U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/16/95 - 05/17/95 ** EVENT NUMBERS ** 28729 28791 28808 28809 28810 28811 28812 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28729 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/26/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:37 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/26/95 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: SCOTT |LAST UPDATE DATE: 05/16/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 93 POWER OPERATION | 93 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED AN LCO ACTION STATEMENT TO BE IN COLD SHUTDOWN IN 24HRS | | DUE TO BOTH CORE SPRAY PUMPS BEING INOPERABLE. | | | | THIS WAS DETERMINED WHEN THEY DISCOVERED THAT THE FLOW TRANSMITTERS, WHICH | | CONTROL THE MINIMUM FLOW VALVES FOR BOTH CORE SPRAY PUMPS, WERE INOPERABLE | | DUE TO AN INCOMPLETE SURVEILLANCE. THE "O" RINGS HAD NOT BEEN REPLACED AS | | REQUIRED BY THE SURVEILLANCE PROCEDURE, MAKING THE TRANSMITTERS NOT | | ENVIRONMENTALLY QUALIFIED. THE FIRST TRANSMITTER WAS MADE INOPERABLE | | 4/25/95 @ 17:37 AND THE SECOND MADE INOPERABLE 4/25/95 @ 20:53 AT WHICH | | TIME BOTH CORE SPRAY LOOPS WERE DECLARED INOPERABLE. THIS CONDITION PUT | | THEM IN A 24 HR TO COLD S/D LCO ACTION STATEMENT. AT 16:06 ON 4/26/95 THE | | "B" CORE SPRAY LOOP FLOW TRANSMITTER "O" RING WAS REPLACED. THE "B" CORE | | SPRAY LOOP WAS THEN DECLARED OPERABLE, ENDING THE 24 HR S/D LCO. THEY ARE | | NOW IN A 7 DAY LCO AND ATTEMPTING TO REPAIR THE "A" LOOP FLOW TRANSMITTER. | | THE RI WAS INFORMED. | | | | **** RETRACTION BY Mr. WELCH @ 1715 EDT 05/16/95 TAKEN BY MACKINNON**** | | | | ON FURTHER ENGINEERING EVALUATION IT HAS BEEN DETERMINED THAT THE O-RINGS | | ONLY NEED TO BE REPLACED WHEN DAMAGED. INSPECTION OF THE TRANSMITTER | | O-RINGS FOUND THEM TO BE IN EXCELLENT CONDITION. THERE WERE NO GOUGES, | | NICKS, BENDS, COMPRESSIONS, OR OTHER INDICATIONS OF AGING. IT WAS FOUND | | THAT THE HOUSING COVERS WERE INSTALLED AND HAND TIGHT TO THE POINT WHERE A | | CERTAIN AMOUNT OF O-RING COMPRESSION WAS OBTAINED. ROSEMOUNT HAS SUBJECTED | | THEIR TRANSMITTERS TO LOCA/HELB TESTING WITH COVERS THAT WERE HAND | | TIGHTENED AND NO PROBLEMS WERE ENCOUNTERED. THEREFORE THE TRANSMITTERS WERE | | NEVER INOPERABLE DUE TO THE EQ CONCERNS. R3DO (PAT HILAND) NOTIFIED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28791 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 05/11/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 15:41 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 05/11/95 | +------------------------------------------------+EVENT TIME: 09:00[CDT]| |NRC NOTIFIED BY: RICK PULEC |LAST UPDATE DATE: 05/16/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES LYNCH RDO | |BPE2 20.403(b)(1) PERS EXPOS > 5REM WB | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 24 HOUR REPORT DUE TO AN OCCUPATIONAL EXPOSURE EXCEEDING THE | | LIMITS OF 10CFR20.1201(2)(ii). | | | | ON 5/10/95 AT APPROXIMATELY 0035 CDT, A PLANT MECHANIC FOUND A HOT PARTICLE | | OF PRIMARILY Co60 ON HIS NECK. HE HAD BEEN COMPLETING REPLACEMENT OF STEAM | | GENERATOR MANWAYS. PRELIMINARY ASSESSMENT OF THE SHALLOW DOSE EQUIVALENT | | IS ESTIMATED AT 65 REM. THIS IS GREATER THAN THE 50 REM REPORTING | | THRESHOLD IN 20.1201(2)(ii). THE HOT PARTICLE WAS REMOVED UPON DISCOVERY. | | THE LICENSEE'S INITIAL METHOD FOR ESTIMATING THE DOSE MAY BE OVERLY | | CONSERVATIVE DUE TO THE COUNTING GEOMETRY AND THE DISPERSION OF THE SOURCE | | IN THE SOLVENT. THEREFORE, THE LICENSEE MAY RETRACT THIS EVENT IF A MORE | | PRECISE RECOMPUTATION DETERMINES THAT THE 50 REM THRESHOLD WAS NOT | | EXCEEDED. THE MECHANIC HAS BEEN REASSIGNED TO NON-RADIOLOGICAL WORK. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | | | **** RETRACTION OF EVENT BY RICK PULEC @ 1615 EDT 5/16/95 TAKEN BY | | MACKINNON**** | | | | LICENSEE IS RETRACTING THIS EVENT BECAUSE THE CALCULATED DEEP SKIN EXPOSURE | | DOSE TO THE MECHANIC WAS 5.422 RADs. REPORTING THRESHOLD IS 50 RADs. | | THEREFORE LICENSEE IS RETRACTING THIS EVENT. R3DO (PAT HILAND) NOTIFIED. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28808 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 05/16/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 12:24 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/16/95 | +------------------------------------------------+EVENT TIME: 10:20[CDT]| |NRC NOTIFIED BY: M STRACKA |LAST UPDATE DATE: 05/16/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAT HILAND RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |BOB DENNIG EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SHUTDOWN BASED ON EVALUATION OF STEAM GENERATOR | | INSPECTION DATA TAKEN IN THE FALL OF 1993 MAY NOT BE IN COMPLIANCE WITH | | TECH SPEC 3.3.1.b. (INSPECTION OF STEAM GENERATOR TUBES & EVALUATION OF | | DATA). | | | | BASED ON EVALUATION OF STEAM GENERATOR INSPECTION DATA TAKEN IN FALL OF | | 1993 IT HAS BEEN DETERMINED THAT THEY CANNOT SAY WITH CERTAINTY THAT UNIT 1 | | IS IN COMPLIANCE WITH TECHNICAL SPECIFICATION 3.3.1.b (INSPECTION OF STEAM | | GENERATOR TUBES & EVALUATION OF STEAM GENERATOR TUBE DATA). LICENSEE USED A | | ROTATING PANCAKE COIL FOR THEIR LAST INSPECTION OF THEIR STEAM GENERATOR | | TUBES. THEY RECEIVED INDICATIONS USING THE ROTATING PANCAKE COIL ON 154 OF | | ALL THEIR STEAM GENERATOR TUBES. ALL 154 OF THE INDICATIONS WERE IN THE | | ROLL TRANSITION AREA OF THE TUBE SHEET. LICENSEE FAILED TO RECOGNIZE THAT | | THE AFOREMENTIONED INDICATIONS ALMOST ALWAYS MEAN THAT THE TUBES HAVE A | | FLAW THAT IS GREATER THAN 40% OF THE TUBE WALL THICKNESS. LICENSEE ENTERED | | TECHNICAL SPECIFICATION 3.0.3 (MOTHERHOOD STATEMENT) AT 1020 CDT. THEY HAVE | | TO BE IN A HOT SHUTDOWN CONDITION BY 1520 CDT. ALL THEIR EMERGENCY CORE | | COOLING SYSTEMS & THEIR EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF | | NEEDED. LICENSEE SAID THAT THEY ARE PURSUING ENFORCEMENT DISCRETION. | | LICENSEE SAID THAT STEAM GENERATOR "1C" HAS APPROXIMATELY 110 OF THE 154 | | SUSPECTED STEAM GENERATOR TUBES. LICENSEE DOES NOT KNOW HOW THE ABOVE | | MENTION PROBLEM WAS FOUND. UNIT 2 IS NOT AFFECTED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ****UPDATE FROM MARK STRACKA @ 1345 05/16/95 TAKEN BY MACKINNON**** | | | | LICENSEE RECEIVED ENFORCEMENT DISCRETION FROM REGION 3 AND ARE RELIEVED | | FROM TECHNICAL SPECIFICATION 3.0.3 REQUIREMENTS. LICENSEE STOPPED THEIR | | POWER REDUCTION AT A POWER LEVEL OF 71%. THEY WILL STABILIZE REACTOR POWER | | THEN RETURN TO FULL POWER OPERATION. R3DO (PAT HILAND) NOTIFIED. RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28809 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/16/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 14:48 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/16/95 | +------------------------------------------------+EVENT TIME: 14:24[EDT]| |NRC NOTIFIED BY: DUFFY |LAST UPDATE DATE: 05/16/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY DOERFLEIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PARTIAL ENGINEERED SAFETY FEATURES (EFS) ACTUATION WHILE REMOVING ESF | | ACTUATION CABINET # 5 FROM SERVICE PER A TROUBLESHOOTING PROCEDURE. | | | | LICENSEE REMOVED ESF ACTUATION CABINET # 5 FROM SERVICE TO TROUBLESHOOT A | | PROBLEM WITH THEIR EMERGENCY DIESEL GENERATOR LOAD SEQUENCER. AS THEY WERE | | REMOVING THE ESF ACTUATION CABINET BLOCK FUSES (BLOCK ESF SIGNAL) ONE OF | | THE FUSES JIGGLED IN ITS HOLDER, BROKE, AND MADE CONTACT WITH THE HOLDER. | | THE FUSE BREAKING AND MAKING CONTACT WITH THE BLOCK FUSE HOLDER INITIATED A | | PARTIAL ESF ACTUATION. LICENSEE RECEIVED ENCLOSURE BUILDING FILTRATION | | SYSTEM ACTUATION (EBFS) AND A CONTAINMENT ISOLATION ACTUATION SIGNAL | | (CIAS). THE ESF ACTUATION THAT THE LICENSEE IS REPORTING IS THE CONTAINMENT | | VENTILATION RADIATION MONITOR FAN TRIPPED. ALL SYSTEMS HAVE BEEN RETURNED | | TO THEIR PROPER LINEUP. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28810 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 05/16/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 16:06 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 05/16/95 | +------------------------------------------------+EVENT TIME: 11:35[CDT]| |NRC NOTIFIED BY: TOM WEB |LAST UPDATE DATE: 05/16/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAT HILAND RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 5 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NUCLEAR CONTROL OPERATOR ERROR CAUSED A REACTOR TRIP. | | | | LICENSEE WAS STARTING UP WITH REACTOR POWER AT 5%. LICENSEE WAS PERFORMING | | SURVEILLANCE PROCEDURE 54-064 (TURBINE OVERSPEED TRIP TEST) AFTER | | COMPLETING THEIR REFUELING OUTAGE. DURING THE PERFORMANCE OF THE | | SURVEILLANCE TEST PROCEDURE, A NUCLEAR CONTROL OPERATOR (NCO) MISPOSITIONED | | THE OVERSPEED PROTECTION & CONTROL SWITCH WHICH CAUSED THE STEAM CONTROL | | VALVES TO GO CLOSED. WHEN THE NCO & OPERATIONS PERSONNEL ATTEMPTED TO | | REOPEN THE STEAM CONTROL VALVES, THE REACTOR TRIPPED DUE TO STEAM FLOW > | | FEEDWATER FLOW COINCIDENT WITH LOW STEAM GENERATOR WATER LEVEL IN STEAM | | GENERATOR "B" (LESS THAN 25% NARROW RANGE). ALL RODS FULLY INSERTED INTO | | THE CORE. NCOs MANUALLY TOOK MAIN FEEDWATER PUMPS OFF LINE AND STARTED | | AUXILIARY FEEDWATER (USED ALSO AS STARTUP FEEDWATER) TO INCREASE STEAM | | GENERATOR WATER LEVELS. LICENSEE WILL RESTART LATER TODAY AND PERFORM THE | | TURBINE OVERSPEED TEST. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28811 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 05/16/95 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 17:59 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/16/95 | +------------------------------------------------+EVENT TIME: 09:10[CDT]| |NRC NOTIFIED BY: GRAIG JOHNSON |LAST UPDATE DATE: 05/16/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAT HILAND RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSED OPERATOR TESTED POSITIVE FOR ALCOHOL. | | | | Mr. JOHNSON OF NORTHERN STATE POWER CALLED IN THIS FITNESS FOR DUTY REPORT. | | | | A LICENSED OPERATOR AT MONTICELLO NUCLEAR POWER PLANT TESTED POSITIVE FOR | | ALCOHOL DURING A RANDOM DRUG & ALCOHOL TEST AT 0910 CDT. HIS FIRST ALCOHOL | | LEVEL WAS .057 AND THE SECOND (CONFIRMATORY) ALCOHOL TEST SHOWED A ALCOHOL | | LEVEL OF .063. HE WAS RELIEVED OF HIS DUTIES AN DENIED ACCESS TO ALL | | NORTHERN STATE POWER PLANTS. INVESTIGATION SHOWED THAT HE DID NOT POSE ANY | | DANGER TO THE PLANT. SEE HOO LOG FOR FURTHER DETAILS. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28812 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 05/16/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 21:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/16/95 | +------------------------------------------------+EVENT TIME: 21:22[EDT]| |NRC NOTIFIED BY: GWIRTZ |LAST UPDATE DATE: 05/16/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY DOERFLEIN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SHUTDOWN DUE TO # 12 & # 13 SWITCHGEAR ROOM SUPPLY | | FANS BEING INOPERABLE ALONG WITH THE ASSUMED SINGLE FAILURE OF # 11 | | SWITCHGEAR SUPPLY FAILING DURING A DESIGN BASIS ACCIDENT. | | | | LICENSEE ENTERED TECH SPEC 3.0.3 AT 2122 EDT AND BEGAN A UNIT SHUTDOWN TO | | COMPLY WITH TECH SPEC ACTION STATEMENT AT 2126 EDT. TECH SPEC 3.0.3 WAS | | ENTERED DUE TO INABILITY TO JUSTIFY CONTINUED OPERATION WITH # 12 & # 13 | | SWITCHGEAR ROOM SUPPLY FANS INOPERABLE. # 12 SWITCHGEAR ROOM SUPPLY FAN HAS | | BEEN TAGGED OUT OF SERVICE FOR A COUPLE OF MONTHS DUE TO A BAD MOTOR | | BEARING. LICENSEE IS UNABLE TO FIND A MOTOR BEARING FOR THE SUPPLY FAN. # | | 13 SWITCHGEAR SUPPLY FAN TRIPPED ON OVERLOAD ON 5/13/95 AND A PHASE-TO- | | GROUND SHORT TO THE MOTOR WAS FOUND. AREAS SERVICED BY THE SWITCHGEAR | | VENTILATION SYSTEMS INCLUDE 64' & 84' SWITCHGEAR ROOMS, 78' ELECTRICAL | | PENETRATION AND 100' CHILLER ROOM. DESIGN BASIS TEMPERATURE OF 105 DEGREES | | F COULD BE EXCEEDED IN THESE ROOMS DURING ACCIDENT CONDITIONS WITH A LOSS | | OF THEIR ONLY REMAINING SWITCHGEAR SUPPLY FAN (# 11). COMPONENTS IN THESE | | ROOMS INCLUDE "1A", "1B", "1C" 460, 230 VAC VITAL TRANSFORMERS AND BUSES, | | 28/125 VDC BATTERY CHARGERS AND BUSES, CHILLED WATER PUMPS AND CHILLER | | COMPRESSORS, AND "1C" 125 VDC BATTERY. OPERABILITY OF THESE COMPONENTS CAN | | NOT BE JUSTIFIED THEREFORE TECH SPEC 3.0.3 WAS ENTERED. REPAIRS ARE IN | | PROGRESS ON # 12 SWITCHGEAR SUPPLY FAN AND ESTIMATED TIME TO COMPLETE | | REPAIRING IT IS 56 HOURS. THEIR IS NO TECH SPEC FOR THESE FANS. ALL THEIR | | EMERGENCY CORE COOLING SYSTEMS AND THEIR EMERGENCY DIESELS ARE OPERABLE. | | LICENSEE HAS TO BE IN HOT STANDBY BY 0422 EDT ON 5/17/95. NUCLEAR | | ENGINEERING IS RUNNING COMPUTER MODELS TO FIND OUT IF THEY CAN FIND A WAY | | TO KEEP THESE SWITCHGEAR ROOMS COOL BEFORE THEY SHUTDOWN. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+