U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/30/97 - 07/01/97 ** EVENT NUMBERS ** 32417 32559 32560 32561 32562 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32417 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/30/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:44 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/30/97 | +------------------------------------------------+EVENT TIME: 15:00[CDT]| |NRC NOTIFIED BY: CROW |LAST UPDATE DATE: 06/30/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING THE 1997 REFUELING OUTAGE, BOTH TRAINS OF STANDBY GAS TREATMENT | | (SGT) SYSTEM EXCEEDED TECHNICAL SPECIFICATION (TS) UPPER FLOW LIMITS. | | | | ON 04/21/97 AND 04/22/97, THE STANDBY GAS TREATMENT SYSTEM, TRAINS 'A' AND | | 'B' FLOW RATES WERE FOUND TO BE 2,028 AND 2,006 SCFM RESPECTIVELY. THE | | TECH SPEC ACCEPTANCE CRITERIA FOR SGT FLOW IS 1780 SCFM ñ 10% OR 1,602 TO | | 1,958 SCFM RESPECTIVELY. THEREFORE, IN THE AS-FOUND CONDITION, BOTH TRAINS | | EXCEEDED TS UPPER FLOW LIMITS. | | | | WHILE EVALUATION HAS YET TO IDENTIFY A SINGLE FACTOR OR COMBINATION OF | | FACTORS RESULTING IN THE OBSERVED HIGH FLOW RATE, IT HAS BEEN CONCLUDED | | THAT A COMMON CAUSE EXISTS. ACCORDINGLY, THIS CONDITION IS CONSIDERED TO | | BE REPORTABLE AS AN EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE | | FULFILLMENT OF THE SAFETY FUNCTION OF SYSTEMS THAT ARE NEEDED TO CONTROL | | THE RELEASE OF RADIOACTIVE MATERIAL. | | | | PRIOR TO RESTART FROM THIS REFUELING OUTAGE, FLOW DAMPERS WERE ADJUSTED TO | | RETURN FLOW RATES TO WITHIN THE TS LIMITS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | | | | * * * UPDATE AT 1743 ON 06/30/97 FROM GREEN TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE FOLLOWING IS TEXT FROM A | | FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "FURTHER INVESTIGATION DETERMINED THAT THE SGT SYSTEM WOULD HAVE BEEN ABLE | | TO FULFILL ITS DESIGNED SAFETY FUNCTION WHICH IS TO MAINTAIN THE SECONDARY | | CONTAINMENT AT A NEGATIVE PRESSURE OF -0.25" wg WITH A SGT FLOW NOT | | EXCEEDING 1780 cfm (EQUIVALENT TO ONE FREE BUILDING VOLUME CHANGE PER DAY). | | THIS IS THE REQUIREMENT IMPOSED BY THE COOPER ACCIDENT ANALYSIS AND | | REQUIRED BY THE CCOOPER TECHNICAL SPECIFICATION SECTION 4.7.C.1.c. THE | | SURVEILLANCE PROCEDURE WHICH DEMONSTRATES THAT THIS REQUIREMENT IS | | FULFILLED WAS SUCCESSFULLY PERFORMED DURING THE 1995 REFUELING OUTAGE, | | PRIOR TO REFUELING DURING THE 1997 OUTAGE, AND AGAIN FOLLOWING THE DAMPER | | ADJUSTMENT MADE TO BRING THE SGT FAN FLOWS INTO AGREEMENT WITH THE | | TECHNICAL SPECIFICATIONS, SECTION 3.7.B.2.c. CONSEQUENTLY, DURING THE 18 | | MONTH PERIOD, SHOULD ANY ACCIDENT HAVE OCCURRED WHICH SOULD HAVE REQUIRED | | THE SGT SYSTEM TO OPERATE, THE SGT SYSTEM SOULD HAVE PERFORMED ITS DESIGNED | | SAFETY FUNCTION." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | THE OPERATIONS OFFICER NOTIFIED R4DO BILL JONES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32559 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 06/30/97 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 08:42 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/30/97 | +------------------------------------------------+EVENT TIME: 08:24[EDT]| |NRC NOTIFIED BY: MIKE GOOGE |LAST UPDATE DATE: 06/30/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILT SHYMLOCK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION PLANT SHUTDOWN DUE TO CONTAINMENT ISOLATION VACUUM | | BREAKER FAILING TO CLOSE DURING THE PERFORMANCE OF ITS MONTHLY SURVEILLANCE | | TEST. | | | | A REACTOR SHUTDOWN WAS INITIATED AS REQUIRED BY TECHNICAL SPECIFICATION | | 3.6.1.8.C.1 DUE TO STUCK OPEN SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER | | #IT48-F323F. THE REACTOR IS REQUIRED TO BE IN HOT SHUTDOWN BY 1402 EDT | | ON 06/30/97. THE SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER STUCK OPEN | | (IT DOES NOT INDICATE THAT IT CLOSED WHEN THE BREAKER WAS CLOSED AND THERE | | IS NO D/P ACROSS THE VALVE) DURING ITS MONTHLY SURVEILLANCE TEST. | | | | THE EMERGENCY DIESEL GENERATORS AND THE EMERGENCY CORE COOLING SYSTEMS ARE | | FULLY OPERABLE. THE ELECTRICAL GRID IS STABLE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1230 ON 06/30/97 FROM BARNES TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS REPAIRED THE VACUUM BREAKER AND HAS EXITED THE SHUTDOWN | | LCO. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE OPERATIONS | | OFFICER NOTIFIED R2DO MILT SHYMLOCK. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32560 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 06/30/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:03 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 06/30/97 | +------------------------------------------------+EVENT TIME: 14:30[EDT]| |NRC NOTIFIED BY: PIONTKOWSKI |LAST UPDATE DATE: 06/30/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HEAT EXCHANGER CAPACITY DIMINISHED DUE TO FOULING. | | | | THE LICENSEE REPORTED THAT THE HEAT TRANSFER CAPACITY OF THE 'B' SPENT FUEL | | POOL HEAT EXCHANGER HAS DECREASED DUE TO FOULING TO A LEVEL THAT PLACES THE | | UNIT OUTSIDE OF ITS DESIGN BASIS. THE DESIGN SPECIFICATION FOR THE HEAT | | EXCHANGER IS 22.4 MBTU/HR, WHILE ACTUAL CAPACITY IS CURRENTLY APPROXIMATELY | | 10 MBTU/HR. THE CURRENT FUEL POOL HEAT LOAD, WITH ALL FUEL ASSEMBLIES | | REMOVED FROM THE REACTOR AND IN THE POOL, IS 3 MBTU/HR. THE DESIGN | | SPECIFICATION IS TO PERMIT A FULL CORE OFFLOAD FROM A RECENTLY OPERATED | | CORE; THIS UNIT HAS NOT OPERATED IN THE RECENT PAST, AND IS CURRENTLY BEING | | DECOMMISSIONED. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32561 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 06/30/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/30/97 | +------------------------------------------------+EVENT TIME: 12:35[CDT]| |NRC NOTIFIED BY: MIELKE |LAST UPDATE DATE: 06/30/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO POWER DISTRIBUTION CABLES DO NOT MEET 10CFR50, APPENDIX R REQUIREMENTS. | | | | THE LICENSEE HAS IDENTIFIED TWO POWER DISTRIBUTION CABLES, LOCATED IN THE | | AUXILIARY FEEDWATER PUMP ROOM, THAT DO NOT MEET THE REQUIREMENTS OF | | 10CFR50, APPENDIX R, SECTION III.G.2, AND ARE NOT SPECIFICALLY IDENTIFIED | | IN THE NRC APPROVED EXEMPTION FROM APPENDIX R REQUIREMENTS FOR THIS AREA. | | THESE CABLES ARE THE POWER SUPPLY CABLES FROM GAS TURBINE #G05 TO BUSES | | #1B03/1B04, AND THE POWER SUPPLY FROM EDG #G04 TO BUSES #2B04/2B03. | | | | THE LICENSEE REPORTED THAT THESE CABLES DO MEET THE SEPARATION CRITERION | | AND CONDITIONS OF THE APPLICABLE EXEMPTION REQUEST; HOWEVER, THEY WERE NOT | | SPECIFICALLY IDENTIFIED IN THE EXEMPTION REQUEST. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32562 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 06/30/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 19:31 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/30/97 | +------------------------------------------------+EVENT TIME: 17:00[CDT]| |NRC NOTIFIED BY: MIELKE |LAST UPDATE DATE: 06/30/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIALLY DEGRADED PLANT ELECTRICAL BUSES. | | | | BASED ON PRELIMINARY CONSERVATIVE CALCULATIONS, PLANT PERSONNEL HAVE | | IDENTIFIED A NUMBER OF POTENTIALLY DEGRADED PLANT ELECTRICAL BUSES. THESE | | BUSES HAVE THE POTENTIAL TO EXPERIENCE FAULT CURRENTS (DUE TO 3 PHASE | | BOLTED FAULTS) THAT COULD EXCEED MANUFACTURERS' RECOMMENDATIONS ON | | SWITCHGEAR AND/OR BREAKERS, WHICH COULD RENDER THE EQUIPMENT INOPERABLE | | AND/OR CAUSE SECONDARY FIRES. | | | | THE LICENSEE IS CONTINUING TO EVALUATE THIS CONDITION, AND WILL EMPLOY | | COMPENSATORY ACTIONS (FIRE ROUNDS) AS REQUIRED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+