ML20196A920
| ML20196A920 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Sequoyah, Pilgrim, South Texas, 05000000 |
| Issue date: | 06/17/1988 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-88-024, OREM-88-24, NUDOCS 8806300148 | |
| Download: ML20196A920 (15) | |
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i JUM 11 N MEMORANDUM FOR:
Charles E. Rossi. Director Division of Operational Events Assessmcnt Office of Nuclear Reactor Regulation FROM:
Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment g
Office of Nuclear Reactor Regulation SJBJECT:
THE OPERATING REACTORS EVENTS MEETING June 14, 1988 - MEETING 88-24 5
On June 14, 1988 an Operating Reactors Events meeting (88-24) was held to brief senior managers from NRR, OSP, AE00, and Regional Offices on events which occurred since cur last meeting on June 7, 1988. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. presents a sumary of reactor scrams.
Two signif-icant events were identified fer input to NRC':: performance indicator program.
- No events were suggested for long-term followup.
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" e v. r;. t e,w Wayne Lanning. Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/Encio.:
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- *M MEMORANDUlt FOR: Charles E. Rossi. Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation FROM:
Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation
SUBJECT:
THE CPERATING REACTORS EVENTS MEETINC June 14, 1908 - MEETING 88-24 On June 14, 1988 an Operating Reactors Events meeting (88-24) was held to brief senior r, tanagers from NRR, OSP, AEOD and Regional Offices on events which occurred since our last meeting on June 7,1988. The list of attendees is included as Enclosure 1.
The events discussed and the significant elements of these events are presented in Enclosure 2. presents a sumary of reactor scrams. Two signif-r icant events were identificd for input to NRC's performance indicator program.
No events were suggested for long-term followup.
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$fMv)Ss tiv 1M yr4 Lanning. Chie Events Assessment Br nch Division of Operat ial Events Assessment Office of Nuclear Reactor Regulation
Enclosures:
As stated cc w/Er.clo.:
See Next Page 4
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ENCLOSURE'.
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LIST OF ATTENDEES
-OPCRATING REACTORS EVENTS CRIEFING (88-24)
June 14, 1988 NAME ORGANIZATl_0N NAME ORGANIZATIOh W.Lanning IIRR/00EA P. Baranowsky flRR/00EA B. Brach fiRR/0RIS
~R. Scholl NRR/00EA S. Black OSP/TVA E. Rossi f.RR/00EA G. Zech AE00/00A
- 0. Mcdonald NRR/P013 S. Richardson OSP/TVA H. Garg OSP/TVA R. Ciliniberg NRR/ORIS G. Holahan NRR/0RSP
-S. Vietti-Cook OCM/LZ J. Calvo NRR/0RSP
- 0. Tondi NRR/ DEST C. Berlinger NRR/00EA F. Paulitz OSP/TVA W. Minners RES/CRPS F. Rosa NRR/DECT F. Miraglia NRR/ADP G. Dick NRR/0RSP
- 0. Crutchfield hRR/0RSP W. Troskoski DEDR0 J. Sniezek NRR B. Boger NRR/ADR1 M.L.Reardon NRR/00EA l
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ENCLOSURE 2 OPERAI.ING REACTOR _S EVENTS BRIEFING 88-:4 EVENTS ASSESSMENT 3 RANCH LOC AT_LON :
lE-B-11 WHI1E FL Uil TUESDAY, JUNE 14, 1988, 11 : 00 A.M.
BR01:NS FERRY 3 3 EDGS Fall DURING LOOP /LOCA TEST SOUTH TEXAS 1
'hECHANICAL BINDING CAUSES BREAKER FAILURE PILGRIM MOTOR OPERATED VALVE FAILURE SECUOYAH 2 05/13/88 - 06/13/88 SCRANS GENERIC ISSUE BULLETIN 88-05 UPDATE
33-24 BROWNS FERRY UNIT 3 3 EDGs Fall LOP / LOCA_IEST JUNE 5, 1988 PRQ3kER DURIllG A LGP/LOCA TEST'3 0F'4 EDG OUTPUT BREAKERS FAILED TO REMAIN CONNECTED TO THE!R 4160 SHUTDOWN BOARDS.
CAUSE ANTIPUMP RELAY SEALED-IN PREVENTING RECLOSING 0F THE OUTPUT BREAKERS.
SIGNIFICANCE Tlils EVENT REPRESEHTS A CONDITION IN WHICH Tile PLANT DOES NOT MEET THE DESIGN BASIS SHUTDOWN REGUIREMENTS.
DISCUSSION o
LOCA SAFETY INJECTION SIGNAL GENERATED 6 SECONDS AFTER THE LOOP SIGNAL GENERATED c
6 SECOND DELAY CONSISTENT WITH SAFETY ANALYSIS WORST CASE DNB SCENARIO PER APPENDIX K, "ECCS EVALUATION MODEL" REQUIREMENTS o
TEST SCENARIO:
0.0 SEC - 4KV SHUTDOWN BOARD DEENERGlZED.
1.5 SEC - DGS STARl.
5.0 SEC - UNDERVOLTAGE DEVICE TIMES OUT.
BREAKER CLOSURE CIRCulT
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CONTAC.'S CLOSE.
6.5 SEC - DG 3A, 3C, 3D COME TO SPEED AND CLOSE CONTACTS IN BREAKER CLOSURE CIRCulT.
6.5 SEC - DG OUTPUT BREAKER CLOSES WHICH INTURN ENERGIZE 52M AND 52Y RELAYS TO RECHARGE (2 SEC).
BREAKER SPRING CLOSURE 4
L C0ll 52X ISOLATED FROM CIRCulT WillLE 52Y ENERGIZED.
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6.5 SEC - ACCIDENT SIGNAL INJECTED, DG BREAKER 3A, 3C, 3D TRIPPED l
VIA LOCA SIGNAL.
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FAILURE ATTRIBUTED TO GE ANTIPUMP NETWORK LOGIC-CIRCulTRY DESIGNED TO HOLD BREAKER IN LOCK 0UT IF BREAKER SPRING NOT CHARGED.
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CONTACT:
C. SCHULTEN
REFERENCE:
50.72s # 12495 AND 12470 AND MORNING REPORT 06/08/88
BROWNS FERRY 3 E8-24 o
TRACINGS INDICATED EDGs 3A, 3C, AND 3D COTPUT BREAKERS OPENED AT 10, 15, 8 30 CYCLES AND WilEN LOCA SAFETY INJECTION SIGNAL RECElVED AFTER LOP, o
OUTPUT BREAKERS COULD N0' LE CLOSED FROM CONTROL ROOM SWITCHES OR ON AUTO AS REQUIRED.
e 52Y RELAY RESET BY KILLING P0hER TO IT BY SLOW CLOSURE OF C0kTROL ROOM POWER SELECTION SWITCH.
o ANTIPUNP RELAY IS INTERNAL TO THE GE MAGNABLAST, AMH-46, BREAKER-POTENTIALLY APPLICABLE TO SIhlLAR VINTAGE BOILERS E.G.,
- DRESDEN, BRUNSWICl-:, DUANE ARNOLD, AND PWRS, o
TECH, SPECS, REQUIRE LOP IN CONJUNCTION WITH LOCA EVERY 18 MONTHS, FOLLOWUP.
o PART 21 NOTIFICATION BEING CONSIDERED BY TVA.
c ELECTRICAL SYSTEMS BRANCH WILL EVALUATE GENERIC IMPLICATIONS.
88-24 i
Mkh1 TEXAS @JT 1 MECHANICAL BINDING CAUSES BREAKER FAILURE JUNE 10, 1988
-PROBLEM FAILURE OF Th0 DS-410 SAFETY-RELATED CIRCulT BREAKERS TO CLOSE DUE T0 hECHAl;1 CAL BINDING OF CLOS:NG MECHANISM.
CAUSE TRIP LEVER ON CLOSING MECHANISM DID NOT RELEASE CLOSING SFRINGS.
SAFETY SIGNIF.IfMCE FAILURE OF THE BREAKERS TO CLOSE COULD PREVENT VITAL LOADS FROM BEING SECUENCED ONTO THE DIESEL POWERED BUSES.
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DURING LOOP TEST TWO CIRCUIT BREAKERS FAILED TO CLOSE.
o INITIAL INVESTIGATION INDICATED OVERHEATING AND FAILURE OF CLOSURE
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INSPECTION OF A SPARE BREAKER Sil0WED ONLY LIMITED MOVEMENT OF TRIP LEVER.
o INSPECTION OF 24 ADDITIONAL EREAKERS AT SOUTH TEXAS 1 REVEALED TWO OTHERS WITI: BINDING BETWEEN THE TRIP LEVER AND SUFPORT PLATE.
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FURTHER EXAMINATION 0F THE TWO FAILED BREAKERS ALSO SHOWED INDICATIONS OF BINDING.
o SOUTH TEXAS 1 HAS REINSPECTED ALL SAFETY-RELATED DS-416 BREAKERS BOTH ELECTRICALLY AND PHYSICALLY AND IS CONTINUING WITH RESTART.
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THE BREAKER THAT FAILED INSPECTION WAS QUARANTINED AND PARTS OF TliE i
FAILED BREAKERS ALSO RETAINED.
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NRR AND RIV ON SITE TO INSPECT THE FAILED BREAKERS AT SOUTH TEXAS 1.
o WEST!NGil0USE CALLED IN BY LICENSEE.
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NRR F0LLOWUP FOR GENERIC IMPLICATIONS.
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l CONTACT:
G. DICK i
REFERENCE:
50.72 il 12513 AND MORNING REPORT 06/10/88
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ee-2u PILGRib MOTOR OPEPATE.D VALVE FAltVPE JUNE 7, 1988 PR03t[t' Y0KE ON PORIZONTALLY h0bNTED POTOR' OPERATED
.LVE CRACKED AND FLOW RATE TI,RCUGH THE VALVE CHANGED UNEXPECTEDLY, CAUSE
- UNKNOWN, SIGNIFICANCE FUNCTIONAL CAPAEiliTY OF RHR ISOLATION VALVES IS SUSPECT AND POTENT:AL F0k FRlhARY COOLANT LEAKAGE NEEDS TO BE ASSESSED, DISCUSSION O
PLANT IN COLD SHUTDOWN WITH NO DECAY HEAT.
0 18" MOV WAS CLOSED AND OPENED AS PART OF UNRELATED SURVEILLANCE, o
FAILURE OVER 270* AT WELD OF YOKE TO OPERATOR. FLANGE, o
CHECK OF ANOTHER VALVE SHOWED INDICATION AT DIFFERENT LOCATION, u
EVENT REPORTED ON LOCAL RADIO AND IN NEWSPAPERS PRIOR TO NOTIFYING
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- hRC, EOLLOWUE VALVE YOKE IS UNIQUE TO THESE TWO VALVES.
THEREFORE, PROJECT MANAGER WILL h0NITOR ROOT CAUSE DETERMINATION AND LICENSEE PROPOSED FIX, CONTACT:
J. CARTER
REFERENCE:
50,72 # 12522 l
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88-24:
SEOUOYAH 2 SCRAMS' 05/13/88 - 06/13/88
~CAUSE DA_TL POWER LEVEL.
T PERSONN'tL/EGUIPMENT 05/19/88 49%
S/G LEVEL CONTROL PERSONNEL / PROCEDURAL 05/23/88 70%
EQUIPMENT 06/06/88 98%
FW REG VALVE PERSONNEL / PROCEDURAL 06/08/88 12%
EQUIPMENT 06/09/88 17%
FW HEATER LEVEL CONTROL
-PLANT SHUTDOWN AS OF 06/09/88, LICENSEE TO DISCUSS RESTART IN HEADQUARTERS ON 06/13/88.
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CONTACT:
D. OUDIN0T l
1 88-24 GENERI.C__I SSUE BULLETIN.fE-05 UPDAIE SilEARON HARRIS;J.ESLRESUL.TS._0tLERL.S.UPEllED MAIERIALS PROBLEM TWO FLAf10ES FiCL ASFE STRENGTH AND CHEhlCAL REGUIREMENTS,
.CAUSE FALSIFIED f!ATERIAL CERTIFICATION, SAFET.Y. S.lGNIFICANCE LOW STRENGTH MATERIAL IN ASME CODE CLASS SYSTEMS CCULD RESULT IN FAILURE OF Tile PRESSURE EOUliDARY AND LOSS OF COOLANT, DISCUS $10N o
SHEARON HARRIS IDENTIFIED L1 HEATS OF WEST JERSEY (WJM) SUPPLIED
- FLANGES, OF THE 21 HEATS, 11 IIEATS WERE INSTALLED IN Tl!E SERVICE WATER AND AUXILIARY FEEDWATER SYSTEMS, NINE IIEATS WERE DISPCSED AT.END OF C0fiSTRUCT!0fl.
TWO FLANGES FROM ONE HEAT (7218) WERE IN WARE!!GUSE.
o TEST RESULTS ON TWO FLANGES FROM HEAT 7218 FAILED ASME REQUIREMENT 3.
MEASURED TENSILE STRENGTH IS 45KSI AND 4CKSl; CNTR REPORTED 77KSI; NINIMUM REGUIRED IS 70KSI, MEASURED YIELD IS 27KSI AND 31KSI; CMTR REPORTED 50KSl; MINIMUM RECU! RED 36KSI, MEASURED CHEMISTRY IS OUT-OF-SPECIFICATION, PERCENT CARBCN MEASURED TO BE VERY LOW AT 0,045 (ASME REQUIRED MAXIMUM IS 0.35)
AliD PERCENT MANGANESE i,EASURED AT 0.32 (ASME REGUIRED RANGE IS 0.6 TO 1,05),
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C0flFIRM SHEARON HARRIS REPORT T0 INP0 NUCLEAR I4ETWORK, o
NRC INFGRMATICN TO NUMARC, o
BULLETIll.88-05 SUPPLEMENT, o
NRC TO COMPLETE REVIEW 0F WJM RECCRDS, CONTACT:
R CILIMBERG
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. it 06/0!!!! E.E:!EN'.Y Dl!!EL SENEEATORS FAILED TO FEMAIN lCNkE*iED TO 0 F0iENTI A'. FCR 0: A:Tt:. [E3::::T!:N
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