ML19318A426
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) | |
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