ML20215G136
| ML20215G136 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Palisades, Point Beach, Oyster Creek, Hope Creek, Columbia, 05000000 |
| Issue date: | 10/14/1986 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8610200104 | |
| Download: ML20215G136 (23) | |
Text
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W 14 R
-MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:
Gary M. Holahan, Director Operating Reactors Assessment Staff
SUBJECT:
SUMMARY
OF THE OPERATING REACTORS EVENTS MEETING ON OCTOBER 6, 1986 - MEETING'86-35 On October 6,1986, an Operating Reactor Events meeting (86-35) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on September 29, 1986. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2.
In addition, the assignment of followup review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.
Completion dates have been assigned for items in Enclosure 3.
Each assignee should review Enclosure 3 with regard to their respective responsibilities.
Note that several assignments are approaching the due date.
Please be responsive and advise ORAS (D. Tarnoff, X27864) if the target completion date cannot be met.
.M/.
i Gary M. Holahan, Director Operating Reactors Assessment Staff
Enclosures:
As Stated cc w/ Encl.:
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Out 14 WE6 Harold R. Denton cc:
R. Vollmer H. Pastis J. Taylor H. Bailey C. Heltemes J. Stolz D. Ross T. Wambach T. Murley, Reg. I A. Thadani J. Nelson Grace, Reg. II J. Bradfute J. Keppler, Reg. III E. Adensam R. D. Martin, Reg. IV V. Hodge J. B. Martin, Reg. V T. Colburn R. Starostecki, Reg. I G. Lear S. Ebneter, Reg. I J. Donohew R. Walker, Reg. II R. Becker C. Norelius, Reg. III J. Zwolinski E. Johnson. Reg. IV D. Wagner D. Kirsch, Reg. V C. Shulten H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe
- 15. Rubin P. Baranowsky
--v-r.,---
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00F14 W ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-35)
OCTOBER 6, 1986 NAME DIVISION NAME DIVISION M. Caruso ORAS/NRR D. Jolliffe IE/DEPER K. Jabbour PWR-A/NRR M. Chiramal AE0D R. Ramirez DBL /EICSB D. Basdekas DRSS/RES S. Rhow EICSB/NRR G. Cwalina DHFT/NRR C. Miller PWR-B/NRR M. Clausen OCM/LZ R. Dudley DPLA/NRR T. Wambach DPLB/NRR R. Hernan PPAS/NRR C. McCracken PDBf6/NRR D. Vassallo F0B/ DBL C. Shulten F0B/ DBL R. Scholl ORAS/NRR W. Paulson PWR-B/NRR W. Regan PWR-B/NRR V. Hodge EGCB/IE A. Kimmins ORNL/NOAC
.V. Benaroya PAF0/NRR J. Bradfute DBL /NRR A. Dromerick IE/DEPER/EGCB G. Klingler ORPW/IE J. Stone IE/DQAVT/VPB R. Becker DBL /NRR E. Weiss IE/DEPER/EAB E. Jordan IE R. Starostecki IE A. Thadani NRR J. Rosenthal IE/EAB C. Rossi PWR-A/NRR J. Stolz PWR-B/NRR H. Pastis PWR-B/NRR F. Schroeder PWR-B/NRR R. Houston DBL /NRR T. Colburn PWR-A/NRR R. Baer IE/DEPER G. Holahan ORAS/NRR v,
.___m.,
ENCLOSURE 2' OPERATING REACTORS EVENTS BRIEFING 86-35 0CTOBER 6, 1986 0CONEE 2 LOSS OF LOW PRESSURE SERVICE WATER (LPSW)
PALISADES SERVICE WATER PUMPS DO NOT MEET FSAR REQUIREMENTS ~
WNP2 NO ANALYSIS OF POTENTIAL FLOODING DUE TO FIRE POINT BEACH 2 BOTH MSIVs FAIL TO CLOSE FULLY ON MANUAL DEMAND OTHER EVENTS OF INTEREST OYSTER CREEK CONTROL R0D DRIVE HYDRAULIC CONTROL UNITS NOT INSTALLED AS DESIGNED HOPE CREEK LOSS OF 0FFSITE POWER TEST - UPDATE J
OCONEE 2 - LOSS OF LOW PRESSURE SERVICE WATER (LPSW)
OCTOBER 1, 1986 - (H. BAILEY, IE)
PROBLEM:
LPSW COOLING FAILED ON UNIT 2
. SIGNIFICANCE:
LOSS OF ULTIMATE HEAT SINK.
DESIGN DEFICIENCY MAY BE APPLICABLE TO OTHER PLANTS CIRCUMSTANCES:
LPSW PUMPS ON UNIT 2 LOST SUCTION AFTER ABOUT 1 HOUR OF OPERATION FOLLOWING LOAD SHED TEST WITH CONDENSER CIRCULATING (CCW) WATER PUMPS IDLED.
SUCTION REGAINED AFTER CROSS CONNECT TO UNIT 1 WAS OPENED.
CCW GRAVITY FLOW TEST ON UNIT 2 FAILED.
LPSW SUCTION FROM UNIT 1.
CCW USES SIPHON FOR FLOW OVER HIGH POINT, ULTIMATE HEAT SINK ON UNITS 1 AND 2 DECLARED INOPERABLE PER T/S.
UNITS SUBSEQUENTLY TAKEN TO COLD SHUTDOWN.
FLANGE LEAKS ON UNIT 2 CCW PUMPS SEALED.
PASSED CCW GRAVITY FLOW TEST.
KE0 WEE LAKE LEVEL FOR TEST A CONCERN.
CURRENT LEVEL 785 FT.
NORMAL LAKE LEVEL 800 FT. MINIMUM TECH SPEC LEVEL 0F 775 FT.
FOR KE0 WEE HYDRO EMERGENCY POWER.
CCW PUMP HAS A FLANGE AT HIGH POINT IN SYSTEM.
FOLLOWUP:
REGION II HAS LEAD FOR RESTART LICENSEE TO DEMONSTRATE OPERABILITY OF LPSW SYSTEM PRIOR TO RESTART
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PERS. RELATED(6) >15%
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- Subtotal **
4 7.3 8.0 o* POWER <15%
EQUIP. RELATED
<15%
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PERS. RELATED
<15%
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<15%
1 0.2 0.2 ( 8%)
ed Subtotal **
3 2.6 2.4
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7 9.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVEi(AGE AVERAGE YTD MANUAL SCRAMS 3
1.1 1.0 AUTOMATIC SCRAMS 4
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l, NOTES i
1 -- PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY SCPAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED 4
TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE i
i WITH A PLANT PROCEDURE.
E.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR. __
4.
IN 1985 THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWERLICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER
. REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
l 5.
BASED ON 100 REACTORS HOLDING A FULL POWER LICENSE.
6.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.
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Page No.
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' 10/06/96 SIGNIFICANT EVENTS FREQUENCY PERFORMANCE INDICATOR Nc. 4-PLC]T'AME EVENT EVENT IESCRIPTION SIGNIFICANCE QTR N
DATE PDINT BEACH 2 09/28/86 BOTH M31Vs FAIL TO CLOSE FULLY ON MANUAL DEMAND. PDTENTIAL FOR OR ACTUAL DEGREDATION OF 1
MSIVs CLOSED WITH MANUAL ASSISTANCE.
SAFETY-RELATED EQUIPMENT PALISALES 1 07/30/06 SERVICE WATER PUMPS DO N3T MEET FSAR FLOW POTENTIAL FOR OR ACTUAL CEGREDATION OF 1-REGUIREMENTS. aFPARENTLY DUE TO NOT BACKFITTINS SAFETY-RELATED EQUIPMENT FROFER IMPELLER.
WNP 2 08/17/86 N3 ANALYSIS WAS PERFORMED OF FDTENTIAL FLOODING IDENTIFICATION OF SAFETY-SIGNIFICANT CONDITION 1
DUE TO FIRE MAIN BREAKS WHEN SPRINKLER SYSTEM NOT CONSIIEEED IN LICENSINS BASIS ~
WAS A!DED TO ROOMS ADJACENT TO CONTRO. ROOM.
OCONEE 2 10/01/96 LOSS OF LOW PRESSURE SERVICE WATER DL'E TO AIR FOTENTIAL FOR OR ACTUAL DEEREIATION 0F 1
INLEAKA3E ON CONDENSUR CIRCULATINS WATER PUMP SAFETY-RELATED EQUlFMEhi FLANSE.
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ENCLOSURE 3.
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$le No[
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Ig/01/B0 OPERATINS REACTORS EVENTS MEETING FOLLOWUP ITEMS g.
- F+ l AS OF MEETING B6-35 DN OCTOBER 6, 1986 Y.
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(IN ASCENDING MEETING DATE, NSSS VEND 0R, FACILITY ORDER) s l DID FAtlllTY RESPONSIBLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS I BOERI NSSS VENDOR /
DIVISION /
COMPLET. BY DOCUMENT, I
ING EVENT DESCRIP.
INDIVIDUAL DATE(S)
MEETING,ETC.
l TE I?
lh-10 OYSTER CREEK NRR /HDUSTON W RESQLVE THE QUESTION OF THE 10/30/86 DPEN
/ /
FDLLOWUP ACTION TO g31/86 SE / LEVEL
/
ACCEPTABILITY OF BLIND SWITCHES
/ /
BE INCORPORATED IN t'a SWITCH SETPOINT AND DELETION OF DAILY CHANNEL
/ /
REVIEW 0F JUNE yh DRIFT CHECK 1,1966 EVENT AT LASSALLE
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VERMONT YANKEE NRR /HOLAHAN 6.
DETERMINE STATUS AND 10/30/86 DPEN
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- I p/B6 GE / PROBLEMS
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EFFECTIVENESS OF STAFF AND 09/!0/86 I
WITHSCRAM LICENSEE ACTION ON
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[f-SOLENDID VALVES POST-MAINTENANCE TESTING (GL g
B3-28). DEVELOP RECOMMENDATIONS i
FOR FURTHER ACTION 4*
h;23 MULTI NRR / HOUSTON W.
DETERMINE APPROPRIATE 10/30/86 CLOSED 10/06/86
.I 7/07/86 NA /
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RESULATORY REQUIREMENTS PASED 09/30/06 JULY 24,1996 2.1 BWRS-RESIDUAL ON RECOMMENDATIONS O!SCUSSED AT
/ /
MEMD R.HERMANN HEAT REMOVAL BRIEFING TO 6. LAINAS h-PUMP / WEAR RING k'
FAILURES -
@c FDLLOWUP 06-28 6 RAND SULF IE / JORDAN E.
ASSESS PDTENTIAL FOR SENERIC 10/30/86 OPEN
/ /
INFDRPATIZ N:TICE
[B/11/86 6E / CONTROL RDO
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APPLICABILITY 09/30/86 IN PREFARATION "4
WITHDRAWAL
/ /
h PROBLEM N-32 NINE MILE PT 1 NRR /RDSA F.
DISCUSS WITH LICENSEE AND 10/24/B6 OPEN
/ /
99/15/B6 6E / SCRAM NRR /ZWOLINSKI J.
REB 10N LICENSEE'S
/ /
h OUTLET VALVE IMPLEMENTATION OF GL 63-28 IN
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f DIAPHERAM EEFERENCE TO 09/08/26 EVENT d
FAILURE if Elle has been deleted.
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