ML20149F474
| ML20149F474 | |
| Person / Time | |
|---|---|
| Site: | Salem, Brunswick, Ginna, Farley, 05000000 |
| Issue date: | 01/07/1988 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-88-001, OREM-88-1, NUDOCS 8801140256 | |
| Download: ML20149F474 (24) | |
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MEMORANDUM 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 January 5, 1988 - MEETING 88-01 On January 5, 1988 an Operating Reactors Events meeting (88-01) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on December 22, 1987 (an Operating Reactor Event; meeting was not held on December 29,1987). The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2.
The Enclosure 3 presents one suggested longterm followup, long-term followup assignments to be completed, a summary of reactor scrams, and a comparison of last week's and this week's statistics with industry averages.
No significant events were identified for input to NRC's performance indicator program. provides a 50.72 report tabulation and sunmary for December 28, 1987 through January 3, 1988.
/
k e Lanning, Chief Events Assessmen+ Bran h Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page b ', h,
8801140256 880107 PDR ORG NRRB j.
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T. Murley J. Sniezek F. Miraglia D. Fischer E. Jordan W. Butler J. Taylor E. Reeves E. Beckjord C. Stahle W. Russell, RI E. Brunswick B. Davis, RIII E. Adensam J. Nelson Grace, R. D. Martin, RI'!
J. B. Martin, RV W. Kane, RI L. Reyes, RII C. Norelius, RIII J. Callan, RIV D. Kirsch, RV S. Varga D. Crutchfield B. Boger G. Lainas G. Holahan L. Shao J. Partlow B. Grimes F. Congel E. Weiss S. Black T. Martin J. Stone R. Hernan H. Bailey J. Guttmann A. Thadani
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ENCLOSURE 1 LIST OF ATT,ENDEES OPERATING REACTORS EVENTS BRIEFING (88-01)
January 5, 1988 NAME ORGANIZATI,0,N.
N_AME ORGANIZA_T,lg W. Lanning NRR/00EA R. Woodruff NRR/D0EA M.L. Reardon NRR/00EA B. Grimes NRR/DRIS C.E. Rossi NRR/DOEA W. Hodges NRR/ DEST J. Thompson NRR/DOEA T.M.Novak AE0D J. Roe NRR/DLPQ W. Minners RES/DRPS R. Scholl, Jr.
NRR/DOEA G. Klingler NRR/PMAS J. Carter NRR/00EA B. Clayton OED0 N. Fields NRR/D0EA C. Stable NRR/PDR 3
- 8. Boger NRR/ADRI J. Stang OSP/TVA J. Richardson NRR/EAD C.Y. Chang NRR/EMTB E. Reeves NRR/PD 2-1 G. Lainas NRR/DRP2 S.A.Vargas NRR/DRP L. Shao NRR/ DEST l!(
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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-01 TUESDAY, JANUARY 5, 1988 THIS INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 27174, SALEM 1 FLOODING 0F SERVICE WATER SYSTEM FARLEY 2 SAFETY INJECTION PIPE LEAK GINNA 1 FAILURE OF WESTINGHOUSE CIRCUIT BREAKERS BRUNSWICK 2 DRYWELL DRAIN VALVE FAILURES i
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SALEM UNIT 1 FLOODING 0F SERVICE WATER SYSTEM DECEMBER 22, 1987 PROBLEM FAILURE OF ISCLATION VALVE (S) ON SERVICE WATER (SW) SYSTEM CAUSES FLOODING 0F SW BAY, DAMAGE TO SW PUMP MOTORS AND ASSOCIATED EQUIPMENT, SIGNIFICANCE DEGRADED SAFETY RELATED SERVICE WATER SYSTEM, DISCUSSION o
UNIT 1 EQUIPPED WITH 6 SW PUMPS (3 IN SW BAY 1-3 IN SW BAY 2),
o UNIT 1 IN REFUELING OUTAGE-ONE SW PUMP (13) IN OPERATION AS REQUIRED BY TECH SPECS, o
TIME RESPONSE TESTING OF SW PUMPS AND WELDING IN PROGRESS, o
M0 VALVES SW 20 AND SW 26 WHICH ISOLATE THE SAFETY RELATED FROM THE NON-SAFETY RELATED PORTION CLOSED, l
0 LEAKAGE PAST CLOSED ISOLATION VALVES SW 20 AND SW 26 HINDERS l
WELDING ACTIVITY ON OPENED 3" CHLORINATION LINE DOWNSTREAM, o
FLANGE ON CHECK VALVE SW 5, LOCATED BETWEEN SW 20 AND SW 26 ON 30" LINE LOOSENED TO CONTROL LEAK AND ALLOW WELDING, o
FLOODING DISCOVERED IN SW BAY 1 AROUND 8:30 A.M.
WATER LEVEL 1 FT BELOW SW PUMPS MOTORS, l
0 STEPS TO DETERMINE AND CORRECT CAUSE OF FLOOD UNSUCCESSFUL, o
WATER LEVEL REACHES WITHIN 2 FT OF CEILING AT 10:30 A.M.
o SW PRESSURE REDUCTION AND USE OF HIGH CAPACITY SUBMERSIBLE PUMP DECREASES WATER LEVEL.
l 0
ISOLATION VALVES SW 20 AND SW 26 INDICATED CLOSED IN CONTROL l
ROOM THROUGHOUT EVENT, o
SW 20 AND SW 26 DISASSEMBLED AND INSPECTED, o
TORN RUBBER SEAT LINER ON SW 20.
o SW 26 HAD DISK ROTATED PAST SEAT, l
CONTACT:
W JENSEN l
FOLLOWUP o
REG 10t! TO SEND SPECI AL INSPECTION TEAM TO~ REVIEW SEQUENCE OF
- EVENTS, EAB TO PARTICIPATE.
o LICENSEE TO REPLACE OR REFURBISH FLOODED ELECTRICAL EQUIPMENT, l
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FARLEY 2 SAFETY INJE.CTION PIPE LEAK DECEMBER 9, 1987 PROBLEM o
AN UNISOLABLE LEAK DEVELOPED IN AN ECCS LINE 3 FEET FROM THE RCS COLD LEG, CAUSE o
HIGH CYCLE FATIGUE DUE TO THERMAL STRESS.
SIGNIFICANCE o
CIRCUMFERENTIAL FAILURE OF THE LINE WOULD RESULT IN A 6-INCH LOCA, o
SEPARATION OF THE ENDS OF THE LINE WOULD RESULT IN A LARGE LOSS OF EMERGENCY CORE COOLANT TO THE SUMP, DISCUSSION o
ONE ON THE WELDS AT A SCHEDULE-160 ELBOW HAD A 120 DEG CIRCUMFERENTIA
- CRACK, o
EXAMINATION OF THE FAILURE INDICATED THAT THE WELD WAS SATISFACTORY BUT ITS FATIGUE LIFE HAD BEEN EXCEEDED, o
WESTINGHOUSE POSTULATED THAT THE STRESS LOADS WERE: (A) TilERMAL AND CREATED BY VALVE LEAKAGE OR CONVECTIVE FLOW CELLS OR (B) MECHANICAL AND CREATED BY FLOW INDUCED VIBRATION, o
THE LICENSEE INSTRUMENTED THE REPLACEMENT PIPING WITH 3ENSORS FOR TEMPERATURE AND ACCELERATION, o
THE LICENSEE AND WESTINGHOUSE BY TELEPHONE STATED THAT DOUBLE ENDED FAILURE OF AN ECCS LINE IS COVERED BY THE THE SAFETY ANALYSIS, o
THE FSAR PROVIDES THE RESULTS OF ANALYSIS OF A 6-INCH LINE BREAK AND SHOWS THAT THE CORE IS COMPLETELY UNCOVERED FOR THREE MINUTES, o
WESTINGHOUSE REFERRED US TO PAGE 5-2 0F WCAP-10054 (NOTRUMP) WHICH STATES THAT THE ANALYSIS FOR AN ECCS LINE BREAK ASSUMES THAT: (A) THE BREAK SIZE IS LESS THAN THE LINE DIAMETER AND (B) COOLANT SPILLS AT RCS BACK PRESSURE, FOLLOWUP o
DOCUMENTATION SHOULD BE OBTAINED WHICH VERIFIES THAT THE BREAK IS A DOUBLE ENDED ECCS LINE FAILURE WITH RCS PRESSURE AT ONE END AND ECCS PRESSURE AT Tile OTHER, o
IDENTIFY THE STRESS LOADS AND CAUSES, CONTACT: ROGER WOODRUFF
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GINNA 1 FAILURE OF WESTINGHOUSE CIRCUIT BREAKERS DECEMBER 21, 1987 PROBLEM FAILURE OF WESTJNGHOUSE CIRCUlT BREAKER (CB) TO CLOSE DURING RHR PUMP SURVEILLANCE.
[A!,LSE IMPROPERLY INSTALLED "AMPTECTOR" OVER CURRENT DEVICE.
SIGNIFICANCE WESTINGHOUSE TYPE DB 25, 50, 75 CIRCUIT BREAKERS ARE USED EXTENSIVELY IN BOTH VITAL AND NON-VITAL CIRCUlTRY THROUGHOUT PLANTS.
DISCUSSION o
ON DECEMBER 21, 19S7, THE "B" RHR PUMP FAILED TO START DURING SURVEILLANCE DUE TO ITS POWER SUPPLY CIRCUIT BREAKER FAILING TO CLOSE.
THE CB FAILED TO CLOSE DUE TO INADEQUATE CLEARANCE BETWEEN THE o
CB TRIP BAR AND THE ACTUATOR ARM 0F THE "AMPTECTOR" OVERCURRENT RELAY DEVICE.
o THE "AMPTECTOR" IS A SOLID STATE OVERCURRENT TRIP DEVICE INSTALLED AS A REPLACEMENT FOR THE ORIGINAL ELECTRO-MECHANICAL TRIP ON 12, JE CB's AND 32, NON-VITAL CB (ALL WESTINGHOUSE TYPE DB).
o CONSULTATION BETWEEN LICENSEE AND WESTINGHOUSE REVEALED THAT LICENSEE FAILED TO INSTALL THE "AMPTECTOR" MODIFICATION WITH PROPER 1/32 INCH CLEARANCE BETWEEN THE ACTUATOR ARM AND TRIP BAR (INSTALLATION MANUAL DOES NOT STATE SPECIFIC CLEARANCE REQUIREMENTS).
o ALL CLASS 1E BREAKERS WITH "AMPTECTOR" MODIFICATION WERE l
SUBSEQUENTLY TESTED.
THE "B" TRAIN SI PUMP BREAKER FAILED ON THE 7TH ACTUATION AND "B" RHR PUMP BREAKER FAILED ON THE l
14TH ACTUATION.
o ALL CB WERE VERIFIED TO BE PROPERLY ADJUSTED BY BENDING ACTUATOR ARM TO THE REQUIRED CLEARANCE.
o THESE WERE THE FIRST FAILURE EXPERIENCED SINCE THE BACKFIT WAS MADE IN MAY OF 1987.
FOLLOWUP l
l CONTACT:
N. FIELDS
DPilNSWICK 2 DRYWELL DRAIN VALVE FAILURES JANUARY 2, 1988 PROBLEM TWO SETS OF PRIMARY CONTAINMENT ISOLATION VALVES FAIL TO CLOSE, CAUSE CURRENTLY ATTRIBUTED TO SOLEN 0ID INOPERABILITY, SIGNIFICANCE o
CONTAINNENT ISOLATION WAS NOT ACHIEVED IN TWO DRAIN LINES, o
COMMON MODE FAILURE.
DISCUSSION o
EVENT DATE:
JANUARY 2, 1988.
o PLANT AT 51% POWER WHILE SHUTTING DOWN TO REFUEL, o
DECREASING CONDENSER VACUUM LED TO MANUAL SCRAM, o
REACTOR WATER LEVEL 1 CAUSED GROUP 2, 6, AND 8 ISOLATION, o
ISOLATION VALVES (4 TOTAL) DID NOT AUTOMATICALLY CLOSE IN DRYWELL FLOOR DRAIN (2)
DRYWELL EQUIPMENT DRAIN (2) o FLOOR DRAIN VALVES CLOSED WITH VALVE SWITCH IN MANUAL, o
EQUIPMENT DRAIN VALVES FOUND CLOSED AFTER CYCLING VALVE SWITCH, o
ONE S0LEN0ID INSPECTED - NOTHING OBSERVED.
o UNIT 1 VALVES OPERATED SUCCESSFULLY, o
SURVEILLANCE REQUIREMENT IS 18 MO, FOLLOWUP AIT SENT TO SITE.
l CONTACT:
J. CARTER
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LONGTERM FOLLOWUP ASSIGNMENTS TO BE COMPLETED ORGANIZATION LONGTERM FOLLOWUPS OUTSTANDING 01/05/87 SPLB 6
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4 EUMMARY OF COMPLICAi!ON3
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- 8. C I'.f MANUAL VS AUTO SCRAMS TYPE NUMEER 19E7 1986 1CED OF WEEKLY WEEKLY WEEV Y SCRAMS AVER AGE A'.'EF.A3C AVER.l 3E YTD MANUAL SCRAME 2
1.5 1.O 1.0 AUTOMATIC SCRAMS 7
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PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGH ',
MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.
E.
RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAU5E OF SCRAM.
3.
1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEXLY DATA DETERMINED BY TAXING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY S2 WEEKS / YEAR.
4.
IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND HANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES).
THFS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.D TRIPS PER WEEX FOR ALL REACTORS.
5.
BASED ON 109 REACT 0d5 HOLDING AN OPERATING LICENSE.
6.
PERSONNEL RELATED.SROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOP. LEVEL CONTROL PRODLEMS.
7.
"0THER" INCLUDES AUTOMATIC S01 AMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
8.
1985 INFORMATION DERIVED FRON AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAXING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
9.
IN 1985, THERE VERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND KANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF S.0 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.
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s MEMORANDUM 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 January 5, 1988 - HEETING 88-01 On January 5,1988 an Operating Reactors Events meeting (88 01) was held to brief senior managers from NRR, RES, AE0D and Regional Offices on events which occurred since our last meeting on December 22, 1987 (an Operating Reactor Events meeting was not held on December 29,1987).
The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2.
The Enclosure 3 presents one suggested longterm followup, long-term followup assignments to be conipleted, a sumary of reactor scrams, and a comparison of last week's and this week's statistics with industry averages.
No significant events were identified for input to NRC's performance indicator program provides a 50.72 report tabulation and sumary for December 28, 1987 through January 3, 1988.
Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
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- 01/V/88 OFFICIAL RECCRD COPY
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