ML19318A426

Slide Presentation Entitled, Safety/Relief Valve Discharge Into Suppression Pool.

ML19318A426
Person / Time
Site:	Nine Mile Point, Susquehanna, Columbia, Limerick, LaSalle, Zimmer, Shoreham, Bailly  File:Long Island Lighting Company icon.png
Issue date:	04/10/1980
From:	STONE & WEBSTER, INC.
To:
Shared Package
ML19318A421	List: ML19318A426
References
REF-GTECI-A-39, REF-GTECI-CO, TASK-A-39, TASK-OR NUDOCS 8006230007
Download: ML19318A426 (28)

Text

.

'- 1' SRV DISCHARGE INTO SUPPRESSION POOL v -

o HATCH PRESENTATION - FEBRUARY 1978

- SIMILAR TO SNPS PRELIMINARY TRANSIENTS PRESENTED IN JANUARY 1976 2

- EVALUATED AGAINST 150 F/40 LBM/FT -SEC LIMIT o NRC EXPRESSED SERIOUS ~ RESERVATIONS WRT R/H LIMITS-MAY/ JUNE 1978

- STRONGLY SUGGESTED QUENCHERS FOR MK II o ZIMMER/LA SALLE CLOSURE REPORTS - JULY 1978

- INCLUDED TRANSIENTS EVALUATED AGAINST R/H LIMITS o MK II COMMITS TO QUENCHERS - AUGUST / SEPTEMBER 1978

-l l :FCR

.4/3/80.

t.

89

• 2 *

• 7 _ n

SRV DISCHARGE INTO SUPPRESSION POOL (CONTINUED) -

o LP ACCEPTANCE CRITERIA /LER ISSUED SEPTEMBER /0CTOBER 1978 200 F (LOCAL)-LIMIT ESTABLISHED FOR QUENCHERS INVITED ADDITIONAL DATA TO SUPPORT HIGHER OR NO LIMIT o MK II APPROACH WORK WITH NRC 200 F LIMIT G0AL: TO MEET LIMIT INDEPENDENT OF RVP MASS FLUX VERY LOW FOR T APPROACHING P00L MAXIMUM ADDITIONAL INFORMATION SUPPORTING STABLE CONDENSATION FOR QUENCHER UNDER ALL CONDITIONS

.FCR 4/3/80

- - _ - - _ _ . _ f

3, NRC REQUESTED MK IIs EVALUATE THE SUPPRESSION-POOL TEMPERATURES FROM THE FOLLOWING TRANSIENTS A. A STUCK-0 PEN SRV DURING POWER OPERATION ASSUMING REACTOR SCRAM AT 10 MINUTES AFTER THE P0OL TEMPERATURE REACHES 110 F AND.ALL RHR SYSTEMS OPERABLE

B. SAME AS EVENT (A) AB0VE EXCEPT THAT ONLY ONE RHR TRAIN AVAILABLE C. A STUCK-0 PEN SRV DURING HOT STANDBY CONDITIONS, ASSUMING 120 F P0OL TEMPERATURE INITIALLY AND ONLY ONE RHR TRAIN AVAILABLE D. THE AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) ACTIVATED

-FOLLOWING A SMALL LINE BREAK, ASSUMING AN INITIAL P0OL TEMPERATURE OF 120 F AND ONLY ONE RHR TRAIN AVAILABLE E. THE PRIMARY SYSTEM IS ISOLATED AND DEPRESSURIZED AT A RATE OF 100 F/HR. WITH AN INITIAL P0OL TEMPERATURE AT 120 F AND ONLY ONE RHR TRAIN AVAILABLE FCR'JLK/1433-4/3/80

EVENTS EVALUATED FOR MK II SUPPRESSION POOL TEMPERATURE ANALYSIS o STUCK-0 PEN RELIEF VALVE (SORV) o WITH ONE RHR TRAIN AVAILABLE o SPURIOUS ISOLATION - LOSS OF MAIN CONDENSER (WITH ALL RHR SYSTEMS AVAILABLE) o ISOLATION SCRAM i

o WITH ONE-RHR TRAIN AVAILABLE o STUCK-0 PEN RELIEF VALVE AT ISOLATION

.(WITH ALL RHR SYSTEMS AVAILABLE) o -SMALL BREAK o WITH ONE RHR' TRAIN AVAILABLE o WITH SHUTDOWN COOLING UNAVAILABLE (WITH ALL RHR SYSTEMS AVAILABLE FOR P0OL C00l.ING)

FCR: JLKri434 4/4/80

_. 2 ._

_._.:__m_..___..____..__._______.._.__

SUMMARY

OF ZIMMER RESULTS PRELIMINARY PEAK BULK POOL CASE DESCRIPTION TEMP, F STUCK-0 PEN SRV WITH ONE RHR TRAIN AVAILABLE 179 STUCK-0 PEN SRV, SPURIOUS ISOLATION WITH TWO 179 RHR TRAINS AVAILABLE ISOLATION SCRAM, WITH ONE RHR TRAIN AVAILABLE 181 ,

ISOLATION SCRAM, WITH S0RV 186 SMALL' BREAK, WITH ONE RHR TRAIN AVAILABLE 184 SMALL BREAK, WITH SHUTDOWN COOLING UNAVAILABLE 190 FCR: JLK/1435

.4/4/80 1

- r--,,,,-- , . ...,..-._.,..,-#_ -

4.& -- ,,,, . -. ,e 1+ . ..,,..---..--r .--~,+i.,-.c. e e .. -

^-

,;

ZIMMER PLANT UNIQUE SUPPRESS 10ii POOL TEMPERATURE ASSESSMENT ,

10NCLUSIONS BASED ON THE PRELIMINARY EVALUATIONS PERFORMED

-ON ZIMMERi ZIMMER MEETS THE NRC SUPPRESSION POOL TEMPERATURE LIMITS FOR THE B0UNDING EVENTS EVALUATED, FCR:atx/1436 4/3/80

GENERALIZED ASSUMPTIONS USED FOR P0OL TEMPERATURE ASSESSMENT o ' MAXIMUM SERVICE WATER TEMPERATURE o- INITIAL SUPPRESSION P0OL TEMPERATURE AT MAXIMUM

- NORMAL' TECHNICAL SPECIFICATION LIMIT o DECAY HEAT PER ANS-5 o FULLY CRUDDED RHR HEAT EXCHANGERS o HOT FEEDWATER DUMPED INTO THE SYSTEM TO MAINTAIN LEVEL (FEEDWATER TERMINATED WHEN FURTHER ADDITION WILL RESULT IN REDUCTION OF P0OL TEMPERATURE) o 122.5% ASME RATED FLOW RATE FOR SRV o MINIMUM POOL TECHNICAL SPECIFICATION LEVEL

'o SHUTDOWN COOLING NOT UTILIZED FOR CASES WHERE TWO RHR AVAILABILITY' ASSUMED I

FCR: JLK/1437 4/3/80

+<-

-MASS ENERGY INPUT ASSUMPTIONS .

-SORV AT~ FULL POWER, WITH ONE RHR TRAIN AVATLABLE o

MANUAL SCRAM AT-TP00L = 110 F

-o GRADUAL CLOSURE 0F THE TURBINE CONTROL-VALVES WITH DECREASING REACTOR PRESSURE o- ONE RHR IN POOL COOLING TEN MINUTES AFTER HIGH

-TEMPERATURE ALARM L

.o MAIN CONDENSER REESTABLISHED THROUGH BYPASS SYSTEM TWENTY MINUTES AFTER SCRAM AND-MAINTAINED UNTIL REACTOR VESSEL PERMISSIVE FOR RHR SHUTDOWN COOLING i

o RHR OUT OF P0OL COOLING.WHEN PRESSURE PERMISSIVE FOR

~

RHR SHUTDOWN' COOLING IS REACHED, SIXTEEN MINUTES

FOR RHR TRANSFER FROM POOL COOLING TO SHUTDOWN COOLING, l

FCR 4/4/80

1, MK II MASS ENERGY ASSUMPTIONS SORV AT FULL POWER - SPURIOUS ISOLATION 0-MANUAL SCRAM AT TP00L = 110 F o ISOLATION AT SCRAM WITH 3,5 SECOND MAIN ISOLATION VALVE CLOSURE o .TWO RHRs IN POOL COOLING TEN MINUTES AFTER HIGH POOL TEMPERATURE ALARM o MANUAL DEPRESSURIZATION (IF REQUIRED) INITIATED AT TP00L = 120 F

.o -RHR SHUTDOWN COOLING NOT USED FOR POOL TEMPERATURE ASSESSMENT 4

FCR-  ;

4/3/80

~

~

MASS ENERGY ASSUMPTIONS ISOLATION SCRAM POSTULATED LOSS OF ONE RHR TRAIN J

o ISOLATION. SCRAM AT T = 0 WITH 3.5-SECOND MAIN ISOLATION VALVE CLOSURE

o ONE RHR IN P0OL COOLING TEN MINUTES AFTER.THE' EVENT o WHEN TP00L = 120 F, BEGIN MANUAL DEPRESSURIZATION o RHR OUT OF P0OL COOLING WHEN PRESSURE PERMISSIVE FOR

. 'RHR SHUTDOWN COOLING IS REACHED. SIXTEEN-MINUTE DELAY'FOR-RHR TRANSFER FROM P0OL COOLING TO SHUTDOWN COOLING.

1 l

l

- FCR: JLK/1440-l  : 4/3/80-l i

G (w

• WS---.8'-h +A- mm aP h.id ewm

• We,.=.w M 459e uwgrea t W @ WO 4W -^ -9cI4W9 W,Aem er ww - * -e. _-, -W, pgg,g,p g .g gp e ,,+

MASS ENERGY ASSUMPTIONS ISOLATION SCRAM WITH S0RV o . ISOLATION SCRAM AT T'= 0 WITH 3.5-SECOND MAIN ISOLATION VALVE CLOSURE o' SORY AT T = 0

. o 'TWO RHRs IN P0OL COOLING AT TEN MINUTES AFTER THE EVENT o -WHEN-TP00L = 120 F, BEGIN MANUAL DEPRESSURIZATION o RHR SHUTDOWN-COOLING NOT USED FOR P0OL TEMPERATURE

. ASSESSMENT FCR: JLK/1441L 4/3/80- -

- . . . . .. _ .. . . . . - . - = .

g:;:.  ;

.7 MASS ENERGYJASSUMPTIONS SMALL BREAK'WITH ONE RHR. TRAIN AVAILABLE

- 01 SCRAM AT T = 0 ON HIGH DRYWELL PRESSURE o ISOLATION AT T =-0 WITH 3.5-SECOND MAIN ISOLATION VALVE CLOSURE

- o- ONE RHR IN POOL COOLING TEN MINUTES AFTER HIGH P0OL TEMPERATURE ALARM o WHEN TP00L.= 120 F, BEGIN' MANUAL DEPRESSURIZATION o' RHR OUT 0F-P00L C00 LING'WHEN PRESSURE PERMISSIVE FOR.

RHR. SHUTDOWN COOLING IS REACHED. SIXTEEN-MINUTE DELAY FOR RHR TRANSFER FROM POOL COOLING TO SPJTDOWN COOLING.

FCR:atx/1442-4/3/80-

• 7 @ -

Vs-i-n+'=g i, gv- g .a_wW .eg,4-p s , E4h g Wi 9p,g -w uv.wy.w p ,_- p.,9_,reym-,g,4,p ,,g , ,_,., , _i ,p , .e pp g g. %_,,

MASS ENERGY ASSUMPTIONS SMALL BREAK WITH SHUTDOWN COOLING UNAVAILABLE cr SCRAM AT T = 0 ON HIGH DRYWELL PRESSURE -

o ISOLATION AT T = 0 WITH 3.5 MAIN ISOLATION VALVE CLOSURE o .TWO RHRs IN P0OL COOLING TEN MINUTES AFTER HIGH P0OL TEMPERATURE ALARM

o. WHEN TP00L = 120 F, BEGIN MANUAL DEPRESSURIZATION c- RHR SHUTDOWN COOLING NOT USED FOR P0OL TEMPERATURE I ASSESSMENT:

1 l

l

'FCRiJLK/1443 4/3/80

=r,.-ims __ .4A: 4 e m

(,.. , .Q)- ( k' ' '

A,

.;.>.?' ' -;lL + ~

+

.--y :- elm:.1

'+ =

y .4..' * [ 93... t p,.-: L_gn%

l L, c- ,

._; ; , ,

k..) < , .v_-

, ., 4 t- <- , *

[.- e

• s ';-L'1 ~

, r ev,y L

?

• T_

b. N -

c c. , 1 . .

$ n m 4

.~j v

J i

-* I'

'A'

SUMMARY

OF AVAILABLE TEST RESULTS-

_ . ON'P RFORMANCE OF QUENCHERS AT HIGH SUPPRESSION POOL TEMPERATURES ,.=.

h T

? $ f

?

"t y i t

- +

c l

., 'I

-k,. ; '

4 '

(_

4

.m' .

- 7

. l u

^ ~

O- - - - ;, Q- __

< - i :., ,1 - l

,' \}i_ , * ,I '  ;

p ,*- _, ,- . - - ' '

~

,M'*.

y 3 S- =

.._e.  %' s

.< .]

, d .5 _ . < , - , .

1

, t , sb s

.' + +< t t' . 'l

"'t?-

.c- + < .e c > s.<;; _ u;_ i - -

_9

~ ~

e. ;. ,

, , . l' 4-CONTENTS

' .1. - Title' 2.. Objective:

/3. -Main Questions

4. Approach 5.1 . Chronological- List.of Reports Reviewed

^*6.. Experimental Set-up for Testing Various Hole Patterns-

• 7. - LResults from Tests of Various Hole Patterns

• 8. -Temperature Dependence of Pressure Loading for Five Versions of Perforated Pipe Segments up to 100*C

~ .*9. Important Results from Small-Scale Tests

• 10. . Test: Stand forLPerforated Pipe Experiments

• 11.~ - - Floor- Pressure as a Function of Pool Temperature for

. Perforated Pipe Tests

'*12.  ; Distribution. of Temper ature on the Face of Perforated Pipe Segment at Various Times

• 13. Full-Scale Tests at Brunsbuttel

• 14.: SSES T-Quencher

• 15;. ' Observed Condensation Phases.

16. Schematic of Condensation Tank in SRI Tests

• 17. . Effect .of Mass Flux'on Steam Jet -

• 18.: - Effect 'of'Subcooling on . Steam Jett

• 19. .Results from SRI Tests

~20.-

! Pool Temperature Limit

. 1

~

. ..L .

7

• 21. Va'riation of the Maximum Pressure Fluctuation Amplitudes

~with Pressure Ratio Across the Nozzle in SRI ~ Tests

• 22. Variations of the Maximum Pressure Fluctuation Amplitudes with Pressure Ratio Across the T-Quencher Holes

• 23. Comparison of' Test Results Obtained by SRI and KWU 24.~ Bubble Drift

25. 'Subcooling

26. . Bubble Rise Path

. *27. Theoretically predicted Temperature Variation in the Suppression Pool of SSES

28. . Condensation Rate

. 29. Conclusions 1

-* proprietaty information l

l l

l

, \

OBJECTIVE Assess performance of PP&L T-quencher when saturation temperatures are approached in the suppression pool

ga-esww.suw ymy ,~ ~v i

f:'.

[ I s

-l a

i d

i s

?-

?

(

l a

i MAIN QUESTIONS e Pool Temperature Limit

• Effects of Bubble Drift a

3 3

i I

3: -

1 1

i i

1

t. _ _

t APPROACH I

e Review available results on quencher performance at high pool temperatures e Analyze the results collectively in relation to performance

.. T-quenchers near pool saturation conditions t

3

."4, 4

_ _ ,,, , , . . - ,---.e t,--

CHRONOLOGICAL LIST OF REPORTS REVIEWED Number Date Source Report Number 1 May 1973 KWU (Germany) KWU E3-2593 2 May 1973 KWU (Germany) KWU E3-2594 3 July 1973 KWU (Germany) KWU E3/E2-2703 4 December 1974 Brunsbuttal Power Plant KWU R113-3267 (Germany) 5 June 1975 General Electric GER SR-19 6 October 1975 General Electric NEDE-21078 7 August 1977 Brunsbuttel Power Plant KWU R521/40/77 (Germany) ATW 5 1 g,Lu E l 8 October 1978 General Electric MS984999t> g o o g 9 December 1978 KWU (Germany) R 14/100/78 55E5 10 February 1979 KWU (Germany) R 54/1/79 [ DAE 11 July 1979 SRI International PYC 5881

131PORTANT RESULTS FRO.\1 S3f ALL-SCALE TESTS e Coalescence of bubbles sliould be avoided e Adequate circulation of subcooled water is necessary

s SCHEMATIC OF CONDENSATION TANK IN SRI TESTS n

V Water Tank 36-1/4., (at uniform temperature Viewing and pressure)

Port 1 cm Diameter

" Hole (s)

We Steam Inlet i

POOL TEMPERATURE LIMIT is there a limiting pool temperature above which pressure loads would exceed the values measured during the T-quencher verification tests?

4

BUBBLE DRIFT e is it possible that pool rotation causes large bubbles formed at high pool temperatures to drift into a highly subcooled region and generate excessive pressures as a result of rapid condensation?

l 1

~ -

j , .

SUBCOOLING e Condensation rate strongly depends on the subcooling (subcooling = saturation temperature - local temperature) e An approximately linear increase of saturation temperature is expected with depth 100 C

~

1 m l 23 ft '

107 C 4 Suppression Pool Saturation Temperature  !

l i

e Local temperature depends on the extent of bubble drift due to l i

pool rotation l

l l

9 .

BUBBLE RISE PATH e Maximum pool speed is approximately15 cm/sec e Bubble drift is less than 10 ft (much less than pool perimeter) e Only depthwise temperature variation can influence condensation rate l

i 9 _

I

i l

l l

CONDENSATION RATE e Pool is hotter near the bottom around the quenchers e Changes in local temperature and saturation temperature tend to offset each other e Approximately constant condensation rate is expected

CONCLUSIONS e Near or at saturation conditions, pressures are smaller than those measured in T-quencher verification tests e Unnecessary to assign a limit for suppression pool temperature on the basis of quencher operation e Violent collapse of large steam bubbles due to drift has no practical significance at SSES l

I l

9 -m