MCP Regulatory Reform Waste Site Cleanup Advisory Committee January 26, 2012 1.
o NUCLEAR REGULATORY COMMISSION .I ADVISORY … · [o,, ' UNITED STATES 8 o NUCLEAR REGULATORY...
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. ___ . . ._ . - [ 'o,, ' UNITED STATES 8 NUCLEAR REGULATORY COMMISSION o 3 .I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS ! % * WASHINGTON, D. C. 20555 %...../ September 11, 1985 ', . . _. . MEMORANDUM FOR: C. Wylie, Chairman, CE System 80 Subcormiittee o ACRS Members G.A. Reed [ FROM: SUBJECT: Attached Morning Report on Palo Verde Incident ' , You are acquainted with my position that the Palo Verde (CE System 80) units had " lean" systems as far as assured core cooling was concerned and , that my opinion favored the inclusion of a PORV system. (ACRS letters in . the past have expressed concern about the noninclusion of PORVs in the i System 80 design.) The attached Morning Report of August 25, 1985 indi- cates to me that reliance by CE on Auxiliary Feed Pumps (in the configura- tion at Palo Verde) for the accidents of tube rupture and steam ifne breaks (wherein.the need for primary depressurization and assured core cooling becomes complicated) should be further reviewed on an urgent basis. In my opinion, this Palo Verde incident may also be a precursor indicating a need for ACRS to reflect further on my proposed primary blowdown -- redundant in principle -- concepts for some PWRs. Attachment: as stated cc: J. Flack i I | , l , 8604030593 860311 PDR FOIA SCOTT 86-4 d PDR , . _
Transcript of o NUCLEAR REGULATORY COMMISSION .I ADVISORY … · [o,, ' UNITED STATES 8 o NUCLEAR REGULATORY...
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UNITED STATES
8 NUCLEAR REGULATORY COMMISSIONo
3 .I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS! % * WASHINGTON, D. C. 20555
%...../ September 11, 1985
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MEMORANDUM FOR: C. Wylie, Chairman, CE System 80 Subcormiitteeo ACRS Members
G.A. Reed [FROM:
SUBJECT: Attached Morning Report on Palo Verde Incident'
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You are acquainted with my position that the Palo Verde (CE System 80)units had " lean" systems as far as assured core cooling was concerned and,
that my opinion favored the inclusion of a PORV system. (ACRS letters in. the past have expressed concern about the noninclusion of PORVs in thei System 80 design.) The attached Morning Report of August 25, 1985 indi-
cates to me that reliance by CE on Auxiliary Feed Pumps (in the configura-tion at Palo Verde) for the accidents of tube rupture and steam ifne breaks(wherein.the need for primary depressurization and assured core coolingbecomes complicated) should be further reviewed on an urgent basis.
In my opinion, this Palo Verde incident may also be a precursor indicatinga need for ACRS to reflect further on my proposed primary blowdown --redundant in principle -- concepts for some PWRs.
Attachment: as stated
cc: J. Flacki
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MORNING REPORT - REGION V .
DATE: AUGUST 25, 1985 *
REGIONAL ACTION
FACILITY NOTIFICATION ITEM OR EVENTFOLLOWUP PER MC 25t5
BECHTEL NOTIFIED THE LICENSEE THAT AN ENGINEERING'ARIZONA PUBLIC FAX FROM SENIOR EVALUATION HAS SH0HN THAT A MAIN STEAM LINE BREAK
SERVICE COMPANY RESIDENT INSPECTOR IN THE MAIN STEAM SUPPORT STRUCTURE COULD RESULTPVNGS 81 IN TH0 AUXILIARY FEEDHATER (AFH) PUMP ROOMS BEING
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DN 50-528 7 PRESSURIZED TO APPROXIMATELY 20 PSIG AND 260 F 'eDEGREES. THE LICENSEE HAS DECLARED BOTH PUMPS/ 7- 'TC).'IINOPERABLE BASED ON THE PUMPS AND ASSOCIATED-; ,- INSTRUMENTATION NOT BEING QUALIFIED FOR THE REVISED,
PALO VERDE 1 HILL'7 -
A*SUMED ENVIRONMENTAL CONDITIONS.*
# ROMAIN IN MODE 4 UNTIL CONDUIT SEALANT (HHICH IS THE-
c eul7dIdd 'I)[/ '' MEANS BY HHICH THE STEAM HOULD BE COMMUNICATED INTO' '
jf
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[gg'4[/ THE AFH PUMP ROOMS) IS UPGRADED TO PREVENT LEAKAGE.,q,,,,[,[i 4 j~. WI
/j . 3FOLLOWUP PER MC 2515
THE LICENSEE N/.S NOTIFIED BY COMBUSTION ENGINEERINGARIZONA PUBLIC FAX FROM SENIOR THAT AT PALO VERDE 1 THE VARIABLE SETPOINT (VSP)
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SERVICE COMP RESIDEyT INSPECTORCARDS ASSOCIATED HITH THE VARIABLE OVERPDHER TRIP
PVNGS 81 j (V0PT) RATE CIRCUIT IS SUBJECT TO RANDOM SETPOINTDN 50-528 /) FLUCTUATIONS AT VARYING POWER LEVELS. IF A RANDOM'
/SETPOINT INCREASE HERE TO OCCUR SIMULTAMEOUS HITH AsCONTROL ELEMENT ASSEMBLY EJECTION, THE ACCIDENT-
ANALYSES MAY BE VIOLATED. THE UNIT IS CURRENTLY-
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SHUTDOHN AND HAS BEEN SINCE JULY 24, 1985, TO PERFORMVARIOUS MAINTENANCE ACTIVITIES. THE LICENSEE HAS,
MODIFIED THE VSP CARD IN ACCORDANCE NITH CERECOMMENDATIONS TO PREVENT A SETPOINT FLUCTUATION.OPERATIONAL RESTRICTIONS PROPOSED BY CE HILL ALSD BEIMPLEMENTED UNTIL THE MODIFIED CIRCUITRY HAS BEENTESTED.
PDTENTIAL 50.55(E) AND PART 21: FOLLOWUP PER MC 25f2ARIZONA PUSLIC TELEPHONE CALL FROM
CE HAS IDENTIFIED MONCONFORMANCES CONCERNINGSERVICE COMPANY LICENSEE AT 2:00 PM4
STAINLESS STEEL FLEXIBLE CONDUIT ON CE SUPPLIEDPVNGS 828S DN 08/21/85 INSTRUMENT RACKS AS INSTALLED IN UNIT 2. THESE
NONCONFORMANCES INCLUDE VIOLATION OF MINIMUM SENDDN 50-529 ..
- 50-550 RADIUS CRITERI A, DAMAGED CONDUIT, LOOSE FITTINGI NUTS, ONE DISCONNECTED END FITTING. (DER 85-28)'
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ANPP/NRC MEETING T0 DISCUSS
PVNGS AUXILIARY SPRAY CAPABILITY AND.
THE STARTUP TESTING EVENT OF SEPTEMBER 12, 1985
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i I. INTRODUCTION J. G. HAYNES.
V. P. - NUCLEAR PRODUCTION
- II. SEPTEMBER 12, 1985 EVENT 1) R. E. G0UGE
UNIT 1 DAY SHIFT SUPV.,
2) D. D. SWAN,,
UNIT 1 ASST. SHIFT SUPV.. .
: III. AUXILIARY SPRAY DESIGN / T. F. QUANI
LICEf1 SING COMMITMENTS LICENSING SUPERVISOR|; IV. EVEllT EVALUATION T. F. QUAN '
V. CONCLUSION J. G. HAYNES
V. PP- NUCLEAR PRODUCTION:
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CONDITIONS PRIOR TO EVENT OF 9-12-85
1. REACTOR AT 53% FULL POWER'
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2. TURBINE GENERATOR ONLINE AT 585 MWe
3. PREPARING FOR 50% LOSS OF LOAD TEST
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PURPOSE OF 50% LOSS OF LOAD TEST:1
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1. DEMONSTRATE THAT THE PLANT CAN ACCOMMODATE
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A LOAD REJECTION FROM 50% POWER
2. VERIFY THAT THE TRANSIENT DID NOT IlllTIATE
A REACTOR POWER CUTBACK
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SEQUENCE OF EVENTS
2208 TEST INITIATED BY REMOTE MANUAL OPENING OF BOTH
GENERATOR OUTPUT BREAKERS. (TURBINE-GENERATOR
FLUCTUATIONS)
2209 REACTOR TRIP (FLOW-PROJECTED DNBR TRIP FROM CPC)
2209 TUR3INE TRIP (CAUSED BY REACTOR TRIP)
2215 NON-SAFETY RELATED AUXILIARY FEEDWATER PlNP STARTED
2217 ATMOSPHERIC DUMP VALVES (0NE ON EACH STEAM GENERATOR)
OPENED 3%
2218 MAIN STEAMLINE DRAINS AUTOMATICALLY RE0PENED UPON
RESTORATION ON NON-1E ELECTRICAL POWER
2222 SIAS AND CIAS INITIATED (1837 PSIA; 540 F)
SIAS AND CIAS ACTUATIONS WERE VERIFIED AS PER DESIGN
WITH HPSI INJECTING APPR0XIMATELY 75 GPM TO EACH COLD
LEG#
2223 NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO
COMPLICATED REACTOR TRIP AND INITIATION OF A SIAS
2225 AUXILIARY OPERATOR RE-ENERGIZED MOTOR CONTROL CENTER
NHN-M-72 UNDER CONTROL ROOM DIRECTION (RE-ENERGIZED
CHN UV-501, VCT OUTLET AND UV-536, RWT HIGH SLCTION
TO CHARGING PUMPS )
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SEQUENCE OF EVENTS (CONT.)
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2237 CHARGING HEADER LOW FLOW ALARM (40 GPM),
INTERMITTANT CHARGING HEADER PRESSURE ALARMS,
FOR THE NEXT 43 MINUTES, OPERATORS WERE
ATTEMPTING TO REESTABLISH CHARGING PUMP
SUCTION FROM:
(1) RWT HIGH SUCTION VIA CH UV 536
(2) RWT LOW SUCTION VI A CHN V 327
; (3) RWT HIGH SUCTION VIA UV 532 -- BAMP-
CH 514 TO THE CHARGING PUMPS (AFTER
NON-1E POWER RESTORATION)> '
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; 2320 REESTABLISHED CHARGING FLOW WITH TWO CHARGING
PLMPS INJECTING 44 GPM TO RCS
2358 RESET SIAS AND CIAS (RCS PRESSURE AND INVENTORY |
STABLE AND UNDER CONTROL).
0102 9/13/85 TERMINATION OF NOTIFICATION OF UNUSUAL.,
EVENT
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CHRONOLOGY OF AUXILIARY SPRAY
DESIGN / LICENSING CRITERIA
PRE RSB5-1 ORIGINAL DESIGN
i 1978 RSB5-1 ISSUED, SYSTEM UPGRADED TO MEET
| CLASS 2 PLANT REQUIREMENTS -- REDUNDANT
AUX SPRAY VALVEB
2ND OTR,.
: 1981 0440.6 SUBMITTED BY THE NRC ON CESSAR/
! PVNGS DOCKETS A6 'l # * "'fW5m an; .ut h: mb,, -
i B> beva c.y^^%(44giS 10/8/81 CESSAR RESPONSE TO 0440.6 SUBMITTALs
i 8 cu,a L.Z o.M c.ma w y'.t )st vp'u h pp mi r 10/29/81 CESSAR COMMITS TO UPGRADE CH-141 AND 1t & " La |
y CH-501 w y~ g t uw y p w.-p,~ vu %,,'
E ik sbj S 11/3/82 # s" SAFETY GRADE AUXILIARY SPRAY SYSTEM" h** ,
7/28/83 - "SA'FETY-RELATED METHOD FOR RAPID} [<<y'1.. z
h{'s DEPRESSURIZATION ... CONSISTENT WITH ?|'
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4., s THE RECOMMENDATIONS OFi RSB5-1 } ,.,
U%:. . t. s. - STATED CEN-239 APPLICABLE TO PVNGS'
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CHRONOLOGY OF AUXILIARY SPRAY (CONT.),
~ Ma| 4/27/84 - NRC LETTER REQUIRiflG AtlALYSIS ASSUMitlG IN''
%% %g.
FULL OPEf! ADV FAILUREf N $%srz uAc u k %.u 9 4 hk 05E 4 %
w )%aF, 7t2 NRi !ES 9/1/84 - PLANT-SPECIFIC SGTR + LOP + FAILED
Y.'bca-EE ADV ANALYSIS SUBMITTED
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ORIGINAL AUXILIARY SPRAY CRITERIA
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! OPERATOR CONTROL OF THE RCS PRESSURE DURING
iFINAL STAGES OF C00LDOWN (WHEN PRESSURE LESS THAN
| REQUIRED FOR RCP) AND FOR C00LDOWN OF PRESSURIZER.!
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CURRENT AUXILIARY SPRAY CRITERIA
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| SAFETY GRADE PLANT C00LDOWN CONSISTENT WITH
| THE GUIDANCE OF BTP RSB 5-1. FOR CLASS 2 PLANTS:
| OPERATOR ACTIONS OUTSIDE CONTROL ROOM <tv g/ni o 3
o OPERATOR ACTIONS INSIDE CONTAINMENT N %INAFTER SSE
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o- REMAINING AT HOT STANDBY UNTIL MANUAL
| ACTIONS OR REPAIRS ARE COMPLETED.
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|- Alg SPRAY SYSTEM
ACTIVE COMPONENTS
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| SPRAY VALVESi
LOOP ISOLATION VALVES
CHARGING PUMPS [ y f 7 A )!
DETAILED DESCRIPTION IN RESPONS:'. TO 440.6
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1: AUX SPRAY SYSTEM
i CESSAR vs PVNGS!
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o PVNGS liAS REMOVED INTERNALS FROM.
[ MAIN SPRAY BACKFLOW CHECK VALVEi.
o PVNGS HAS MODELED AUX SPRAY IN;s.
) TRANSIENT ANALYSIS OF CERTAIN SG
1 TUBE RUPTURE TRANSIENTS3
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AUX SPRAY USE IN
SAFETY ANALYSES
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e DURING LONG-TERM C00LDOWN PHEE FOLLOWING
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EVENT:
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j CESSAR-F PVNGS-FSAR (0RIGINAL):
ALL WITH LOP ALL WITH LOP
/ GL '' bs
T;
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e DURING SHORT-TERM MITIGATION. 1
PHASE OF EVENT: b" '.
%/CESSAR-F PVNGS-FSAR(AMEND 14) $gg9 |.,.& t,. 1
NONE SGTR/ LOP / FULL OPEN (5 \' i
[h .,. YM\ FAILED ADV y.Qc ?-Ng '' ..; N(, |c.N !
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PVNGS-FSAR (APPENDIX 15A):
SGTR ANALYSIS RESULTS
:SA R EST MATED *EYf31 IIE TilV Kfri DOSE THY (U U UJ5E'
(SECONDS) LREM) UREM)
hubKOPENADV 0 0 0
. LOP 51 0 0
bhACT/AFFECTED) 122/132 0 0
ADV OPENS 460 0 01
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1MSIS 513
SIAS 581
AFW OVERRIDE 655
AUX SPRAY 1015 115 115*,
H!5?eReD 1385 182 18s-
2 JR DOSE !a -AB 7200 200 210* ;
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EVENT EVALUAHOR
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LTflL1 - LOSS OF .VCT LEVEL
| COMPENSATORY MEASURES - tiONITOR REFERENCE LEG WATER LEVEL
4 G % 6 y - ALIGN REFUELING WATER TANK TO
CHARGING PUMP SUCTION PROMPTLY
ON LOSS OF POWER * %.4- INSTITUTE PROCEDURAL CAUTIONS k
ON RESTART OF CHARGING PLNPSt
ITEM 2 - LOSS OF POWER TO CVCS VALVES (501, 536);
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COMPENSATORY MEASURE - ALIGN REFUELING WATER TANK TO!
CHARGING PUMP SUCTION PROMPTLY
ON LOSS OF POWER
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[ Page 1 of 2, Sequence of Events,j PVNGS Unit 1
September 12, 1985 gg$ ,,,d
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Prior to neart of the load rejection test. 525 KV BKR FL 915 (one of twomain generator output breakers) was opened per the test procedure.
4; .IIG DESCRIPTION; 22:08:29 Generator output breaker PL 918 was opened from the{ control room to start the test. '
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j 22:08:30 Fast closure of the main turbine control and-
: intercept valves.1 ,
! 22:08:31:254 Turbine trip "first in" indication was "No ESTV, Press trip" (no electric trip solenoid valvej pressure) - turbine trip was not expected to occur,I troubleshooting ongoing..
1 22:08:53:721 Low DNBR trip on Channel A - CPC projected low flov, causing DNER
22:08:53:738 Low DNBR trip on Channel B - reactor trip signal
22:08:53:796-808 Channel A - D trip breakers opened;
22:09:45 TWPI '*A" tripped on low control ofi pressure. The '
control oil pump is supplied from nonesuential power,
22:10:51 Main Eenerator exciter tripped
22:10:53 circulating water and condensate pumps trip - testconfiguration prevented fast transfer.
22:10:58 Main steam line drain valves are msnually shut - autoopened on turbine trip, per design
22:15:10 Nonclass AFV pump started to maintain SC levels.22:17:42 Manually opened ALV on SC2 to dump steam to>
atmosphere to prevent degrading vacuum and insure,
adequate delta T for natural circulationf
22:|8:36 ADV on SG1 manually opened
22:19:07 ADV on SC2 manuaAly closed
22:19:37 Main stean line low point drain valves openautomatically when nonessential power is restored'with turbine trip sigcal present
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22:21:07 ADV on SC2 manually reopened
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[ Sequence of Events{ PVNGS Unit 1: September 12, 1985!
! 22:21:38 SIAS/CIAS on low pressurizer pressure (1837 psig).Nonclass AFW pump shed, "B" AFW pump starts but is
i not used to add water due to SG 1evels being in| normal band. Pressurizer prestare low point is 1819
psig.i
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} 22:23:28 ADVs manually closedt .
| 22:23 Unusual Event declared by S/S based on Rx trip and-
SIAS/CIAS'
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| 22:33:01 Established RCP seal injectioni
i 22:33:47 Established charging flow to ECS
Approx 24:00 Pressurizer LVL back in norcal band L
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Approx 00:50 Started RCPs
01:03 Terminated Unusual Event'
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175517|
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204,6 TIME (SEC ) -) 1806,6
P'Est ifCS TEST 501055 Of LOAD M6 ElFFETd SSCWSECTESTDATE: 12-SEP-85 SIMIIIE: 21:52:33,6 oP106 HINI M 1819,65 PSIA F106 HAXI M 2363,21 FSIA
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Ai 1684.6 SEC AT S24.0SEC'
ilE: 228,571SEC/ DIVISION F106 67,315 PSIA / DIVISION
P0INTS PL0iiED FFaiEVERY 16 SCAWS,
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