ML19318A426

From kanterella
Jump to navigation Jump to search
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:
References
REF-GTECI-A-39, REF-GTECI-CO, TASK-A-39, TASK-OR NUDOCS 8006230007
Download: ML19318A426 (28)
v • d • e


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.

89

  • 2 *
  • 7 t.

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

+1

+<-

-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, 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-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,,+

mm

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 ASSESSMENT:

'FCRiJLK/1443 4/3/80

=r,.-ims

.4A:

4 e

m

.--y :- elm:.1

-;lL +

(

k' A,

(,..

.Q)-

~

.;.>.?'

+

p,.-: L_

.4..'

  • [ 93...

'+

y

=

t gn%

l L,

c-k..) <

.v_-

t-4

[.-

e s

';-L r

~

'1 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

, sb

+

+<

t

. 'l s

t t'

"'t?-

_ u;_ i

_9

.c- + <

.e c s.<;;

~ ~

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

~

..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

\\

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

-ai d

i s

?-

?

(l a

i MAIN QUESTIONS e Pool Temperature Limit

  • Effects of Bubble Drift a

3 3

i I

3: -

1 1

ii 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 g,Lu E 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 (at uniform 36-1/4.,

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?

~

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 Suppression Pool Saturation Temperature 4

l i

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

pool rotation

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

9

-m

Retrieved from "https://kanterella.com/w/index.php?title=ML19318A426&oldid=4790075"