ML20210A014

Summary of 870115 Meeting W/Util in Richland,Wa Re thermal-hydraulic Analysis Supporting Util Proposed Expansion of Spent Fuel Pool.List of Attendees & Summary of Description of Util thermal-hydraulic Analysis Encl

ML20210A014
Person / Time
Site:	Vermont Yankee
Issue date:	02/04/1987
From:	Rooney V Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8702060371
Download: ML20210A014 (29)

Text

_ _ _ _ _ _

n

' 4 FEB 1987 Docket No. 50-271 LICENSEE: Vermont Yankee Nuclear Power Corporation FACILITY: Vermont Yankee Nuclear Power St0 tion

SUBJECT:

JANUARY 15, 1987 MEETING WITil THE VERMONT YANKEE NUCLEAR POWER CORPORATION (VYNPC)

Re: Spent Fuel Pool Expansion On January 15, 1987, a meeting was held in Room 148 of the Hanford House in Richland, Washington to dicuss the thermal-hydraulic analysis supporting Vermont Yankee's proposed expansion of the spent fuel pool. Pacific Northwest Laboratory (PNL) is under contract to perform independent analysis of natural convection cooling in the spent fuel pool. Comparison of results of PNL's calculations will be made with VYNPC's results. Enclosure 1 is a list of individuals that attended the meeting. Enclosure 2 is a summary of the description of VYNPC thermal-hydraulic analysis which was presented at the meeting. The following clarifying information was also provided:

1. Vermont Yankee fuel pool was designed and licensed for 150 F bulk temperatu re.

2. The pool now has empty locations for exactly one full core offload (368 assemblies).

3. Vermont Yankee is in the process of going from a 12 month to 18 month fuel cycle (the cycle includes about 2 months for outages).

4. At the location of the fuel in the pool, saturation temperature is about 230-240 F due to the head of water above the fuel.

C. The conservatism of Vermont Yankee analysis is supported by measurements in the Maine Yankee spent fuel storage pool as described in Enclosure 2.

eriginal sigel W Vernon L. Rooney, Project Manager BWR Project Directorate #2 Division of BWR Licensing

Enclosures:

As stated cc: w/ enclosures:

See next pa DBL:PD#2 DBL 1 -2 VRooney:cb D l e'r 2/1 /87 2 /87 8702060371 E70204 POR ADOCK 05000271 P PDR

j . s. ...T ...v....._..,......_.........._.._....._,...

l .

~

Mr. R. W. Capstick Verwent Yankee Nuclear Power Vermont Yankee Nuclear Power Corporation S'ation cc:  ! W. P. Murphy, Vice President & .

Mr. J. G. Weigand Vr.

President & Chief Executive Officer Manager of Operations Vermont Yankee Nuclear Power Corp. Vermont Yankee Nuclear Power Corp.

R. D. 5, Box 169 R. D. 5, Box 169 Ferry Road Ferry Road Brattleboro, Vermont 05301 ,;, Brattleboro, Vermont 05301 Mr. Donald Hunter, Vice President e Mr. Gerald Tarrant, Comissioner Vermont Yankee Nuclear Power Corp. Vemont Department of Public Service -

1671 Worcester Road 120 State Street Framingham, Massachusetts 01701 Montpelier, Vermont 05602 New England Coalition on Public Service Board Nuclear Pollution State of Vermont Hill and Dale Farm 120 State Street .

R. D. 2, Box 223 Montpelier, Vermont 05602 -

[

Putney, Vemont 05346 g

Vermont Yankee Decommissioning [

Mr. Walter Zaluzny Alliance (

Chairman, Board of Selectman Box 53 Post Office Box 116 Montpelier, Vermont 05602-0053 Vernon, Vermont 05345 Resident Inspector Mr. J. P. Pelletier, Plant Manager U. S. Nuclear Regulatory Commission Vermont Yankee Nuclear Power Corp. Post Office Box 176 Post Office Box 157 Vernon, Vermont 05354 Vernon, Vermont 05354 Vermont Public Interest Mr. Raymond N. McCandless Research Group, Inc.

Vermont Division of Occupational 43 State Street

& Radiological Health Montpelier, Yemont 05602 Administration Building 10 Baldwin Street Regional Admin.istrator, Region I Montpelier, Yemont 05602 U. S. Nuclear Regulatory Commission 631 Park Avenue Honorable John J. Easton King of Prussia, Per(1sylvania 19406 Attorney General s State of Vermont Ellyn R. Weiss 109 State Street Harmon & Weiss Montpelier, Vermont 05602 2001 S. Street, N. W.

Suite 430 Washington, D.C. 20009-1125 John A. Ritscher, Esquire Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110

o.

Enclosure 1 List of Meeting Attendees Vermont Yankee Spent Fuel Pool Expansion .

Janua ry 15, 1987 Name- Organization VRdoney NRR/ DBL /PD#2 JRidgely _NRR/ DBL /PSB RLodwick VYNPC PBergeron Yankee Atomic Electric Co.

MMarlon Yankee Atomic Electric Co.

CWheeler PNL SBian PNL l'

s

?

6 A h

$.\

Enclosure 2 i.

~

VERMONT YANKEE FUEL P0OL THERMAL-HYDRAULICS i

r i

{-

l-I' .

P. A. BERGERON

, YANKEE ATOMIC ELECTRIC COMPANY 1

e

O OUTLINE s

o INTRODUCTION l

o PREVIOUS YANKEE APPLICATIONS o FUEL P0OL COOLING SYSTEM .

~

o ANALYSIS DESCRIPTION o BULK P0OL HEAT LOAD ANALYSIS o ASSEMBLY-WISE ANALYSIS o TEST DATA o DISCUSSION OF OPEN ITEMS e

G

l VERMONT YANKEE PROPOSED CHANGE o INCREASE NUMBER OF ASSEMBLIES STORED IN P00L 2000-2870 i .

i

- o RACKS WITH REDUCED PITCH TO ACCOMMODATE g NUMBER OF ASSEMBLIES o P00L SPARGERS l

r l

t l.

1

v 1

PREVIOUS YANKEE APPLICATIONS l

0 VERMONT YANKEE - 600 To 2000 l

l 1

- o YANKEE R0WE - DOUBLE TIER STORAGE  ;

g o MAINE YANKEE - CONSOLIDATED STORAGE i

I i

r 1

i-t

.-w- m.-em-, ., - ,y ,--,.m, -,m--r -, ,wrw--,,-,-y --,+ - - - - - - --- - - - - - - -- - - - - - - - - .~ , -. -

, I G

N I

L

• F O

O LL 05 G EO VI l

L OO < O =.-_

FP D

= F g L

E U y F

. g -

I

_ O.

N m c

c

_ e s

- =

u em s

E M o W

E c E T 7 a

S

< S Y

Y S

l N 3#

A S

O (\

R Y R E H _ ~ AT =

~

- R W ~

N O E C

M l V

R z a

h R E

E /w R

W S V oso HS et r

R a s.

7 s

x l 0 g

g y

j g

T:

B OO R

FT

o THERMAL-HYDRAULIC ANALYSIS CONSIDERATIONS o INCREASED HEAT LOAD

o FUEL P0OL SPARGERS o P00L LOADING j

o FLOW DISTRIBUTION l

i o HYDRAULIC RESISTANCE TO NATURAL CIRCULATION e

l w,... ~ ,. , , ,w w.,..,-,, ,- ,,am_g. g. . , , - ,,,+ ,- . , .. , ,. ,

e FUEL P0OL COOLING ANALYSIS o BULK P00L HEAT LOAD ANALYSIS o COOLING SYSTEM CAPABILITY

- o LIMITING HEAT LOAD CONDITION I

o MAXIMUM BULK POOL TEMPERATURE o ASSEMBLY-WISE ANALYSIS o LIMITING LOCAL TEMPERATURE IN P0OL 1 .

l l

T BULK P0OL HEAT LOAD o EVALUATION OF P00L LOADING I

o ANNUAL o- 18 MONTH I

o NET DECAY HEAT IN P0OL o CYCLES 1-10 (1202) l l

o PROJECTED LOADING l

o POOL FULL EXCEPT FOR 368 SPACES (FULL CORE) o FULL CORE DISCHARGE l

o COMPARE HEAT LOAD TO P0OL COOLING CAPACITY l

BULK TEMPERATURE i

t A ..

FUEL P0OL COOLING HEAT LOAD

• CAPACITY 6 MRE BULK TEMPERATURE X10 BTU /HR FUEL POOL COOLING FUEL P0OL COOLING 57 5/<150 F 17.0 I AUGMENTED RHR POOL CONTAINS 2870 ASSEMBLIES AFER FULL CORE DISCHARGE .

10 DAY DECAY

IMPACT ON P0OL HEAT LOAD HEAT LOAD 6

X10 BTU /HR 2000 ASSEMBLIES 16.14 .

t 2870 ASSEMBLIES 17.0

- a0 e

a e

ASSEMBLY-WISE ANALYSIS o 0BJECTIVE - LIMIT LOCAL BULK FLUID TEMPERATURES

< SATURATION o HYDRAULICS FUNCTION OF POOL LOADING (INCLUDING VACANT CELLS) t o FLOW DISTRIBUTION IN POOL o IMPACT OF SPARGERS l . o HYDRAULIC FLOW PATHS i o INLET TEMPERATURE TO ASSEMBLIES o SIMPLIFIED CONSERVATIVE MODEL (1-D)

VY Spent ruel storage Rack Arrangement

,t l

Y/M//MHHfA ,

e

' Direction of l k_,

flow assumed ' H '

f i

> ;, o . , . . . . . . . . .

q,,!

/ 4

, i ,

i

, l l

l .

l f NSteT l

- - Caps l

l l

4 r

I F s C j.d

. F - Cld.

F s 8 j.d. .

n o

6 ],d i ,

F s t c

n g

. . u ,

F s 6_j. d_. J h

F s f .

d_,,. j t

i F * $_p.d.

F

• f a-  ;

F s a d_-

h F , 6]. d .

l l

. e w

F .. - .

l

• o F 6_ . 4 o s p

~

l e

d o

F

• d .l F e

'0 u f

M 2

- F ,

6_ .

. d ,. 5 1 e h

0 i tt f_ . d.

N F e 3 d .

A R t. .

dnr eao T F o 6_ . d-

,t E

R s t e

,l

? p_d.

f tk t

e e I s ' ncl iao aro r

t n

F * -

a.

l m

sol f

p e e e S

p F s 6],,d ieu l gf i bd

'. . d.

T

. . med V F 3 e

sea n

t sh

~ F . 6 .

d. et m i nt cet o

F s %_ , d. ueo f wb t

F s %_ , d.

t eek vbc o

bnr .

o P i d, aoi ne s

"._ rgei eeel J. d, n t rwb F

• i o e vree t m F , " d, t i

p f n oone ebs s

, r co c l nil F . $_ -

d, s e

owge ooeu D FDRF d,

l . %_ -

b . 6_ , d. e I

. d, l m

u 12 - -

22 37 l, o 33 V 4 I

- e -

. i ' -

l

i I

TEST DATA

>- o MAINE YANKEE POOL o VERIFICATION OF SIMPLIFIED LICENSING MODEL o VERIFICATION OF GFLOW

~ l (3D GRAVITY DRIVEN FLOW)

, I l o EPRI NP-3097 MAY '83 i

o EPRI NP-3381-CCM Nov. '84 .

l l

o DATA TAKEN o FOLLOWING FULL CORE DISCHARGE

~

o VELOCITY AND TEMPERATURES THROUGHOUT P0OL l

l l

l l

l l

t .. -.

I J I '

e c

n e a n c r o '0 n a a

r a

e l

C e

ig t

i a

c

(

1 4

1 c

e b

d f n l

C '0. i a r r 1 u, a 4 P, '2 e

• . .l 1

3 C

, I 7 5

• x x

9 0 0 1 1 )

w e

i V

7 4 p 7 o x 5 T

(

x 0 y 0 1 r n

e 1 t

e m m o

e 5 5 G x x '8 l o

4 o 0 0 4 P 1 1 l  !  !

h t qI  ; 1 4

l e

u r 5 o 5 _ F N x x _

t n

0 e 0 - p 1 1 S

- '7 l B

7 m 6

._ rs 1 e

• x _ f n ei r u

sa g

' 0 nh i 1 _ ac F re

_ Tl f

. l e

5 .

u 7 F 7

x x c $

8 x n 0 l a '0.

1 9 ar 4 nt an 5 2

CE 3

0 \ fh 9

Nn t Y 3

, l.

' a e 1 6 3 r l a n '

1 e I 9 r, l

T C 6 3

g

\\ i' l I!lI ll lI lll l )l ll

9 I

f k

t l

1 1

Secondary Coolant Exit Water Level Coolant "

Y 3; 9

' L'

[2 ' Coolant Leaves -

Inlet 4

. .'I 13' Pool I

b" Fuci

anal E1tranca 36.5' Spent Fuel Storage l~s I i 0 t

,I41

,I i 1 i l Ii 1 8 ii 14.3' 9.4"lII8 fddl'bdddfb't'!I' 8 Main Coolant

'88 hech'abism*l1I - n 3, 1. lj i 8 88IeIeie a I .' 1 L i Y +.J fJ t._

3' Exit

. --g c 41.4'  ;

9 Figure B2. Sido View of Maine Yankee Spent Fuel Storage Pool e

I l

l B-2 1 1

a

Y

.s j . _ _ _

98.4 98.6 P Q B C l

l C 98.55 c 98 ( 98.6 98.6 98.6 i l

l l

i I D G F A E t

P l-4

-, a 98.5 96 5 98.45 98.6 98. '

98.5 98.2 98.6 98.6 a.

98.3 98 J J K L M N O J A

98.6 98.5 }

98.6 98.6 98.6

_ (98.8) 9R.C

,,3 98.5 1

l l

_____.-n_,-_m- -- - _ _ w o- _ . x_ - . ,_ m, _ __

l 6 I'igure 3-8. Measured Ternperatures at 2' Depth i

9 1

1 1

1 i

3-10 l

t O .

l l

e r

98.55 98.55

. 9 B P C 98.6 98.65 99.6 98.5 98.5 D G F A E 98.2 98.6 98.6 98.5 9 s.5 98.4 98.5 98. *' 98.5 9 -

98.3 l

J K L M N O gg $

98.6 98.6 98.9 98.5 98.5 98.6 (98.6) l fa e

98.4 98.5 1

l 0 l

l i

f Figure 3-7. Measured Temperatures at 6' Depth l

l l

t 3-9 i

h

1

\

i l

)

.o

)

j 9A.4 98.5 B C l g

P l i

'* 98.55 l i

98. a 98.55 98.5

- )

i l

I 0 c r a e

)

I 9 -

98.2 98.6 98.6 98.5 98.5 98.5 98.45 9F.5 98.55 99.3 J K L M N O 98.5 98.7 98.4 98.5 98.5 97.8 98.6 98.5 6.0 l

.-,m-_ ____ m----m __ __..-.-..---m_____----w,m_

i Figure 3-6. Measured Tempora.tures at*10' Depth l 1

l l

l 3-8

! I

e e

l l

l l

I l

l l

98.5 98.4 l

B l g

C l P l l \

l i 98.5 98.5 98.7 98.55 98.5 )

l D G r A g 90 98.6 98.5 98.5 9 .5 98.45 98.4 90 .4 98.55 98 4 l

)

y 98.3 I K L M N O l

98.5 98.4 98.4 98.2 98.5 98.5 i

, 98.3 l 98.5 95.8 l

l Figure 3-5. Measured Temperatures at 14' Depth l

I l

l I

3-7 i

____-1

I 1

n P p C 98.6 98.6 99.1 98.6 98.5 98.5 G F n .

D I

l i

93 97.7 97.6 97.7 97.7 97.7 l

i E

97.9 98.1 97.7 99.2 97.9 97.8 1

1 46.1

, J K L M N O l

Figure 3-4. Measured Ternperstures at 18' Depth 3-6 I

• e e

t

I I i

• l e .c 95.7 o -,e b 96.6 AUO*1 ***"

97.9 102 99.4 100. 97.2 l p 101 98.1 97.5 100. 97.6 97.

l l 95.2 98.6 99.1 9's 97.8 98.

l Ic2 '7 2 '74

97. 502.599.6 99.5 1

4' A 97.2 94,7 97.5 96.8 98.0 95.8 97*2 97.0 9g,0 j '

~ l 17.0 1

Ir. M

• 97.6 95.0

." 97.1, 97 4 M r 37.6 9(. 6 98.2 8*

96.1 96.8 98.2 97.1 98.0 98.2 99.6 98.2

'01.5 97.8 96.6 98.2

• • 7 98.4 97.4 97.1 97.4 96.4 y g g 96.8 N O 97.2 97.2 97.7 Figure 3-3. Measured Temperatures at Top of Fuel Assemblics Circled Numbers refer to measurements performed over empty fuel rack locations ,

l

\

l

,+ b

. , 3-5

~

l

.g.. l e -

l l ~-

SUMMARY

/ CONCLUSIONS OF DATA o INLET TEMPERATURE TO P0OL 790F (83 F IN P0OL) o OUTLET TEMPERATURE FROM POOL +980 F o PEAK TEMPERATURE IN P00L ~102.5 o TEMPERATURE OVER VACANT CELLS 97-99 F t

o BULK TEMPERATURE AB0VE RACKS UNIFORM AT -98 F l

o TEMPERATURE AT BOTTOM 0F FLOOR 94 F o DATA COMPARED WELL TO GFLOW o ASSEMBLY AT 1/3 THAT PREDICTED BY LICENSING MODEL

OVERALL CONCLUSIONS o LICENSING ANALYSIS MODEL OVERPREDICTS TEMPERATURES IN POOL o LICENSING MODEL ACCOMMODATES CASE WITH .

~

CUT SPARGERS I

o BULK P0OL TEMPERATURE WILL BE MAINTAINED 0

(FOR MAX HEAT LOAD) 5 150 F o LOCAL TEMPERATURES IN HOTTEST ASSEMELIES

< SATURATION

o Keywords: EPRI NP 3097 Spent Fuel Storage Project 2240-4 Storage Pool Thermal Hydraulics Final Report Electric Power Storage Pool Temperature Data May 1983 Research Institute Thermal Hydraulics Verification of the GFLOW Computer Code Using

. ~j.wygr Experimental Data From the l Wifa*28'* Maine Yankee Spent-Fuel .

Storage Pool t .

I Prepared by NUS Corporation Menlo Park, California l

l l

lt..

Topics: EPRI NP-3381 CCM Spent fuel storage Volume 1 Ponds Project 2240-4 El:ctric Power Computer codes Computer Code Manual Research Institute Thermal-hydraulic models November 1984 J GFLOW Thermal Hydraulic Code

i Volume 1:

4 g -fy, Spent-Fuel Pool Licensing Analysis and

. M&nJ4

. Sensitivity Studies .

1

(

Prepared by NUS Corporation Menlo Park, California

DISTRIBUTI0f{

-06cket File NRC POR' ~

Local PDR PD#2 Reading File DMuller VRooney OGC-Bethesda Edordan BGrimes ,

ACRS (10)

NRC Participants -

s s

k i