ML20237L111
| ML20237L111 | |
| Person / Time | |
|---|---|
| Site: | Point Beach, Callaway, McGuire, 05000000 |
| Issue date: | 08/28/1987 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-87-028, OREM-87-28, NUDOCS 8709080218 | |
| Download: ML20237L111 (13) | |
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%,.....f NO 2 8 gy f1Ef!0RAfiDUtt FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Wayne Lanning, Chief
. Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING August 25,1987 - MEETINC 87-28 On August 25,1987 an Operating Reactors Events meeting (87-28) was held to.
brief senior managers from NRR, RES, AE0D and Regional Offices on events which occurred since our last meeting on August 18,1987. 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 reactor scrams and "significant events" that will be input to NRC's performance indicator program.
i flayn ;[er [ng, Chie
'ut L Even s Assessment $r ch Division of Operat ha 1 Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page
& y :,eea h.f 7
O,gyf 9709080218 870828 PDR ORO NRRD PDR
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1 MEliORANDilM FOR:
narles E. Rossi, Director Division of Operational Events Assessment j
FROM:
Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment SL'BJECT:
THE OPERATING REACTORS EVENTS MEETING August 25,1987 - MEETING 87-28 1
On August 2S,1987 an Operating Reactors Events meeting (87-28) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on August 18,1987..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 reactor scrams and "significant events" that will be input to NRC's performance indicator program.
I l
Mayne Lanning, Chief l
Events Assessment Branch L
Division of Operational Events Assessment
Enclosures:
As stated 1
cc w/ Encl.:
1 See Next Page DISTRIBilTION c~ Central File NRC PDR""'
EAB Rdg i
EAB Members JTHOMPSON RD FL PWR:EP SL:PWR:EAB SL:
- EAB ACT.BC:EAB JTHQfr60N RLOBEL PBA NOWSKY WpANNING y / %/87
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5 Charles E. Ross',
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T. Mod ey M. Grothenhuis J. Snierek D. Muller F. Niraglia
.. Starostecki E. Jordan J. Taylor E. Beckjord W. Russell, Reg. I J. Nelson Grace, Reg. II B. Davis, Reg. III R. D. Martin, Reg. IV J
B. Martin, Reg. V W. Kane, Reg. I L. Reyes, Reg. II C. Norelius, Reg. III R. Hall, Reg. IV i
D. Kirsch, Reg. V S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan F. Schroeder L. Shao J. Partlow B. Grimes F. Congel E. Weiss S. Black T. Martin, EDO E. Merschoff R. Hernan H. Bailey J. Guttmann l
l 1
ENCLOSURE 1 QSTOFATTENDEES OPERATING REACTORS EVENT,5 ERTEFING (87-28) l August 25, 1987 NAME ORGANIZATION NAffE ORGANIZATION C ~E. Rossi NRR/DOEA '-
Dhompson ' EAB R. Starostecki NRR/ADT L. Zerr EAB R. tcbel DOEA R. Scholl EAB W. Lanning DOEA R. Auluck OSP C. Berlinger DOEA/0GCB S. Elrod OSP B. Grimes DRIS t!. Troskoski OEDO P. Bararowsky DOEA D. Wagner PDIII 3 G. Lainas RPII T. Quay PDIII 3 D. Crutchfield NRR/DRSP J. Mazetis DRPS/RES
R. Baer RES/DE P. Polk DPELQ O
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ENCLOSURE 2 OPERATI))G.REACTORSEVENTSDPJ.EFING87-28 TU.E.SDAY AUr-UST 25,3987.,_11 A.M.
TliE AGEt0A INFDPFATION MAY /LSD DE ODTAlt.'ED BY DIALING FYTENS!ON 27174.
MCGUIPE ]
MCGUIRE SCPAM WITH COMPLICATI0t.!S POINT EEK H 2 INOPERABLE MAIN STEAM ISOLATION VAL'ES CALLAPAY DEGRADED ESSEllTIAL SEP.VICE WATER (ESW) SYSTW.
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MCGilRE 1 SCRAM WITF COMPLICATIONS AUGUST 16, 1987 PROBLEM SCRAM WITil SAFETY ItUECTION (SI) FOLLOWED BY LEAK IN LETDOW SYSTEM AND LOSS 1
0F CONDENSER YACUUM
{
CAUSE MALFUNCTION OF DIGITAL FYPPAULIC CONTROL (DHC) SYSTEM HlGH - LYCLE FATIGUE IN LETDOWN LINE 1
SIGNIFICANCE
- REACTOR AT 5% POWER hMILE PARALLELING GENEPATOP TO GRID j
- MALFUNCTION IN DHC SYSTEM PESULTS IN EXCESSIVE STEAM DEMAND l
- STEAM PRESSURE DROPPED FROM 1100 TO 990 PSI I
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NOT RESEAT IFTEDIATELY l.
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- ONE MSR PELIEF VALVE, FAILED TO RESEAT, RESULTING IN LOSS OF CONDENSER VACUlfi
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- HEAT SINK Pfa#IDED VIA MAIN STEAM PORVs l
- LETDOWN LINE ISOLATED ON SI SIGNAL
- 30-40 GPM PRIMARY LEAK IN CONTAINMENT WITH LETDOWN RETURNED TO SERVICE l
- LEAK PESULTED FPG CRACKED WELD ON 3/4" DRAIN VALVE
- LEIDOW WAS ISOLATED, LETDWN ESTABLISHED VIA EXCESS LETDOWN
- IN ADDITION, VARIABLE ORIFICE VALVE FAILED (GUIDE PIN ON PLUG WAS MISSING),
- WELDS FAILED DUF TO HIGH - CYCLE FATIGUE -- WATER HAPTER AND HIGH VIEPATION DURING HOT FUNCTIONAL TESTING FOLLOWUP l
PEGION II AND RI FOLLOWING LICENSEE ACTIONS CCf! TACT: SWENSON,NRR
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I P01hT BEACH 2 INOPERABLE t%IN STEAM ISOLATION VALVES PROBLEM POWER t'EEDED TO CLOSE BOTH MAIN STEAM ISOLATION VALVES (MSIVs)
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WAS UNAVAILABLE FOR APPROXIMATELY FOUR HOURS LICENSEE DID fl0T REPORT EVENT AS REQUIPED UNDER 10 CFR 50,72 CAUSE l
- C0mtNICATION BREAKDOWN BEIVEEN AUX EQUIP OPERATOR AND MAltJENANCE SUPERVISOR RESULTED IN CB's BEING LEFT OPEN FOR FOUR HOURS AFTER MAlfRENANl WAS C0tPLETED
- LICENSEE REASONED THAT NO TECH SPEC VIOLATION OCCURRED SIGNIFICANCE
- BOTH MSIV's INOPERABLE (AliTOMATIC AND MANUAL)
DISCUSSION
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- ON 8/16/87 REACTOR SCRAffED DUE TO LIGHTNING STRIKE TO MAIN GENERATOR DUTPUT TRANSFOPER l
- MSiv MANUAL CLOSURE PROCEDURE ENTAILS LOCKING OUT AND TAGGING CB's WHICH ISOLATE DC POWER TO MSIV ACTUATING SOLEN 0ID
- UNIT WEtU TO ABOUT 2 PERCENT POWER WITH MSIV's IMOPERABLE
- LICENSEE FAILED TO REPORT INCIDENT CITING THE BELIEF lliAT NO OPERABILIT/
Pf0VIREKNTS WERE VIOLATED
- ON 8/20/87 LICENSEE FILED 10 CFR 50.72 REPORT WHEN REGIONAL OFFICE IDENTIFIED TECH SPEC WHICH WAS VIOLATED FOLL0kUP
- LICENSEE HAS FORTD INCIDENT INVESTIGATION CO MITTEE T0 INTERVIEW PRINCIPALS INVOLVED IN EVENT
- LICENSEE IS PERFORMING ANALYSIS OF SAFETY SIGNIFICANCE OF EVENT
- REG 10t! IS CONSIDERING POSSIBLE ENFORCEMENT ACTION CONTACT: N. FIELDS c_-___________-_
Call AWAY ]
DEGPADFD ESSENTIAETt HVICE WATER (ESW) SYSTEM PROBLEM
- RETUPA VALVE TO ULTIMATE HEAT SINK IN TPAIN B 0F ESW SYSTEM WAS PAR CLOSED APPAPENTLY SINCE 5/84 CAUSE
- HANDWHEEL WAS NOT INSTALLED PROPERLY SIGt!I.F.LCANCE
- BPEAll)0WN IN QA f%MAGFIUT DISCUSSION
- TIE UNIT WAS PROBAPLY OPEPATED FOR PERIODS OF TIME WITH TRAIN A Ot SERVICE AND TPAIN B DEGRADED
- ESW SERVES SAFETY-PELATED COMPONENTS INCLt0 LNG CONTAlfFENT GENEPATOR COOLERS, CCW HEAT EXCHANGERS, AND ROOM COOLERS FOR SAFETY IfUECTION, C0fffAINMENT SPPAY, AND C04 PLMPS
- WHEN THE POSITION OF THE HANDMEEL INDICATED FULL OPEN, THE STEM DID NOT, AND THE VALVE WAS NOT FULL OPEN
- LICENSEE CONCLUDED BY EVALUATION THAT ESW FLOW WAS 11,000 GPM INSTEAD OF l
13,594 GPM AS DESCRIBED IN THE FSAR
- WORK REQUEST, ISSUED 5/11/84 FOR VALVE RETEST < WAS LATER CANCELLED
- WR ISSUED 5/14/84 PE HANDWHEEL PROBLEM WAS WIDED IN 9/86
- LICENSEE REALIZED THAT THE VALVE WAS t0T FULLY OPEN AND OPENE
- LICENSEE'S OPERATING PERF0 PRANCE HAS GEBERALLY BEEN GOOD; HOWEVER, RECENT SALP REPORT NOTED ADVERSE TREND IN SURVEILLANCE ERRORS FOLLOWUP
- SRI IS DOING A SPECIAL SAFETY INSPECTION AT THE REGION'S RE0 JEST TO DETEPNINE HiY THIS CONDITION HAD NOT BEEN DETECTED BY READO PAPN1ETERS, SilRVFILLANCE, AND VALVE ALIGtfENT CHECVS
- LICENSEE HAS FDPNED A TASK FORCE TO LOOK INTO THESE CONCEPNS
- BEOTTEL IS ANALYZING THE ADEQUACY OF 11,000 GPM C0ffTACT: ROGER WOODRUFF
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ENCLOSURE 3 F.EA TOR SCRAR SUMMAD WEEE ENDING 05/2;!B7 I
- f. FLANT Sf EClfi: *ATA
- ATE IITE Cil' F CsER FJ5 C A' 5E CCMFLI-YTs fTL ITL J
CATIENS AiDVE SELOW TDIAL l
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1 05/17/E7 Fall 5AIE5 1
63 A EGulF/P.EC h3 4
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08/23/67 Fall 5 ALES 1
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II. CDt1PARISON OF WEEl:LY STATIETICE WITH I N D U S T R
Ai.'E R T,C-E ;
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i L' RAr CAUIE POWER NUIlEER 957 i C E c.,
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DF WEEl,LY WE EF.L Y WE El '.L S j
AVERAGE AVERAGE AVERAGE YTD (3/ (4)
(8 (9)-
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EOU1F. REL A.TED 15*.
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TYPE NUMBER 1987 1986 1905 l
OF WEEl:LY WEEl4LY WEElLT
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SCRAM 5 AVERAGE' AVERAGE Ab'ERAGE l
YTD i
MANLIAL SCRAM 5 0
1.6 1.O 1.O AUTOMATIC ECRAMS e
7.7 7.9 9,4 i
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t NOTES a
1.
PLANT SPECIFIC DATA BASED ON INITIAL-REVIEW 0F E0.72 REPORTS FOR THE UEEK OF INTEREST.
PERIOP IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCRAfiS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAPS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
2.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE DF SCRAM.
3.
1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS 1
IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
i 4.
IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUT0f1ATIC AND
.j MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES).
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.
5.
BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM CENERATOR LEVEL CONTROL PROBLEliS.
7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN 'USE.
8.
1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAXING TOTAL TRIPS IN A GIVEN l
CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
9.
IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
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