ML20214P612
| ML20214P612 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Oconee, Indian Point, Columbia, Diablo Canyon, Maine Yankee, Zion, 05000000 |
| Issue date: | 05/27/1987 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-87-014, OREM-87-14, NUDOCS 8706030456 | |
| Download: ML20214P612 (19) | |
Text
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MhY 2 71937 MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment Fh0M:
Wayne Lanning, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON MAY 12, 1987 - MEETING 87-14 On Tuesday, May 12, 1987, an Operating Reactors Events meeting (87-14) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events which occurred since our last meeting on May 5,1987. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. provides a summary of those presented events that will be input to NRC's performance indicator program as significant events.
0%imi*>lFadS?:
Vayne Lanning, Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION Central File:
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MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Wayne Lanning, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON MAY 12, 1987 - MEETING 87-14 On Tuesday, May 12, 1987, an Operating Reactors Events meeting (87-14) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on evonts which occurred since our last meeting on May 5,1987. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. provides a sumary of those presented events that will be input to NRC's performance indicator progran; as significant events.
\\ kl tynh L nning, Ac Chief Events Assessmen Bran h Division of Oper tional Events Assessment 4
Enclosures:
As stated cc w/ Encl.:
See Next Page 1
- _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ -, _ _.,,. _ _. _ _ _ _ _.. ~
Those Listed -
cc:
T. Murley J. Norris J. Sniezek R. Samworth R. Starostecki H. Schierling J. Taylor C. Trammel E. Jordan S. McNeil E. Beckjord M. Slosson W. Russell, Reg. I J. Neighbors J. Nelson Grace, Reg. II P. Sears B. Davis, Peg. III G. Gears R. D. Martin, Reg. IV H. Pastis J. B. Martin, Reg. V S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan F. Schroeder L. Shao J. Partlow B. Grimes F. Congel H. Miller E. Weiss S. Black T. Martin, EDO F. Miraglia E. Herschoff R. Hernan i
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e 6
ENCLOSURE 1 LIST OF ATTENDEES OPERATING PEACTORS EVENTS BRIEFING (87-14)
MAY 12, 1987 NAME DIVISION NAME DIVISION P. Starostecki NRR R. Bosnak RES G. Holahan NRR F. Miraglia NRR A. Thadani NRR B. Clayton OED0 E. Rossi NRR J. Heltemes AEOD S. Rubin AEOD T. Speis RES C. Berlinger NRR L. Shao NRR J. Richardson NRR L. Spessard AE0D B. Grimes NRR T. Novak AEOD B. Boger NRR G. Murphy OPNL M. Slosson NRR R. Hernan NRR W. Beach NRR R. Scholl NRR D. Basdekas RES 4
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ENCLOSURE 2 OPERATING REACT 0PS EVENTS BRIEFING 87-14 MAY 12, 1987 ZION 1 MSIV OPENING / INADVERTENT SAFETY INJECTION Wt;P-7 WATEP IM STEAM LINE DIABLO CANYON LOSS OF RHR (UPDATE)
CALVERT CLIFFS 2 CRACKED PIPE IN SHUTDOWN COOLING SYSTEP OTHER EVENTS OF INTFPFST INDIAN POINT 2/3 SINGLE FAILURE IN AUX FEEDWATER SYSTEM PAINE YAPKEE POTENTIAL FAllllPF 0F CCW FOR EDG BP.0WNS FERRY 1/3 PUI.TIPLE CHECK VALVE Fall.!!RES OCONEF HEAT EXCHANGER FOULING (l!PDATE) i
1 t
ZION 1 - MSIV OPEPING/INADVEPTENT SAFETY INJECTION PROBLEM FAILURE TO FOLLOW PPOCEDURES RESULTFD IN SilDPEN OPENING OF MSIVs AFD It!ADVEPTENT SAFETY IPJFCTION CAUSE MISCOMMUNICATION SIGN!FICANCE LOST AUTOMATIC / REMOTE STEAM LINE ISOLATION CAP /PILITY WHILE IN HOT EHUTDOWN DISCUSSION ON APRIL 30, 1987 UNIT IN HOT S/D FOR REPA!R ON TlIPBIPE GENERATOP; MSIVs CLOSED MSIVs ARE FYDRAULICALLY CONTROLLED AND SOLEN 0 IDS MUST BE ENEPGIZED TO CLOSE MSIVs SOLENDID CANNOT BE KEPT ENERGIZED MORE THAN 7 DAYS PER YEAR TO PAINTAIN COMPLIANCE WITH E0 CRITERIA WHEN MSIVs NEED TO BE CLOSED FOR A LONG TIFF, LICENSEE OPENS BREAKER TO THE ELECTRIC MOTOP OPERATING THE PYDRAllLIC PIlf1P DEFORE DEENERG! ZING THE SOLEN 0 IDS TO THE DPATF VALVES DUE TO COMVUNICATION ERROR BETWEEP SHIFT COPTROL ROOM ENGINEER AND EQUIPMENT OPERATOR, THE TRIP S0LEMOID FUSES WERE PULLED BEFORE OPENING PREAKER TO MOTOP DELTA P SIGNAL PETWEEN S/G LOOPS ACTUATED SI l
FOLLOWUP LICENSEE H/S INSTALLED SHIELDS AND WARNING LAPELS ON FUSE ECXES CCPTACT:
D, OUDIN0T
WNP-? WATER IN STEAMLINE PROPLEM SCRAM WITH COMPLICATIONS CAUSE OPERATOR ERROP SIGNIFICANCE WATER IN STEAMLINES OPERATION DIFFICULTY DUE TO C0flTATFFFNT ISOLATION
- DISCUSSION FAILFD FUSE CAUSED MAXIMllM FEEDWATER DEMAND: FW PUMPS TRIPPED OF LOW SUCTION PRESSURE ANTICIPATORY MANUAL SCRAM: RV LEVEL 2 INIT!ATED HPCS, RCIC, CONTAINMEf!T ISOLATION, ATWS RECTRC PUMP TRIPS, AND SEPVICE WATER SYSTEM (LOAD SHEDDING)
IMPP0PER FEEDWATER ALIGNMFNT CONTRIBUTED TO OVERFILL OF RV
(+17, 34, 169 MINS AFTER SCRAM)
HPCS 8 PCIC ISOLATED ON HIGH LEVEL; P'RESSURE/ WATER RELTEF TilRU SRVS OPERATOPS PRE 0CCUPIED WITH REESTABLISHING CONTAINMENT COOLING STEAMLINES FLOODED PREVIOUSLY (LER 86-25) BY CONDENSATE B0OSTER PUMPS A-47 EVALUATED DVERFILL FOLLOWUP ISOLATION OF CONTAINMENT COOLING Fl!NCTI0f!
ISOLATION OF FEEDWATER SYSTEM ON HIGH RV LEVEL PEPORTING REQUIREMENTS (ESF ACTUATION)
OPERATOP TRAINING / PROCEDURES HYDRODYNAMIC EFFECTS (WATER HAPMER, WATER IN SRV, THERMAL EFFECTS)
DLAPLO CAf! YON LOSS OF RHR FOLLOW UP ACTIONS OWNEPS GROUP PEGULATORY RESPONSE GR0l'PS (3) HAVE BEEN INFORMED OF THE EVENT AND NPC CONCEPNS, PESPONSES PUE 5/.11/87 PLANTS PLANfl!NG TO SHUTDOWN DURING THF NEXT SIX (6) WEE HAVE BEEN IDENTIFIED PROJECT PANAGERS WILL BE BRIEFED AND THEY WILL BRIEF FFSIDENT INSPECTORS AND LICENSEES DURING WEEK OF 5/))/87 DOG AND PONY SHOWS IN PEGIONS (EXCEPT REGION V),
REG 10?'S I 8 III PITHIN 2 WEEKS INFORMATION NOTICE BEING PREPAPED FOR 5/15/87.
TARGET - ISSUE BY 5/29/87 A 50,54(F) LETTER BEING PREPAPFD FOR ISSUANCE 5/22/87
CAIVFRT CLIFFS 2 - CRACKED PIPF !N SHUTDOWN COOLING SYSTFM PROBLEM LEAV FROM A REllEF LINE IF THE SHUTDOWN COOLING SYSTEM (SDCS) cal'SE CRACKED PIPE SIGNIFICAPCE THE LEAK AFFECTS BOTH TRAINS OF THE SDCS DISCUSSION THE UNIT llAS DEEN SHUT DOWN SINCE 3/14 THE LEAK RATE WAS 0.3 GPM A LEAK llAD OCCURRED AT THE SAME LOCATION EARLIEP IN THE PRESENT CL'TAGE, WAS REPAIRED, AND A SUPPORT !!AD BEEN ADDED TO REDUCE VIBRATION TO REPAIR THE LEAK, DECAY HEAT REMOVAL WAS PROVIDED BY AL10NING A CONTAINMENT SPRAY Pl'MP THROUGH A St!UTDOWN HFAT EXCHANGER TO THE SUCTION SIDE OF AN llPSI PUMP THE CRACK APPARENTLY STARTED IN THE HEAT AFFECTED ZONE OF A WELD, WAS DIPECTED AT A 45 DEGREE ANGLE FROM THE WELD, AND EXTENDFD 1 INCH Tilt PIPE MATERI AL IS 1/2 INCH B-36 SA 382 FOLLOWUP EAD WILL OBTAIN APPITIONAL INFORMATION
. 1NDIAN POINT 2 & 3 - POTENTIAL SINGLE FAILUEE IN Al!Xill ARY FEEDWATFR SYSTEM PPORLFP POTENTIAL SINGLE FAILURE IN THE INDIAN POINT 2 8 3 (IP2, TP3)
AUXILIARY FEEDWATEP (AFW) SYSTEMS CAUSES LOSS OF BOTH MOTOR DRIVEN AFV PUMPS (MDAFWPi, CAUSE RELAY FAILURE PREVENTS AUTO START OF MDAFPP SIGNIFIGANCE UNANALYZED SCENARIO PLACES UNITS OliTSIDE FSAR ACCIDENT ANALYSES POSSIBLE GENEPIC IMPLICATIONS
- DISCUSSIOM QA Al!DIT OF MAIN FEEDWATER (MFW) APD AFW SYSTEMS AT IP2 SUPFACED POTENTIAL SINGLE FAILURE.
TWO SEP. IFS PEDl'NDANT RELAYS, ENERGlZED TO CPEN ON SI, ELOCK AllT0 START SIGNAL TO BOTH AFV MOTOR DRIVEN PUMPS FACIL'TATING THEIP LOADING BY SAFEGUARDS SF0VENCER.
THESE RELAYS APF PART OF AFW SYSTEM'S ORIGINAL DESIGN, FAILitPE OF EITHER RELAY (RE0lilPING CONTINUOUS HOT SHORT) WOULD INHIEIT A VALID AUTO STAPT SIGNAL TO BOTH PUMPS ON LOP LOW STEAM GENERATOR LEVEL OR LOSS OF MFW.
FAILURE WOULD NOT AFFECT MANUAL. START OF PilMP MOTORS.
AFW TilRBINE DRIVEN PUMP NOT AFFECTED, (IP2 FSAR ACCIDENT ANALYSIS TAKES NO CREDIT FOR TURBINE DRIVEN PUMP),
SIMILAR, THOUGH NOT IDENTICAL PROBLEM, IDENTIFIED AT IP3, IF BFP RELAY FAILS, HALF 0F SIGNAL RE0lllRED TO START BOTH AFW PUMPS r
ON SG' LOW l.0W LEVEL OR LOSS OF MFW WILL NOT DEVELOP, MANUAL STAPT AND INITIATION ON SI SIGNAL. WILL NOT BE IMPACTED, LATEST INFORMAT!0N INDICATES IP3 MAY NOT ALTER AEW LOGIC DESIGN, LICENSEE IS EVALUATING, FOLLOWilP EAB PREllMINARY SURVEY HAS NOT IDENTIFIED OTHER PLANTS W!TH PROBLEM.
IP2 LICENSEE HAS MADE CIRCUIT MODIFICATIONS, PECOMMEND FOLLOWUP FOR IP3, PEGION I HAS LEAD RESPONSIPILITY FOR REVTEP AFD HAS PPEPARED A DRAFT IFF0PPATION NOTICE FOR 110 REVIEW.
WESTillGH0!'Sr IS LOOKING AT REPORT!PILITY UNDER PART 21, 50.59, AND 50,55E,
f,AINE YANVEE - POTENTIAL FAILURE OF CCW TO EKEPGENCY DiFSEL GENERATORS (EDGs)
PROBL_Ef.
A POTENTIAL EPEAK IN A NON-SAFETY GRADE FIRE WATEP LINE COUPLED WITH LOSS OF 0FFSITE POWEP C0llLD CAUSE LOSS OF EDP C001.ING.
CAUSE SINGLE AIR OPERATED VALVES VHICH Fall OPEN ON LOSS OF AIP SEPARATE CCW FROM THE FIRE WATER LINES, sir.NIFICANCE POTENTIAL FOR LOSS OF EMERGENCY AC POWER, DISCllSSION L!CENSEE DISCOVERED A POTENTIAL FAILURE MODE FOR BOTH TRAINS OF CCW TO THE EDG C00LEPS.
EITHEP. THE CCW OR THE FIRE WATFR COOLING (FWC) SYSTEM CAN SUPPLY THE COOLERS.
THE FWC SYSTEM IS NORMALLY ISOLATED FROM THE COOLERS BY AIR OPERATED VALVES WHICH FAIL OPEF, LOSS OF SERVICE AIR COUPLED WITil A RREAK IN THE FWC PIPING COULD CAUSE ALL CCW TO BOTH EDG COOLERS TO BE LOST, A RELATED PROBLEM WAS DISCOVERED AT MAINE YANKEE ON Jllt!E 25, 1985 AS PART OF A SAFETY SYSTEM DESIGN REVIEW, A SIMILAR PROBLEM WAS DISCOVERED FOR HADDAM NECK (VALVES ELOCKED OPEN PLUS PRA STUDY) NOVEMBER 1, 1985, A DFSIGN DEFICIENCY IN EMERGENCY DIESEL OPERAT!0?' WAS DISCOVERED AT H.B. ROBINSON (EVENT 8550) MAY ), 1987.
FOLLOWUP THE LICENSEE IS EVALUATING PERMANENT CORPECTIVE ACTION TO Br, COMPLETED DEF0PE STARTUP (BLOCKING FWC ISOLATION VALVES CLOSFP),
NRR ACT10PS PESULTING FROM AF0D CASF STUDY (C701)
LETTER TO RES PE0llFSTING REVISION TO GI-43 AFD PEPRIORITIZATION INF0PMATION NOTICE TO ENSURE FPGAD DISSEMINATION OF CASE STUDY FINDINGS
BROWNS FFRPY - 1 AND 3 MULTIPLE CHECK VALVE FAILURES IN EECVS PROBLEM 24 CHECK VALVES FAILED IN OPEN POSITION IN THE EMEPGENCY E0lllPMENT COOLING WATER SYSTEM CAllSE CORROSION OF CARBON STEEL CHECK VALVES SIGNIFICAFCE COULD AFFECT LPCS ROOM COOLERS FOR UNITS 1 AND 3, RHR SEAL AND RHR ROOM COOLERS FOR llNIT 3 DURING DP.A CilECK VALVE FAILURES CAUSE LOSS OF SEPARABILITY OF EECWS TPAINS
[fNKNOWN HOW LONG CONDITION EXISTED DISCllSSION EECW SYSTEM SERVICES EDGs, RHR, LPCS, CONTROL ROOM - AC, OTHERS FECWS KEPT PUNNING DURING N0PPAL OPERATION BUT ONLY PE0VIPED TO OPERATE DURING DBA EECWS COMPRISED OF TWO " INDEPENDENT" LOOPS VHICH FEED COMM0F SUPPLY HEADERS TO FOUIPMENT AND ROOM C00LFPS CHECK VALVES PROVIDED TO PREVENT CROSS FLOW FROM ONE LOOP TO THE OTHER l
Dl! RING FIRST TIME SURVEILLANCE TO MEET ASME SECTION XI VPICH PF0l!!RES,1NTERNAL INSPECTION, 24 CHECK VALVES F0ltFD FAILED OPEN l
(8 VALVES AFFECT UNIT 1 SERVICE, 16 VALVES AFFECT UNIT 3 SERVICE) l FAILURE OF'EECWS PUMPS IN ONE TRAIF COMDINED WITH CHECK VALVES l
FAILED OPEN COULD CAUSE LOSS OF COOLING TO AFFEC.TED EQUIPPENT i
FOLLOWUP l
LICENSEE PLANS TO INSTALL STAINLESS STEEL VALVES AS REPLACEMENTS LICENSEE WILL INVESTIGATE THE POSSIBILITY OF USING EXISTING TEST l
DATA TO CHECK FOR REVERSE FLOW THP0 UGH CHECK VALVES 1.lCENSEE IS EVALUATING OTHER SYSTEM FOR SIMILAR PROBLEM (S)
J L
OCONEE HEAT EXCHANGER FOULING PROBLEM:
REDUCED HEAT TRANSFFP CAPABILITY IN LOW PRESSURE SERVICE WATER, LOW PRESSURE INJECTION AND REACTOR BUILDING COOLING SYSTEMS CAUSE:
LAKE SEDIMENT DEPOSITED IN HEAT EXCHANGERS SIGNIFICANCE:
SAFETY EQUIPMENT INCAPAPLE OF PERFORMING DESIGN FUNCTION PEOVESTFD ACTIONS:
DETERMINE FHAT OTHER PLANTS ARE DOING AB0l!T HEAT EXCHANGE FOULING WHAT ACTIONS HAS INP0 TAKEN WHAT ACTIONS HAS NPC STAFF TAKEN A)
GENERIC C0KMUNICATIOMS B)
TEPPORARY INSTRUCTIONS FINDINGS:
STAFF ISSUED BULLET'.N 83-03 STAFF ISSUFD IF P3-21 AND IN 86-96 INF0 ISSUED SOER 84-01, RECOPPENDED A)
ONE (31 DESIGN CHANGE
B)...THREE (3) PROCEDllPAL CHANGES C)
ONE (1) INSPECTION STAFF ISSUED TEMPORARY INSTRUCTION 2535/77 REGARDIUC TNDi!STPY RESPONSE TO INP0 RECOMPENDATIONS IN SOER 84-01 HEAT EXCHANGER F0llLING IS A SUBJECT OF GI-51, TO EE CONCLUDED BY PES WITHIN SIX (6) MONTHS MEMO FROM R BAER TO E JORDAN, 3/2/87 REPORTED THAT 50, 0F 5
~
PLANTS HAVE IMPLEMENTED INP0 RECOMMENDATIONS (TI 2515/77 RESPONSE)
INP0 SENT EVALUATORS TO 68 SITES (95 PLANTS)85-907. HAVE SATISFACTORILY IMPLEMENTED RECOMMENDATIONS IFP0 DESIGN CHANGE - INSTALLATION OF INSTRUMENTATION TO MONITOR ADE0llACY OF HEAT TRANSFER CtPABILITY (FLOW AND TEMPERATl!RE, HEAT EALANCE)
ONLY SEVEN (7) PLANTS REMAIN T0 IPPLEMENT DESIGN MODIFICATION CONCLllSIONS 1)
NEE 5FORHEATBALANCEMEASilREMENTRATHERTHANJUSTFLOPFELL UNDERSTOOD 2)
NO Fl'RTHER GENERIC COMMUNICATION NEEDED AT THIS TIFF 3)
WHEN GI-53 CONCLUDED RECONSIDEP NEED FOR FURTHER ACTION-
/
V0GTLE 1 SCRAM
SUMMARY
- 3/19/87 THROUGH 5/6/87 DATE EYEET POWS EAUSE RDARKS N3iES 87/C3/19 09099 31 FLUIRAYE SAIN IRTRDFER'LY SET 87/03/20 03114 31 SS LEVEL LOLO-UN!!RTEDPY0?tRATOR 87/03/21 05127 31 $$ LEVEL LO LO - 05:!LLATION EAUSED BY STEAR DU".?S 1
87/C3/23 01138 41 SBLEVEL LC LO - AFW EONTROL ERROR BY OFERATOR 2
87/03/24 02146 71 56 LEVEL LD LO - MLFUN:TICN OF STEA't CURP?
3 87/C3/27 08178 111 SSLEVEL LD LO - H31 NELL LEVEL INSTRUMENT FAILURE 4
87/04/05 03:78 251 56 LEVEL HI Hl/LO LO - CAUSIC IY TURE!NE TRIP 5
87/04/10,08332 301 55 LEVEL HIHl/LOLO-CAUSEDBYSTUCKCHECKVALVE 6
87/04/11 0B345 211 56 LEVEL HI Hl/LO LO - TRANSFER BYPASS TO RAIN FEED RES 7
87/04/29 02524 751 0'DT/0 TDT 2/4 L0i!C - 1 TRIP FOR SURV, 1 TRIP UNrntet 8
87/C5/04 02572 761 0PDT/DTDT 2/4 LDSIC - 1 TRIP FOR SURV, I TRIP URKh:W 8
87/05/09 06618 801 SS LEVEL LC LO - DVERSHDOT ON LOA 3 DERAC TEST 9
1.
STEAM DUMP VALVES OSCILLATED IN AUTOMATIC AND WERE PLACED IN
- MANUAL, SUBSEQUENT OPERATOR ACTIONS CAUSED LEVEL OSCILLATIONS, 2.
MANUAL CONTROL BY OPERATOR WAS NOT ADEQUATE.
3, APPARENT MALFUNCTION OF STEAM DUPP VALVE.
14,
INSTRUMENT FAILED HIGH, WATER WAS' DIVERTED FROM HOT WELL TO CONDENSATE STORAGE TANK, CONDENSATE PUMPS CAVITATED, MAIN FEED PUMP TRIPPED, 5.
TURBINE TRIP CAUSED STEAM GENEPATOP. TO FILL TO HI HI, FPICH CAUSED MAIN FEED PUMP TRIP, 6.
WITH ONE MAIN FEED OPERATING, DISCHAP.GE VALVE FOR OTHER PUPP VAS OPENED.
THE CHECK VALVE FOR THIS PUMP WAS STUCK OPEN, A
DIVERTING FLOW FROM THE STEAM GENERATORS AND CAUSING A LOW LEVEL
- ALARM, OPEPATOP INCREASED FLOW AND HI HI LEVEL TRIPPED PUMP, 7,
MAIN FEED REG VALVE MALFUNCTIONED, 8,
1 BISTABLE TRIPPED FOR SURVEILLANCE, 1 TRIPPED FOR. UNKNOWN CAUSE, 9.
LOAD DEMAND TEST WAS INTENDED TO BE 65% TO 75%,
IT WAS ACTUALLY 65% TO 80%.
REACTOR SORAM SU'L'.:PY WEEK Ek3!h! c5/10/87
- 1. PLANT SFECIFIC t!TA CATE
!!TE UN!i FCWER EFS CA'!E CC 1 1-YTD YTD YTD J
CAT!OE5 A!C'.'E BEttd TCTAL 151 151 C:/04/E7Ifr.ON 2
E! A E L'I'! ELECT N
3 3
6 05/04/97V0GTLE I
76 A tv.h:n N2 5
6 11 05/06/E7 CATAWlA 2 103 M EGU!F?.ENT N3 4
0 4
C!/06/67 CLIKTCN 1
17 M EC'JIFMENT' N3 1
1 2
C5/07/E7r.I'.LSicht 3 100 A EE'J1FMENT N3 4
2 6
05/03/&7CATAh!A 2
65 M EQUlPP.ENT YES 5
0 5
C5/09/E7 V GTLE 1
60 A E0U!FMENT N3 6
6 12 S'JMMARf CF COMFLICATICN!
!!TE UNIT CCf,FL!OATICNS CATAWIA 2 I $5 SAMFLE VALVE FAILED TO FULLY CLCEE 0415 LAi!0% SIEhAL
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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WsEK ENDING 05/10/B7 SCRAM CAUSE '
POWER NUMBER 1997 1986 1985 OF-WEEKLY WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE AVERAGE YTD (5) (4)
(8) (9)
- POWER ?15%
EQUIP. RELATED
>15%
6 5.9 4.3 5.4 PERS. RELATED(6) 315%
O 1.6 1.9 0.0 OTHER(7)
'15%
1 1.2 0.4
- 0. 6
- Subtotal **
7 6.6 6.5 E.O 44 POWER <15%
ECUIP. RELATED
<15%'
O 1.1 1.4 1.3 PERS. RELATED
<15%
O O.B O.9 0.9 OTHER
<15%.
O O.4 0.2 0.2 S*
Subtotal **
O O.3 2.4 2.4
- ** Total $tt 7
8.9 9.9 10.4 MANUAL VS AUTO' SCRAMS TYFE NUMBER 1987 19E6 1955 OF WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAME 3
1.6 1.0 1.0 AUTOMATIC SCRAMS 4
7.3 7.9 9.4
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PLANT SPECIFIC DATA BASED ON INITIAL PFVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDN!GHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
2.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERFORS UNRELATED TO CAUSE OF SCRAM.
3.
1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
4 IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATINGLICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS.
r.
BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE PUMAN ERROR, PROCEDUPAL DEFICIENCIES, AND MANUAL STEAM GFNERATOR LEVEL CONTROL PROBLEMS.
7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTR1BUTED TO ENVIRONMENTAL j
l CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNGWN CAUSE.
8.
1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVFN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
l 9.
IN 1985, THERE WERE AN FSTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL l
UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER l
LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIP 9 PER REACT 0P l
YEAR AND AN AVERAGE RATE Of 10.4 TRIPS PER WEEK FOR ALL PEACTORS.
l l
ENCLOS1DRE 3 Fair N:.
I
'45/12/57 SIGNIFICANT, EVENTS FREQUEN:V FEtFDRMAh:E INDICATCR hs. 3 i
. PLANT 4AME EVEhi EVENT DESCRIPTION GTR CAUSE CATE CALVERTCLIFFS2 C5/07/87 CFA:t DISCOVEEED IN LPSI FIFINS, SA".E LD:Afith AS 2MAINTEN?N:[
RECENTLY EEFA! FED CEACF. EDTH TEAINE OF SID CCDLlh5 LCST WNP 2 0;/::/67 MAN'.'At SCEAM CCP.?LitATED 11 WATER IN STEAM L!hES 1 FEESONNEL EEF37.
2itsI (4/20'67 Fe! LURE TO FOLLOW FF3:ILUEES F.ESULTED IN CFEhlh3 CF MS!Vs 1 FEE!CNNEL EE50R Ah3 thA!VERTENT SAFETY INJECTION 4
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