie v e some d e s i r ed s u b c r i t i c a l r e a c t i v i t y l e v e l . A ls o

may be given

as

grams of

B

per mi l l ion grams of

w a t e r .

Shutdown Margin -R ep re se nt a t iv e of t h e amount of r e a c t i v i t y which would

have t o be added t o

a

s u b c r i t i c a l r e a ct o r t o a ch ie ve c r i t i c a l i t y .

S i t e - L a n d

area

l o c a t i o n f o r

a

power s t a t i o n .

Standby Coolant System

- A

supply of coo l i ng water t h a t

i s

a v a i l a b l e i n

case of emergency.

i n g f u n c t i o n . T h i s s u p p ly i s somet imes ava i l ab le by a c ross-connec t ion

between two o r more co ol in g sys tems.

A s u p p l y t h a t

i s

n o t n o r m a l l y u se d f o r

t h e c o r e c o o l -

Standby

Gas

Treatment System - S p e c i a l v e n t i l a t i o n s ys te m f o r t h e r e a c t o r

bu i ld in g. The system

i s

used

if

r a d i o a c t i v e

mater ia ls

a r e p r es e n t i n t h e

r e a c t o r b u i l d i n g .

r o u te d t o t h e v e n t .

A i r

f ro m t h e r e a c t o r b u i l d i n g

i s

removed, pur i f ied, and

Standby Liquid Control System

-

A r ed u nd a nt c o n t r o l s y s t em f o r s h u t t i n g

down t h e r e a c t o r i n t h e u n l i k e l y e v e n t t h a t t h e n o rm a l c o n t r o l sy s t em

i s

i n o p e r a b l e .

L iqu id po i son

i s

pumped i n t o th e re ac to r t o p rov ide th e nega -


26/250

xx

v

Suppression Chamber Cooling System

-

Co o lin g s y st em f o r r e d u c in g s u p p res -

s i o n p o o l t em p era tu re s an d t o r u s p re s s u r e fo l l owin g

a

l o s s o f c o o l a n t ac-

c i de n t i n

a BWR.

T em po ra ry Co n t ro l Cu r t a in -Bu r n ab l e p o i s on s h ee t s p l aced i n

a

new co re t o

compensate

f o r t h e e x ce ss r e a c t i v i t y a s s o c ia t e d w i t h t h e i n i t i a l c or e. A l l

or any number of th e cur ta in s

a re

removab le , usua l ly dur ing re fue l ing , when

t h e r e d u c t i on i n r e a c t i v i t y i n t h e c o r e o r r e g i o n t h e r e o f makes t h e c o n t r o l

p ro v id ed by t h e c u r t a i n s u n n ecess a ry .

Thermal Output - T herm al h e a t en e rg y o u tp u t o f t h e r ea c to r .

Total Flow Rate - Qu an t i t y of co o l a n t f lo w thro ug h t h e r ea c t o r .

T o t a l Heat Output

f o r S a f e t y D e si gn

-

The v a l u e of h e a t o u t p u t f o r t h e c o r e

u se d i n a c c i d e n t a n a l y s i s .

T o t a l P e ak in g F a c t o r - T h e p r od u ct o f t h e i n d i v i d u a l p e ak in g f a c t o r s .

assumes each peak ing fac to r

i s

e f f e c t i v e s i m ul t a ne o u sl y a nd i s t h e r e f o r e

a

T h i s

maximum

es t imate .

To ta l Rod Worth , Pe rc en t - 100

X

t h e ch an ge i n t h e m u l t i p l i c a t i o n c o n s t a n t

f ro m t h e most r e a c t i v e c o n f i g u r a t i o n o f t h e c o n t r o l ro d s t o t h e

l e a s t

re-

a c t i v e c o n f i g u r a t i o n d i v i d e d by k e f f .

I n some p lac es i t may be expressed

i n terms of t h a t v a lu e o f k e f f wh ich t h e ro d s

w i l l

h ol d j u s t c r i t i c a l .

T u r b i n e O r i e n t a t i o n

-

W hether o r n o t t u r b i n e c e n t e r l i n e i s p e r p e n d i c u l a r

t o a c e n t e r l i n e t hr ou gh t h e r e a c t o r , o r w h et he r bo t h h av e t h e same c e n t e r -

l i n e .

m i s s i l e s t h a t c ou ld s t r i k e o r p e n e t r a t e c on ta in me nt .

T h e i n t e r e s t

i s

i n t h e p o s s i b i l i t y of e j e c t e d t u r b i n e b l a de s b ei ng

Unborated

Water

C o n t r o l - A sp ec ts o f bo ro n d i l u t i o n c o n t r o l , i . e . , reduc-

t i o n

o f

b o ro n co n cen t r a t i o n i n t h e c o o l a n t .

S e e

chemical shim.

Variable-Cycle Cooling

-

Both towers and once-through co ol in g

are

combined

and used i n a v a r i a b l e m anner d e pe nd in g upon l i m i t a t i o n s on h e a t r e j e c t i o n

t o

a r i ve r ,

l a k e ,

e tc .

Vessel Vend.or

-

Su p p l i e r of t h e r e a c t o r

vesse l .


27/250

1

I N D I A N

POINT #1, 50-3

pr o j e c t

N ~ ~ ~ :

ndian Point Nuc lea r Uni t

No.

1

Locat ion: West Chester

C O . , N.Y.

Owner

: Conso l idated Edison Conta inment

A E :

Consol idated Edison Co.

Vessel

Vendor:Babcock &

Wilcox

NSS

Vendor: Babcock & Wilcox

Co. of

N . Y .

Cons t ruc to r : Consol ida ted Edison

B .

NUCLEAR

_ _

~

T o t a l

Heat

Output ,

Sa fe ty Des ign. M W t

T o t a l

Heat

Output ,

Btu/hr

Sys tem

P r e s s u r e ,

p s i a

DNBR ,

Nominal

To t a l F l owr at e ,

E ff F l owr a t e f o r

,

Hea t T r a ns , l b / h r

Eff Flow Area f o r

Heat

T r a n s , f t 2

Avg V e l

Along

Fue l

Rods,

f t / s e c

Avg

Mass

Ve l oc i t y ,

Nominal

Core

I n l e t Temp,

OF

Avp,

Rise i n

Nom Hot Cha nn el

O u t le t Temp, OF

Avg Film

C o e f f ,

Avg Film Temp

Ac t i ve

Heat

Trans

Surf

Area, i t 2

Avg Heat

Fl ux ,

B tu /h r f t 2

Max

Heat

Flux,

B t u / h r f t 2

l b h r

l b /hr - f

t 2

Core, O F

,

Btu/hr

f t 2 - r F

,

D i f f ,

"F

615

2099 x

l o 6

1550

2.73

57

x l o 6

48.5

l o 6

6 m

l7-7

2.96

x

i o 6

479-6

35.4

567.3

6950

18.7

15,200

133,600

462

00

Maximum Bur

Boron Worth


28/250

2

Exc lus ion Dis tance ,

Miles

0.265

Low PoDulation Zone

De sig n Winds i n mph:

D i s t a n c e , Miles 0.684

M e t r opo l i s D i s t a nc e Popu l a t i on

New

York Ci ty 24

m i

South

1 1 , 5 2 8 , 6 4 9

D1.

CONTAINMENT

Max Leak Rate

a t

Design

P r e s s u r e , % / d a v 0.1% by weight

Des ign Bas i s Ea r thquake

'

150

- 400

f t

De s i gn P r e s s u r e ,

& d a t e d

Max I n t e r -

i e

25.0 (27.5 m a x )

n a l P r e s s u r e , p s i g ---

A c c e l e r a t i o n , g

Opera t ing Bas i s Ea r thquake Tornado

---

' Des ign Bas i s :


0.10 P

Ea r t hqua ke Ve r t i c a l Shoc k , BP = - - p s i / - -sec

Conta inment vesse l l eakage and conta inment annulus pre s sure

a r e

measured a t m a x i m u m i n t e r v a l s o f 420.5 y e a r s .

P e n e t r a t i o n s :

% of H o r i z o n t a l

Is I n t e n t o f 70 Design

50% i . e . , 0.05 R I

C r i t e r i a S a t s i e d

?

Yes

D.

ENGINEEREC SAFETY FEATURES

a

F r e e s t a n d i n g s t e e l s p h e r e c o nf or mi ng t o t h e r e qu i re m e nt s o f ASME B o i l e r

&

Pre ssur e Vesse l Code, Sec t ion

VIII.

The v e s s e l p l a t e i s ASTM A201,

Grade

B

Fi rebox St ee l . The conta inment sphe re i s supported by a con-

c r e t e b i o l o g i c a l s h i e l d wh ic h pr o v id e s

an

a nnu l a r s pa c e .

The containment vesse l de s i gn w a s based upon

a

2 5 p s i g ( 2 7 .5 p s i g m a x i -

mum)

i n t e r n a l pressure, 1 . 25 p s i g e x t e r n a l d i f f e r e n t i a l p r e ss u r e,

-30F

minimum t o +23 0O~m a x i m u m e n v ir o nm e n ta l t e m p er a tu r e r a n ge . S t e e l p l a t e

specimens were s a t i s f a c t o r i l y i mp ac t t e s t e d a t SOOF.

acuum Re l i e f Capabi l i ty :

C ap ab le o f l i m i t i n g t h e e x t e r n a l o v er

i n t e r n a l p r e s s u r e t o 1 .2 5 p s i .

Pos t - Cons t r uc t i on Te s t i ng :

t


29/250

3

1

D 2 . CONTAINMENT

SAFETY FEATURES I n d i a n Po in t

#1

Containment Spray S y s t e m : The c o nt a inm e n t v e s s e l h a s a n e x t e r n a l

s p r a y s ys te m c a p a bl e of l im i t i n g p r e s s u r e i n t h e c o nt a in m en t vesse l

t o

2 7 . 5

p s i g .

t h e f i r s t

24

h o u r s f o l l o win g

m a x i m u m

c r e d i b l e a c c i d e n t . E x t e r n a l

spray heads

axe l o c a t e d around t h e u p pe r p o r t i o n o f t h e c on ta in me nt

ve ss el . Sprays impinge on th e containment vesse l s u r f a c e .

I t i s a l s o c a pa bl e o f r e d u ci n g i n t e r n a l p r e s s u r e 1 6 p s i

Containment Cooling:

Containment coo l ing under acc ide n t cond i t io ns i s accomplished by the

conta inment e x t e r na l sp ray sys tem.

Containment I so l at io n System: The Containment I so la t io n System

c o n s i s t s o f two i s o l a t i o n v a l v e s , a r r an g ed i n s e r i e s o u t s i de t h e

s p h e re , a c o nt ai nm en t i s o l a t i o n p a n e l ( l o c a t e d i n t h e c e n t r a l c o n t r o l

room) , th e conta inment acce ss

doors,

a nd i n c id e n t d e t e c t i o n a n d

a c t i v a t i o n d e v i c e s .

Containment A i r F i l t r a t i o n :

I

Not app l icab le .

P e n e t r a t i o n Room:

I

Not app l icab le .

D 3 . SAFETY I N J E C T I O N SYSTEMS

Accumulator Tanks :

None

High-head Saf ety I nj ec t i on : The proposed ECCS f or In dia n Poin t Unit

No. 1

w i l l

incorpora te two 100% c a p a c i t y h ig h- he ad s a f e ty i n j e c t i o n

syst ems , ea ch ha vi ng two high-he ad pumps. One

(or

two) of t h e four

high-head pumps

i s

( a r e )

normally used to prov ide re ac to r wa te r make-

u p. I n t h e e v en t o f

a LOCA,

one (or wo) pump(s)

i s ( a r e )

immediately

a v a i l a b l e t o supp ly fu l l -hea d core coo l ing . The low pr imary coo lan t

pre ssu re s i gn al ac t i va t es th e remaining pumps. The high-head pumps

t a k e s u c t i o n f r o m

3

c l e a n

w a t e r

s t o r a g e t a n k s .

A t

d e s ig n c o n d i t i o n s

th e high head pumps can each d el iv er 200 g p m w a t e r

a t

1800 p s i g .

d e l i v e r y i s t h ro u gh t h e r e a c to r v e s s e l h ea d.

Low-head Sa ety In je ct io n:

from t h e contain ment sump

i s

pumped i n t o t h e r e a c t o r v i a t h e r e a c t o r

Wate

-

During low-head system ope rat ion , wate r


30/250

4

Paee

4. PWR

Re a c t o r: I nd i a n Po i n t

#1

The p o s s i b i l i t y o f v e s s e l f a i l u r e h a s be en

E .

OTHER

SAFETY-RELATED

FEATURES

R e a c t o r V e ss e l F a i l u r e :

minimized throu gh th e sys tem des ign,

materials

s e l e c t i o n , i n s p e c t i o n

and t e s t i n g

.

Cont a i nme n t F l ooda b i l i t y :

No t a pp l i c a b l e .

Reactor-Coolant Leak-Detect ion

System:

The l e v e l s o f t h e c o nt ai nm e nt p a r t i c u l a t e a n d g a s r a d i o a c t i v i t y ,

conta inment dewpoint , a nd t ime r e qu i r e d t o f i l l t he c on t ai nmen t sump

a r e mon it o re d t o de t e c t a ny pr i ma r y c oo l a n t s yst e m l e a k s .

Fa i l ed-Fue l -De tec t ion Sys tem:

No Fai le d-Fu el Det ect ion System as s u c h , b u t p r i m a r y c o o l a n t a c t i v i t y

moni tor ing can supply informa t ion

of

p o s s i b l e f u e l f a i l u r e .

~~

Emergency Power:

(1) S t a t i o n b a t t e r i e s

( 2 )

S t ea m-dr ive n t u r b i n e ge ne r a t o r

( 3 )

Em ergency d i e s e l s t o b e i n s t a l l e d w i t h t h e p ro p os ed

emergency core-cool ing sys tem.

Con t r o l of

Axial

Xe non Os c i l l a t i ons

By

Burnable Shims, Par t -Length

Cont rol Rods, In-Core Ins t ru men ta t ion :

p r e c l u d e t h e e x i s t e n c e of d i ve r ge n t xe non i nduc e d power os c i l l a t i o ns

and any power os c i l l a t io ns which might

a r i se

f rom coup l e d t h e m a l -

h y d r a u l i c e f f e c t s .

Boron D i l u t i o n C o n t r o l: T he s ys te m i n c o r p o r a t e s s t o r a g e f a c i l i t i e s

t o t a l i ng 500 c f o f 190F, 19%b o r i c a c i d s o l u t i o n (5 40 0 l b b o r i c a c i d )

a nd pumping f a c i l i t i e s

f o r t r a n s f e r r in g t h e s o lu t io n t o e i t h e r t h e p r i .

mary loop ( 2 pumps each c apa ble of

5

gpm) o r t o t h e c l e a n w a te r s to r ag i

t a nks

(1

ump a t 50 gpm). The qu an t i ty of b o r i c a c i d i s s u f f i c i e n t t o

produce about

30,000

cf

of

4 ,000 ppm bo r i c a c i d s o l u t i o n .

Re a c t o r c o r e

i s

d e si g ne d t o

Long-Term Cooling:

se r vi ce when t h e Pr imary Coolant System tempera ture i s 5 2 6 0 ~ ~empera-

t u r e t o 1 40 F an d op e r a t e s c o n t i n u o u s l y t o mainta in t h i s t e m p e r a t u r e a

The Decay Heat Cooling System i s p l a c e d i n t o


31/250

5

Turbine Orientation:

---

-Emergency Plans

:

Page

5,

PWR

Reactor:

I nd i a n Po i n t

#1

.

GENERlZL

Windspeed, Direction Recorders,

and

Seismographs:

T he re e x i s t s on t h e s i t e a 100- f t tower wi th wind speed and di re c t io n

r e c o r d e r s .

Plant Operation Mode:

Base loaded.

Site Description: Loca ted on the ea s t bank of t h e Hudson Rive r about

24

mile s no r th of t he no r th boundary of New

York

City and about

45

miles nor th of th e r ive r -ocean junc t ion . The Hudson Rive r

i s

cha rac -

t e r i z e d by s t e e p ba nk s r i s i n g

up

f r om t he r i ve r f o r mi ng

a

deep N-S

v a l l e y w hich s i g n i f i c a n t l y e f f e c t s t h e w e at he r . The s i t e l e v e l v a r i e s

f rom 10-f t

MSL

t o

140 f t .

Environmental Monitoring Plans:

Envir onme n ta l M on i to r i ng i nc l ude s c he mic a l , r a d i a t i on , a nd b i o l og i c a l

sampling.

Studies Program.

The b i o l o g i c a l s t u d i e s a r e p a r t o f

a

massive Hudson River

b t r n e n t

Twelve-gpm evapora tor used t o t r e a t l iq u id was te a f t e r about one week

holdup. Demine ra l i ze r s

2 )

us ed t o t r e a t s te a m ge ne r a t o r b l owdom

p r i o r t o r e le a s e .


32/250

6

Page 6, PWR

t

I

R a n t - t n r . 11

G. SITE DATA

I Hudson

River

Max Prob Flood Level

7 . 4 l

Size

of

Site Site Grade Elevatio

Once through

Hudson River

Water Taken From:

I

Intake Structure:

River Flow , 3,500 (cfs p minimum;

gpmfreactor "Freshwater flow.

ervice Water Quantity

38

ooo

Flow Thru Condenser 280,000

Heat Dissipated to Environment


33/250

7


34/250

8

DRESDEN.

50

- 0

P r o j e c t

N a m e :

Dresden Nuclear Power

S t a t i o n U n i t 1 A-E: General E l e c t r i c

Location: Grundy C O .

,

Morr is , 111.

Vessel

Vendor: N . Y . S h i p b u i l d i n g Cc

3wner: Commonwealth Ed iso n Co. Con tain men t

NSS Vendor: G.E.

> -

ons t ruc tor :Bechte l Corp .

A . THERMAL-HYDRAULIC B.

NUCLEAR

-uu II1~Iu-. I-

Type and Form

Number of Control 8o

Rods

Number of Part-

None

rhermal Output , H 2 0 / U 0 2 Volume

E l e c t r i c a l O u t p u t ,

Moderator Temp

To ta l Heat Out put , Moderator Temp

R a t i o

12.13:l

Coe

f

Coef

2 . 2 ~ 1 0 - ~ ioo0l

I

Burnable Poisons.

c9An,ini3

RnAc I

280

eak Fuel Enthalpy

on Rod Drop, Cal/gm


35/250

9

Page 2 ,

BWR

-

Reac tc r : L

. SAFETY-RELATED D E S I G N C R I T E R I A

Exclus ion Dis tance ,

Miles .5

radius

De si gn Winds inTh-:

Low Population Zone

Di s t ance , Miles

Metropol i s Distance Population

Chicago,

I l l i n o i s rTq7n i


Opera t ing

Basis

Earthquake

A c c e l e r a t i o n ,

g

' Ear thquake Ver t ica l Shock ,

% of Hor i zon t a l C r i t e r i a S a t i s f t e d ?

Recirculation Pumping System CS MCHFR:

a t 125% power con dit ion s.

canned type, 410 hp pumps producing

a

t o t a l of 25.6

x

l o 6 l b f h r f l o w .

A t

0 -

50

f t e l e v 110

--

6,978,947 50

-

5 O f t 110

' Des ign Basis Earthquake 150 - 400 f t 110

47

---

Tornado ---

---

AP

=

- - p s i /

- 3 e c

Is In te n t of 70 Ces ign _ _ _

MCHFR must b e >1.5 when eva lua te

---

The r ec i r cu l a t i on sy s t em cons i s t s o f 4 GE

P r o t e c t i v e S ystem : P r o vi d es p r o t e c t i o n a g a i n s t c o n di t i o n s t h a t

threaten i n t e g r i t y o f

nuclear

sys tem process ba r r ie r by scramming

t h e r e a c t o r f o l lo w i n g ab no rm al o p e r a t i o n a l t r a n s i e n t s .

D. ENGINEERED SAFETY FEATURES

D1. CONTAINMENT

Drywell Design

Prinary Containment Leak

Su pp re ss io n Chamber Design Second Contai nment Design

Ca lcu lat ed Max In Ze rna l Second Containment Leak

P r e s s u r e , p s i g N/A

Rate,

%/day

N/A

Type

of

Cons t ruc t i on :

c

P r e s s u r e , p s i g

2 9 . 5 Rate , %/dap - 5

P r e s s u r e , p s i g

P r e s s u r e , p s i g N / A

Sphe r i ca l s t e e l s h e l l , 190 f t i n diameter a t

t h e

equator and approxi -

mate ly 156 f t above ground l eve l .

Design Basis:

D es ig ne d t o w i th s t a nd p r e s s u r e e q u a l t o o r e x ce e di n g t h e i n t e r n a l

p r e s s u r e

th a t wou ld be c r ea t ed by t h e most p robab l e k inds of po t e n t i a l

r eac to r - rup tu r e acc iden t s .

Vacuum Kel ie t C a p a b i l i t y


36/250

10

Page

3 ,

BWR

Reactor

:

Dresden

1

2 .

EMERGENCY CORE

COOLING SYSTEMS

Core Spray Cooling System:

A s i n g l e , c i r c u l a r c o re s p ra y s p a rg e r w i t h 64 s p r a y n o z z l e s w i l l be

l oc a t e d a bove t h e r e a c t o r c o r e a nd des i gne d t o d e l i v e r 2100 gpm.

r e qu i r e d c o r e s p r a y fl ow w i l l be main ta ine d by two of t h r e e 50%

c a p a c i t y pumps.

The

Suc t i on w i l l b e f ro m t h e f i r e p r o t e c t i o n s ys te m .

None

Residual-Heat-Removal

S y s t e m

(RHRS):

High-pressure Coolant - In jec t ion

System:

None

Low-Pressure Coolant- Injec t ion

Sys tem:

See

c o r e s p r a y

system.

-

E . OTHER SAFETY-RELATED

FEATURES

Main-Steam-Line Flow R e st ri c to rs :

None

-

Control-Rod Veloci ty L i m i t e r s :

None


37/250

11

'

Conta inment F loodab i l i ty :

None

Reactor-Coolant Leak-Detection

S y s t e m :

Any rea c to r coo l an t l eak would be de tec t ed th rou gh the use

of

the dew

c e l l

sys tem and wi th the use o f the c o n t in u ou s a i r m o n ito r.

Fa i led -Fue l De tec t ion Sys tems:

Page 4 , BWR

I

E. OTHER

SAFETY-RELATED FEATURES (cont 'd) Reactor: Dresden

111

Standby Coolant

System:

See core sp ray sys tem.

Containment Atmospheric Control System:

I-

None

Emergency Power:

A 500 Kw, 480 v d ie s e l - d r iv e n g e n e r a to r i s used on l o s s of o f f - s i t e

power t o p r o v id e power t o t h e e s s e n t i a l l o a d s

on

t h e

480

v system.

Bat t e ry power fu r n is hes 125 v d c f o r c o n t r o l s , e me rg en cy l i g h t i n g ,

a nd i s o l a t i o n v a l v e s .


38/250

12

Pane 5.BWR

Reactor : Dresden 1

.

GENERAL

Windspeed, Dir ec t i on Recorders , and Seismographs:

A

tower

e r e c t e d a t t h e s i t e c on t i nuous l y r e c o r d s w i ndspe ed , d i r e c t i o n ,

t empera ture , dew p o in t and r a i n f a l l .

uni t 2 o r 3.

P l a n t Operation Mode:

Base loaded.

S i t e D e s c r i o t io n :

S i t e

i s

about

47

miles

SW

of Chicago where th e

D e s

Pl a i ne s a nd

Kankalcee Rivers come together ;

a d j a c e n t t o t h e Dr es de n l o c k o n t h e

Illinois River. The s i t e i s compara t ive ly l e v e l w i th maximum va r i a -

t ion

of 25- f t e l e va t io n . The

area

a r ound t he s i t e i s most ly

agri-

c u l t u r a l a nd i n d u s t r i a l .

Seismograph i s i n s t a l l e d i n

- -

t u r b i n e b u i l d i n p . E l e ct e d b l a d e s c o ul d n o t s t r i k e

c

Emergency P l a n s :

T he g e n e r a t i n g s t a t i o n s e me rg en cy p l a n e s t a b l i s h e s p r o t e c t i v e a c t i o n

levels a nd p r o v id e s l i a i s o n w i t h o f f - s i t e s u p p o r t gr ou p s i n c l u d i n g

f e d e r a l ,

s ta te ,

a nd l o c a l gove rnme nt a u t ho r i t i e s when s uc h l e v e l s a r e

exceeded. Document reviews and co nt ro l , emergency prepare dness assess

o b j e c t i v e l y se t f o r t h by t h e p la n .

Envi ronmenta l Moni tor ing p lans : Envi ronmenta l moni tor ing i s c on t r a c t e d

t o

o u t s i d e o r g a n i za t i o n .

1.

17 s am pl e s t a t i o n s f o r a i r b o r n e p a r t i c u l a t e a nd i o d i n e s a mp le s.

F i l t e r s

are

changed weekly a t e a c h s t a t i o n .

have ion chambers which are r ead weekly and T u ' s r e a d q u a r t e r l y .

Weekly samples i nc l ud e s u r f a c e wa te r a nd mi lk .

- a nnua ll y ; f oods t u f f s - 3 t i me s pe r ye a r .

q u a r t e r l y ; a q u a t i c a n i m a l s -q u a r t e rl y .

m en t a nd t r a i n i n g of p l a n t p e rs o n n el , i n c l u d i n g p e r i o d i c d r i l l s a r e

I n cl u de d i n t h e r o u t i n e s am pl in g

are:

T he se s t a t i o n s a l s o

2.

3. F a l l o u t - A i r b o r n e s o l i d s & l i quids -xnonthly ; so i l - a nnu a l ly ; f eedc rops

4.

W e l l wate r -qua r te r ly , bot tom sediments - semi-annua l ly ;

s l i m e -

Radwaste Trea-tment:

I

ystem

collects ,

p r o c e s s e s , c o n t r o l s

and

d i s p o s e s of p o t e n t i a l l y r a d i o -

active

waste.

Li qu i ds f rom t he r e a c t o r p r oc e s s s yst e ms or l i q u i d s

which

have

bec ome c on ta mi na t e d a r e p r oc e s se d a c c o r d i ng t o t h e i r pu r i t y

b e f o re b e in g r e l e a s e d e i t h e r f o r r e t u r n t o t h e p l a n t as condensa te ,

sent t o t h e d i s c h a r g e c a n a l o r i mm ob il iz ed i n dru ms f o r e v e n t u a l d i s -

p o s a l o f f s i t e , s o l i d

wastes are

p ro ce ss ed f o r d i s p o s a l o f f s i t e .


39/250

1 3

G . S I T E

DATA

Nearby Body of

Water:

Kankakee River

Reactor : Dresden 111

Normal Level

505

(MSLJ

I l l i n o i s R i v e r and Max Prob Flood Le ve l 5n81 (MSL)

Page

6 ,

BWR

I n t a k e

St

u c t u r e

:

C a n a l fro m t h e I l l i n o i s R iv e r t o t h e c r i b ho us e w hich c o n t ai n s a

screen

f o r r emov ing de b r i s f r om t h e w a t e r pr i o r t o be i ng pumped t h r ough p l a n t .

Water Body re mp era tur es: Winte r minimum 40 F Summer maximum %OF

Ri ve r Flow 3000 ( c f s ) minimum; 47nn ( c f s ) a v e r a g e

Se rvi ce Watrr Qu an t i ty 12.900 gpm/

r e a c t

o r

Flow Thru Gundenser 1 7 ~ 7 0 0 (gpm)/reactor Temp.

R i s e

---

F

Heat

D i s s i p a t e d t o Environment

---

( B tu / h r) / r e a c t o r

H e a t Removal Ca pa city of Condenser 1. 75

x

l o 6 ( B t u / h r ) / r e a c t o r

S i z e of S i t e 953 Ac re s S i t e Grade El ev at io n 516' (MSL)/

I Topography of S i t e : F l a t

of Surrounding

Area

(5

m i

r a d ) : R o l li n g p r a i r i e

To ta l Pe rmanent Popu la t ion : In

2 m i

r a d i u s

5 0 ;

10 n i

25.000

Date

of

Data:

1968 In 5

m i

r a d i u s

2600

;

50 m i

Nearest

C i t y

of 50,000 P op ul at io n: J o l i e t , I l l i n o i s

D i s t .

from

s i t e

14

Miles,

D i r e c t i o n

NE ,

Popu l a t i on 75,000

Land Use i n 5 X i l e Radius :

A g r i c u l t u r e

Meteorology: P r e v a i l i n g w i n d d i r e c t i o n N h Avg. speed 10 mph

S t a b i l i t y

Data

-

Misce l l aneous

Items

C l os e t o t h e S i t e : S ou th

of

t h e s i t e

i s

the Genera

E l e c t r i c Company's Nuclear Power Pl an t Tra i nin g Ce nter .

A l s o l oc a t e d

i n t h e s a m e area i s

G . E . ' s

Midwest Fue l Recovery Pl an t .

O t h e r a c t i v i t

i e s are t he I l l i n o i s C la y P r oduc ts Company ( Re f r a c t o r i e s a nd Br i c k

Pr oduc t s) a nd some a g r i c u l t u r a l ope r a t i ons .

mine

i s

l o ca t ed i n t h e a rea a l s o .

H . CIRCUU.'TING

WATER

SYSTEM

Gases

would

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