ML20065H323
| ML20065H323 | |
| Person / Time | |
|---|---|
| Site: | 05002698, 05002858 |
| Issue date: | 05/12/1981 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082180533 | List:
|
| References | |
| FOIA-82-261 NUDOCS 8210050064 | |
| Download: ML20065H323 (9) | |
Text
r 1
g f.AY I 2 19 81-i MEMORA'iDUM FOR:
Darrell G. Eisenhut Director Division of Licensing
- FROM:
G.C. Lainas, Assistant Director' for Safety Assessment Division of Lic.ensing SUBJECI:
SUMMARY
OF THE OPERATING REACTOR EVENTS MEETING ON MAY 6,1981 On May 6, 1981 an Operating Reactor Event meeting was held to brief the Office Director, the Division Directors, and the'ir represen-tatives on events which occurred since the last meeting. The list of meeting attendees is included as Attachment 1.
.s The events discussed and the significant elements of these events are '
presented in Attachment 2.
In addition to these events, the assignment of follow-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Attachment 3.
The next Ope, rating Reactor Events meeting is scheduled for May 13,1981.
f.
O t
G.C. Lainas, Assistant Director for Safety Assessment s
Division of Licensing Attachments:
As stated cc w/ attachments:
Meeting Attendees ORAB Members G. Zech H. Denton T. Novak E. Case G. Lainas R. Mattson R. Tedesco R. Vollmer J. Olshinski S. Hanauer G. Holahan T. Murley H. Thompson 8210050064 820628 PDR FOIA UDELL82-261 PDR h52
/
(I
- " c4.D.L,5,0RAB fq,@,DL 0,G,h,,{,f D h/B Q,f,,, _
5
~m.su.@.ex;.s.h...G".'..h ".i.'..L...'.'.".'."'.".L.-.. ?..... '
our >l. j: /w/.81..V...
. 5"....//)./81
.5
......./. /2..l.81
,///,e/81 see rer.v 3,e.ie oo.nace cus O FFICI AL R EC.- ".D CO PY u
F ATTACHMENT 1 MEETING ATTENDEES S. Wookey A. Oxfurth B. Siegel J. VanVliet K. Eccelston T. Novak T. Murley R. Mattson R. DeYoung N. Moseley J. Sniezek B. Mills D. Eisenhut G. Lainas l
J. Olshinski E. Case J. Hel temes R. Purple G. Holahan J.P. Knight J. Kramer S. Varga
~
r OPERATING ' REACTOR EVEfffS KETING MY6,1981 O BEAVER VALLEY UNIT le fhY 2,1981 PLANT IRIP - EMERGENCY PREPAREDNESS PLAN IMPLD1ENTED - UNUSUAL EVENT PtD-I-81-59
- WHILE AT 100% POWER, C0f00CTING STEAM GENERATOR MOISTURE CARRYOVER TESTING. 1 CURIE OF NA-24 TRACER IN FEEDWATER.
"A" SG FEEDWATER REGULATItE VALVE FAILED OPEN, REACTOR TRIP ON HIGH SG "A" LEVEL.
- NORf%L TRIP RESPONSE, EXCEPT STEAM DlNP TO CONDENSER SEEND SLUGGISH.
- SUSPECTED MAIN STEAM CODE SAFETY VALVE OPENING.
LICENSEE DECLARED UNUSUAL EVENT, E W RGENCY PREPAREDNESS PLAN PARTIALLY IMPLEENTED FOR ONSITE Af0 0FFSITE RADIOLOGICAL MONITORING. NONE DETECTED.-
INSPECTION FOLLOWING TRANSIENT IDENTIFIED FEEDWATER VALVE AND PIPING SUPPORT DAMAGE.
IE FOLLOW UP.
l 0 FORT CAlliOUN, APRIL 28, 1981 - PARTIAL LOSS OF D.C.
- PARTIAL LDSS OF DC CAUSED LOSS OF LOAD TRIP, PARTIAL LOSS OF COMPONENT COOLING WATER AND PARTIAL CONTAINMENT ISOLATION.
l
- LOSS OF DC CAUSED BY LOOSE WIRE IN FEEDER PANEL.
l l
- OPERATOR SECURED RCP'S AFTER 4 MINUTES RUN TIfE WITHOUT COMP 0 TENT COOLING WATER.
PLEP VENDOR, BYRON JACKSON, REC 0f4 ENDS MAX.12 MINUTES AT 250 F.
- UNIT ON NATURAL CIRCULATION FOR 2 HOURS USING ATMOSPHERIC DUMPS.
- ALL SYSTEMS APPEARED TO FUNCTION NORT%LLY.
O MONTICELLO, APRIL 27,1981
- LOSS OF OFFSITE. POWER, LOSS OF NORMAL DECAY HEAT REMOVAL DURING REFUELING OUTAGE.
THE "B" RHR LOOP OUT OF SERVICE FOR MAINTENANCE.
THE "A" RHR PLMP BREAKER RACKED OUT mille ENERGlZED, CURRENT SURE TRIPPED OTHER BREAKERS SUPPLIED BY SAME BUS AND THE OUTPUT BREAKER FROM THE AUXILIARY TRANSFORTER. A FIRE STARTED IN THE BREAKER CABINET.
- 0FFSITE PO4ER LOST FOR 10 MINUTES, HEAT UP OF REACTOR COOLANT 0.5 F PER HOUR.
FUEL POOL COOLING SYSTEM WAS USED TO REMOVE DECAY HEAT FROM REACTOR CAVITY.
- THE "B" RHR LOOP RETURNED TO SERVICE IN 8 HOURS.
Q 0 BRUf6 WICK UNIT 1, APRIL 25,1981
- LOSS OF NORt%L DECAY HEAT REMOVAL, COLD SHUTDOWN FOR MAINTENANG OUTAGE.
ONE RHR to0P OUT OF SERVICE FOR f%INTENANG.
WE BAFFLE IN THE OPERATItG RHR HEAT EXCHANGER FAILED, ALLOWING COOLING WATER TO BYPASS THE TLBE BUNDLE.
- BAFFLE FAILURE CAUSED BY HIGH AP 15 PSI ACROSS WE HEAT EXCHAfEER NORMAL OPERATItG AP I PSI. HIGH AP CAUSED BY CLAMS IN THE HEAT EXWAtEER.
DECAY HEAT REMOVED BY SPENT FUEL POOL COOLING SYSTEM.
- HEAT EXCHANGER REPAIRED AND RETURNED TO SERVIG IN 16 HOURS.
O BURNSWICK UNIT 2, M4Y 5,1981 AT MIDNIGHT SHUTTING DOWN, 2 INOPERABLE RfR HEAT EXCHANGERS, DISPLACED BAFFLE IN ONE OF TWO HEAT EXCHANGERS, OfE IN SERVIG OPERATitG AT REDUGD AP ACROSS U-TUBES.
- AT 7:30 AM GROUP I ISOLATION (REACTOR TRIP AND I$lV CLOSURE, USIrs RCIC FOR DECAY HEAT REMNAL).
3 PREVIOUS BAFFLE FAILURES.
IEFOLLOWUP.
, o 3 INADVERTENT SAFETY INJECTIONS INITIATED 3Y SECONDARY SIDE
- SALIM UNIT 2, SHUTDOWN AND COOLING DOWN, DlJP VALVE SETPOINT DRIFT - STEAM LINE AP SI.
- SEQUOYAH UNIT 1, SHUTDOWN TESTING $1V'S HIGH STEAM FLOW AND LOIAVESl.
- SEQUOYAH UNIT 1100% GEtERATOR TRIF TEST PROBLEf1 TRANSFERRING RCP'S - STEAM LINE - AP SI.
O COOPER, APRIL 28,1981
- FAILED TURBINE BLADES, VIBRATIONS EXPERIENCED IN LOW PRESSURE TURBINE.
- 3 BLADES MISSING, SHROUD MISSING FROM A GROUP OF 6 BLADES, NITE BLADES HAVE BROKEN ROOTS.
- SAME TURBINE ROTOR WHIOi WAS GIVEN TEMPORARY FIX IN fARCH OF 1980.
O PAINE YANKEE, MY 2,1981
- REACTOR COOLANT PlfiP SEALS FAILED.
- FAILURE OF #2 AND #3 SEALS.
OPERATION CONTINUING WITH 2 SEALS STILL FUNCTIONING UNTIL REFUELING.
- E4ERGENCY TECH SPEC 5/5/81 TO ALLOW CLOSURE OF LOOP ISOLATION VALVES TO CLOSE FROM CONTROL ROOM IF IECESSARY.
4 iULTIPLE FAlLlRE INFORI% TION ON TE 73 EVENTS DISCUSSED AT OKRATING REACTOR BRIEFINGS DEC 1980-f%Y 1981 INDEPENDENT FAILIEES.
- FAILURES FAILURE RATE 2
5 IN 5 mrmis 3
1 IN 5 mrmis 4
2 IN 5 mrmis 1
5 0 IN 5 mtmis CONSEQUENTIAL FAILURES
- CONSEQUENTIAL FAILURES FAILURE RATE 1
3 IN 5 mNWs 2
1 IN 5 ta mis 3
0 IN 5 mNms t 4 0 IN 5 mrmis
THE FOLLOWING PRELIMINARY TOTIFICAT10tlS RELATING TO BE FOLLOWits ACT10ftS WERE RECEIVED DURitG BE PAST 2 WEEKS.
PtD-I-81-53, PEACH BOTTcM &nT 2 - uNSmEDULED SHUTDOWN.
PtD-I-81-54, BEAVER VALLEY U11T 2 - mSITE FATALITY.
Pto-I-81-55, HADDAM NECK - INADVERTENT TRANSPORT OF CONTAMINATED MATERIAL OFFSITE.
- Pt0-TMI-81-039 THREE Mim ISLAND UNIT 2 - EPICOR-II RESIN liter SHIPK NT.
Pf0-I-81-57, PEACH BOTTOM UNITS 2 AND 3 - RADIOACTIVE WASTE DISmARGE LITE BREAK.
- PfD-I-81-58, PEAW BOTTOM UNITS 2 AND 3 - POSSIBLE STRIKE BY CONTRACT GUARD FORCE.
Pf0-I-81-59, BEAVER VALLEY UNIT 1 - PLAffT TRIP AND UNPLANNED RELEASE -
UNUSUAL EVENT.
- PID-I-81-60, STEPHAN CHEMICAL CO. - EORIUM CONTAMINATION IN MAYWOOD, NEW JERSEY.
- PID-II-81-31, BRUNSWICK UNIT 1 - LOSS OF NORr%L DECAY HEAT REMOVAL.
- Pf6-II-81-07, NUCLEAR PUEL SERVICES, INC. - NUCLEAR FUEL SERVICES APRIL 30,1981 REPORTED INVENTORY DIFFERENCE.
- Pf0-III-81-42, MONTICEU_0 - HPCIS INOPERABLE DUE T0 mECK VALVE FAILURE.
PID-III-81-40C, DUANE ARNOLD - POSSIBLE DEFECTS IN RECIRCULATION j
PIPitG AND EERMAL SLEEVE WELDS.
- PtD-III-81-43, DAVIS-BESSE - PLANT STARTUP AFTER STEAM GEtERATOR REPAIR.
PID-III-81-44, POINT BEACH UNIT 2 - STEN 4 GENERATOR TUBE DEGRADATION.
l l
t
PRELIMitMRY NoTIFICAT10ts (Cot 3D) R0-III-81-45, MoNTICEU.0 - LOSS OF OFFSITE POIER DURING RENF. LING OUTAGE.
RO-IV-31-11, COOPER - FAIED TURBINE BLADES.
R0-V-81-25, SAN ONOFRE UNIT 1 - EARTHQUAKE AT SAN ONOFRE UNIT 1.
RO-V-81-26, SAN ONOFRE UNIT 1 - IfWESTIGATION OF ALLEGED THEFT OF POTENTIALLY CONTAMitMTED HAto TOOLS.
l i
2.~.-
. -.