ML20195H027
| ML20195H027 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Wolf Creek, Brunswick, 05000000 |
| Issue date: | 11/25/1988 |
| From: | Lanning W Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-88-046, OREM-88-46, NUDOCS 8811300193 | |
| Download: ML20195H027 (11) | |
Text
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NOV 2 51988 MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING Novembe.- 22, 1988 - MEETING 88-46 On November 22, 1988, an Operating Reactors Events meeting (88-46) was held to brief senior managers from NRR, AE0D, OSP, RES, Comission Staff, and Regional Offices on events which occurred since our last meeting on November 15, 1988.
The list of attendees is included as Enclosure 1.
The events discussed and the sigr>1ficant elements of these events are presented in Enclosure 2. presents a sumary of reactor scrams. No significant events were identified for input to NRC's performance indicator program.
0?iginal sumed h h yue D, toe.g,
Wayn3 D. Lanning, Chief f
Events Assessment Branch L
Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page 6'l DISTRIBUTION
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- 8. Davis, RIII R. D. Martin, RIV J. B. Martin, RV W. Kane, RI L. Reyes, RII E. Greenman, RIII L. Callan, RIV D. Kirsch, RV S. Varga, 14E-4 D. Crutchfield,13A-2 B. Boger, 14A-2 G. Lainas, 14H-3 G. Holahan, 13H-4 L. Shao, 8E-2 J. Partlow, 70-24 B. Grimes, 9A-2 F. Congel, 10E-4 E. Weiss, AEOD T. Martin, E00 J. Guttmann, SECY A. Thadani, 7E-4 S. Rubin, A200 J. Forsyth, INP0 R. Barrett, 10E-2 M. Harper, MNBB 4210 1
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j WASHINGTON. D. C. 20656 NOV s W MEMORANDUM FOR:
Chai.
E. Rossi, Director Division of Operational Events Assessment FROM:
Wayne D. Lanning, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING. REACTORS EVENTS MEETING Hovember 22, 1988 - MEETING 88-46 On November 22, 1988, an Operating Reactors Events meeting (88-46) was held to brief senior managers from NRR, AE00, OSP, RES, Comission Staff, and Regional Offices on events which occurred since our last meeting on November 15, 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.
No significant events were identified for input to NRC's performance indicator
- program, pp f=
Wayqe D. Lanning, Chie Events Assessment Bran Division of Operational ts Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page e
W e
+-
.o ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-46)
November 22, 1988 NAME ORGANIZATION NAME ORGANIZATION C.E. Rossi NRR/00EA S. Varga NRR/DRP B..Boger NRR/ADRI P. Baranowsky NRR/00EA R. Capra NRR/PD1-4 C. Berlinger NRR/00EA W. Lanring NRR/00EA B. Grimes NRR/DRIS C. Haughney NRR/DRIS J. Roe NRR/DLPQ C. Schulten NRR/00EA M.L. Reardon NRR/00EA G. Lainas NRR/DRP E. Adensam NRR/PD2-1 J. Guttmann SECY M. Fields OSP D. LaBarge NRR/DRP O
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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-46 EVENTS ASSESSMENT BRANCH LOCATION:
12-B-11 WHITE FLINT TUESDAY, NOVEMBER 22, 1988, 11:00 A.M.
WOLF CREEK CONTROL RODS CLADDING PROBLEMS PEACH BOTTOM UNITS 2 & 3 P0TENTIILCOMMONMODEFAILURE OF EDGs OUTPUT BREAKERS ON A SEISMIC EVENT BRUNSWICK UNITS 1 a 2 SCRAM WITH SUBSEQUENT EQUIPMENT MALFUNCTION j
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88-46 WOLF CREEK CON 1ROL RODS CLADDING PROBLEMS NOVEMBER 8, 1988 PROBLEM PLANNED INSPECTION DURING REFUELING OUTAGE REVEALED UNEXPECTED SWELLING OF CONTROL R0D CLADDING, CAUSE UNKNOWN SAEETY SIGNIFICANCE POTENTIAL FOR CONTROL R0D CLADDING FAILURE, DISCUSSION o
WOLF CREEK IN SHUTDOWN FOR THIRD REFUELING OUTAGE, o
VISUAL INSPECTION REQUIRED DUE TO NEW DESIGN OF RODS USING HAFNIUM VERSUS SILVER - INDI;UM - CADMlUM, o
PRESENCE OF HAFNIUM IN REACTOR COOLANT AND RESULTS OF CALLAWAY TESTING IN 1987 PROMPT LICENSEE TO PERFORM EDDY CURRENT TESTING, o
TEST RESULTS SHOW UNEXPECTED INDICATIONS ON INSIDE SURFACE OF
- CLADDING, PROFILOMETRY REVEALED SWELLING ON OUTSIDE SURFACE, o
INDICATIONS AND SWELLING SEEN TO COINCIDE, o
ALMOST ALL R0D CLUSTER CONTROL ASSEMBLIES (RCCAs) ARE AFFECTED, o
LICENSEE REPLACING ALL RCCAs WITH NEW RCCAs OBTAINED FROM COMANCHE PEAK, o
ONE SELECTED R0D TO BE SENT TO H LAB FOR HOT CELL TESTING - RESULTS EXPECTED BY END OF 1988, o
RESULTS OF 1987 EDDY CURRENT TESTING AT CALLAWAY TO BE REASSESSED IN VIEW 0F WOLF CREEK RECENT PROBLEMS, o
FOURTEEN PWRs AND TWENTY BWRs ARE CURRENTLY EQUIPPED WITH HAFNIUM
- RODS, FOLLOWUE' o
EAB FOLLOWING UP, o
X TO ASSESS SAFETY SIGNIFICANCE OF CONTROL RODS CLADDING PROBLEMS BY 11/22/88.
CONTACT:
D, OUDIN0T
REFERENCE:
MORNING REPORT 11/08/88
i 88-46 PEACH BOTTOM UNITS 2 & 3 POTENTIAL COMMON MODE FAILURE OF EDGs 0UTPUT BREAKERS ON A SEISMIC EVENT SEPTEMBER 15, 1988 PROBLEM DISCOVERY OF A GENERIC DEFECT THAT MAY PREVENT THE PROPER OPERATION OF 4160 VAC EMERGENCY BUS BREAKERS DURING A SEISMIC EVENT.
CAUSE GENERIC DEFECT ON GENERAL ELECTRIC MANUFACTURED BREAKERS, MODELS M26, M36, AND AM4.16-250.
FAILURE TO RECEIVE AND IMPLEMENT GE SERVICE ADVISORY LET1ER (SAL) 073B-302.0 SAFETY SIGNIFICANCE HAD THIS CONDITION EXISTED DURING A SEISMIC EVENT WITH THE NEED FOR EMERGENCY POWER, IT IS POSSIBLE THAT ONE OR MORE OF THE EMERGENCY DIESEL GENERATORS WOULD BE UNAVAILABLE, RESULTING IN A PARTIAL OR TOTAL STATION BLACK 0UT.
DISCUS.SIDH o
DAMAGE OCCURS UPON ROLLING THE BREAKER OUT OF CABINET.
o CELL SWITCH CONTROL LINKAGE OCCASIONALLY INTERFERES WITH BREAKER ASSEMBLY WHEN REMOVED FROM ITS CUBICLE.
o UPON RACKING BREAKER IN, HAD N0 INDICATION OF BREAKER POSITION IN THE CONTROL ROOM.
o THE FAILURE OF THE LINKAGE DISABLES AUTOMATIC AND MANU/'. CLOSURE CIRCUITRY.
o OTHER 4.16KV BREAKER COMPARTMENTS CONTAINED DIST0RTED LINKAGES.
o LICENSEE DETERMINED THAT THERE WAS INADEQUATE ENGAGEMENT TO ENSURE LINKAGE INTEGRITY DURING A SEISMIC EVENT WHICH WOULD ELECTRICALLY DISABLE THE BREAKER.
o FAILURE OF THESE BREAKERS USED ON THE EDG's COULD RESULT IN PARTIAL OR TOTAL SB DURING A SEISM,1C EVENT.
o NPRDS SEARCH OF GE MODEL AM4.16KV BREAKERS REVEALED TWO OTHER CELL SWITCH DISENGAGEMENT FAILURES.
CONTACT:
J. RALEIGH
REFERENCE:
.50.72 # 13488 AND LER # 88-022
2-88-46 PEACH BOTTOM UNITS 2 & 3 o
THESE FAILURES WERE ALSO RELATED TO MAINTENANCE, o
GE SAL OF 1973 NEVER RECEIVED BY PECO WHICH CONTAINED BREAKER UPGRADES TO PREVENT PROBLEM.
o GE UPGRADE KITS WILL BE INSTALLED OVER NEXT 3 REFUELING OUTAGES.
O A TOTAL OF 6.8 BREAKERS INVOLVED.
LOOKED AT 50:
3 FAILED AND 2 PARTIAL FAILURES.
O BREAKERS WILL BE FUNCTIONALLY TESTED UPON ROLLING BREAKER IN.
o OPERATORS HAVE BEEN TRAINED lil REC 0VERY ACTIONS AS WELL AS MECHANICALLY OPERATING THESE BREAKERS WHEN CONTROL POWER IS UNAVAILABLE.
FOLLOWUP EAB WILL ASSESS THE NEED FOR GENERIC NOTIFICATIONS AS APPROPRIATE.
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88-46 e
BRUNSWICK UNITS'1 & 2 SCRAM WITH SUBSEQUENT EQUIPMENT MALFUNCTIOR NOVEMBER 16, 1988 PROBLEM INVERTER POWER SUPPLY INTERRUPTED LEADING TO A REAC1")R TRIPS ADDITIONAL OPERATING PROBLEMS WERE SUBSEQUENTLY NOTED.
CAUSE HIGH VOLTAGE TRIP SETPOINT OF THE RECEflTLY REPLACED INVERTER HAD DRIFTED DOWNWARD.
SAFETY SIGNIFICANCE ONG0ING PROBLEMS.
DISCUSSION UNIT 2 WAS OPERATING AT 100% POWER, o
INVERTER TRIPPED WHILE CONDUCTING AN EQUALIZING CHARGE OF THE "1B" BATTERY.
o POWER LOST TO ONE OF TWO FEEDWATER FLOW INSTRUMENTS AND ONE OF FOUR STEAM FLOW INSTRUMEfiTS RESULTING IN FLOW MISMATCH.
o BOTH FEEDWATER PUMP AND MAIN TURBINE TRIPPED ON HIGH REACTOR VESSEL.
LEVEL.
O SUBSEQUENT ANOMALIES WERE:
HPCI INJECTION VALVE NOT OPENING, ONE CONTROL R0D DID NOT GO TO "00",
ONE MSIV IN AN INTERMEDIATE POSITION FOR 5 MINUTES, START-UP LEVEL CONTROL VALVE DID NOT OPEN.
UNIT 1 IS REFUELING:
o UNABLE TO PRESSURIZE BETWEEN 2 MSIVs.
)
o LEAKAGE PAST OUTBOARD VA1.VE OF ANOTHER PAIR OF MSIVs EXCEEDED 53 SCFH (LIMIT IS 11.5).
FOLLOWUE o
RESIDENT INSPECTORS FOLLOWING RECENT EVENTS, i
CONTACT:
J. CARTER
REFERENCE:
50.72 #'s 14007, 14009, 13999, AND 14013
a.
,BRUN'SWICK 1 88-46 t
THREE ASSIGNED ONSITE.
ONE ADDITICNAL SCHEDULED, o
CP&L HAS REVIEWED PRIOR OVERALL 0PERATION.
RECOMMENDATIONS HAVE BEEN MADE, DISCUSSED WITH REGIONAL ADMINISTRATOR (11/15/88).
i
, STAFF HAS SENT LETTER TO LICENSEE REGARDING ACYIONS TO BE TAKEN BY CP&L.
MEETING SCHEDULED WITH HEAD 00ARTEPS (11/22/88),
o CPal-HAS ENGAGED MANAGEMENT CONSULTING FIRM (CRESAP),
O SALP ASSESSMENT RECENTLY COMPLETED, 1
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1EACTOR SCRAM
SUMMARY
ENCLOSURE 3 4 a WEEX EMll d 11/20/3 7
- 1. PLANT SPECIFIC DATA DATE SITE UNIT PONER $16NAL CAUSE COMPLI-YTD YTD Yil CAi!DNS ABOVE DELOW TOTAL 151 151 11/14/88 CALVERT CLIFFS 1
70 M PERSONNEL N0 3
0 3
l 11/14/89 OCONEE 3
100 A EQUIPMENT NO 2
0 2
11/14/88 OCONEE 3
39 A EDVIPMENT N0 3
0 3
11/15/98 MA!DWOOD 1
95 M EQUIPMENT N0 3
0 3
11/15/88 MAltbOOD 2
80 M EDUlPMENT NO 10 4
14 11/16/88 PALD VERIE 2
10 A EQUIPMENT NO 0
1 1
11/16/88 BRUNSWICK 2
100 a E001PMENT NO 2
1 3
!!/17/81 M AltWOOD 2
6A PERSONwEL N"
10 5
15 l
11/18/88 SEQUOYAH 1
72 A EDU!FMENT NO 1
1 2
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