U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/14/95 - 03/15/95 ** EVENT NUMBERS ** 28411 28521 28522 28523 28524 28525 28526 28527 28528 28529 28530 28531 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28411 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/20/95 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 02:20 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 02/18/95 | +------------------------------------------------+EVENT TIME: 04:00[MST]| |NRC NOTIFIED BY: GRIGSBY |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STARTUP (S/U) STRAINERS FOUND INSTALLED ON THE INLET SPOOL PIECE OF BOTH | | CONTAINMENT SPRAY (CS) PUMPS, "A" & "B". THIS CONDITION HAS EXISTED SINCE | | INITIAL STARTUP TESTING PERFORMED IN 1984. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE. | | | | "ON 02/17/95 AT 0330, A S/U STRAINER WAS FOUND INSTALLED ON THE INLET SPOOL | | PIECE OF "B" CS PUMP. ON 02/18/95 AT 0400, THE SAME CONDITION WAS FOUND TO | | EXIST ON THE "A" SIDE. AT THIS TIME, THE EFFECT ON THE OPERABILITY OF | | SYSTEMS HAS NOT BEEN DETERMINED, BUT THERE IS THE POTENTIAL FOR IMPACT TO | | EXIST, THEREFORE WE ARE REPORTING THE EVENT AT THIS TIME. THE EVENT SHOULD | | HAVE BEEN REPORTED WITHIN 4 HOURS OF DISCOVERY". | | | | THE STARTUP STRAINERS WERE INSTALLED DURING STARTUP TESTING BACK IN 1984. | | THEY SHOULD HAVE BEEN REMOVED AFTER STARTUP TESTING. THE STRAINERS WERE | | DISCOVERED WHILE DISASSEMBLING THE SPOOL PIECE FOR GASKET REPLACEMENT PER | | AN INSPECTION & MAINTENANCE PROCEDURE. LICENSEE SAID THAT THERE ARE NO | | PROCEDURES THAT CHECK THE SPOOL PIECES OF THE CS DURING PLANT OUTAGES. | | UNIT 3 AND UNIT 1 CONTAINMENT SPRAY SYSTEMS HAVE BEEN EVALUATED FOR STARTUP | | STRAINERS BEING INSTALLED AND THEY HAVE DETERMINED THAT NEITHER UNIT HAS | | STARTUP STRAINERS INSTALLED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1035 3/9/95 FROM ROBERSON TAKEN BY STRANSKY * * * | | | | LICENSEE IS RETRACTING THIS NOTIFICATION. THE FOLLOWING IS TEXT OF A | | FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "RETRACTION OF ENS NOTIFICATION MADE ON 2/20/95 @0020 MST FOR 10 CFR | | 50.72(b)(2)(iii)(D) CONCERNING STRAINERS FOUND IN BOTH TRAINS OF THE | | CONTAINMENT SPRAY PUMP INLET SPOOL PIECE. AN LER WILL STILL BE SUBMITTED | | UNDER 10 CFR 50.73(a)(2)(vii)(c) AND (d). THE REASON FOR THE | | DOWNGRADE/CHANGE IN REPORTING CLASSIFICATION IS AS FOLLOWS: | | | | THE EVALUATION HAS PROVIDED A QUALITATIVE ASSESSMENT OF THE FUNCTIONALITY | | OF THE CSS WITH SUCTION STRAINERS IN PLACE. THE RESULTS SUGGEST THE | | STRAINERS WOULD NOT HAVE PRECLUDED THE CSS FROM PERFORMING ITS INTENDED | | SAFETY FUNCTION AND THAT THE PROBABILITY, CONSEQUENCES VERSUS SIGNIFICANCE | | OF A LOCA, WITH RESPECT TO SAFETY, WOULD NOT HAVE INCREASED. THIS POSITION | | IS BASED ON THE ARGUMENTS THAT ACCUMULATION OF FIBROUS MATERIALS AND FAILED | | COATINGS WOULD BE INSIGNIFICANT. THIS IS SUPPORTED BY ANALYSES THAT | | EVALUATION THE POSSIBLE QUANTITIES OF THESE MATERIALS AND THE TRANSPORT TO | | THE SUMP. DEBRIS THAT MAY REACH THE SUMP IS NOT EXPECTED TO PASS THROUGH | | THE FINE MESH OF THE SUMP IN SIGNIFICANT QUANTITIES; THAT AMOUNT | | CONSERVATIVELY ASSUMED TO REACH THE STRAINER DOES NOT PRESENT THE POTENTIAL | | FOR DEGRADED CS PUMP. | | | | IN THE UNLIKELY EVENT SUFFICIENT DEBRIS WERE TO ACCUMULATE ON THE STRAINER | | SCREENS, ADDITIONAL EVALUATIONS PROVIDE SOME QUANTITATIVE ASSESSMENT OF THE | | BLOCKAGE. CONSIDERING THE BLOCKAGE IS DEPENDENT ON THE DYNAMICS OF THE | | LOCA, ALIGNMENT OF THE LPSI PUMPS TO PROVIDE SPRAY AFTER INITIATION OF | | RECIRCULATION WILL PROVIDE ADEQUATE SPRAY AND CONTAINMENT DEPRESSURIZATION | | TO MAINTAIN THE TEMPERATURE AND PRESSURE BELOW DESIGN LIMITS. | | | | EVALUATIONS OF THE SEISMIC AND STRUCTURAL INTEGRITY OF THE STRAINERS | | DEMONSTRATE THE CONSTRUCTION OF THE STRAINERS IS ADEQUATE TO ENSURE | | FUNCTIONALITY OF THE CSS." | | | | THE NRC RESIDENT HAS BEEN INFORMED BY THE LICENSEE. NOTIFIED R4DO | | (YANDELL). | | | | ***UPDATE 3/14/95 @ 16:18 BY ROBINSON TO GOULD*** THE LICENSEE IS NOT | | SUBMITTING AN LER AS PREVIOUSLY STATED, SINCE STRAINERS DID NOT ADVERSELY | | AFFECT CONTAINMENT SPRAY SYSTEM OPERABILITY. THEREFORE THE CSS REMAINED | | OPERABLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28521 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 02:35 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 01:15[CST]| |NRC NOTIFIED BY: VANBUSKIRK |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 +------------------------------------------------------------------------------+ | REACTOR BUILDING COOLING UNITS SEISMIC ANCHORS NOT INSTALLED | | | | THE AS-BUILT REACTOR BUILDING COOLING UNITS SEISMIC ANCHORS WERE FOUND NOT | | TO BE INSTALLED. THE DISCOVERY WAS MADE DURING A SYSTEM WALKDOWN. THERE | | ARE FOUR COOLING UNITS AND EACH SHOULD HAVE HAD MULTIPLE SEISMIC ANCHORS. | | NO SEISMIC ANCHORS WERE FOUND ON ANY OF THE COOLING UNITS. THE COOLING | | UNITS ARE NOT REQUIRED TO BE OPERABLE UNTIL PLANT TEMPERATURE IS RAISED | | ABOVE 200 DEGREES F. | | | | THE LICENSEE IS STILL ANALYZING THE PROBLEM AND DEVELOPING A PLAN OF | | ACTION. THE CURRENT REFUELING OUTAGE IS SCHEDULED TO END MARCH 25TH. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28522 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:25 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 02:00[CST]| |NRC NOTIFIED BY: SCHOTTEL |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO VALVES IN THE FEEDWATER (FW) SYSTEM FAILED A LEAK RATE TEST | | | | THE REACTOR FW HEADER CHECK VALVE (1-B 21 F010A) HAD SEAT LEAKAGE OF 30,000 | | SCCM. THE FW CONTAINMENT ISOLATION AIR-OPERATED CHECK VALVE (1-B 21 F032A) | | HAD GROSS LEAKAGE (NOT QUANTIFIABLE). THE ISI LIMIT FOR EACH VALVE IS | | 20,000 SCCM. MINIMUM PATH LEAKAGE FOR THE PENETRATION IS 30,000 SCCM WHICH | | EXCEEDS ALLOWABLE SECONDARY CONTAINMENT BYPASS LEAKAGE OF .08 La (APPROX. | | 29,000 SSCM). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28523 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 03/14/95 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 05:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 01:44[EST]| |NRC NOTIFIED BY: LADD |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER 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 +------------------------------------------------------------------------------+ | EMERGENCY BUS INADVERTENTLY DEENERGIZED DURING MAINTENANCE | | | | THE TRAIN B 4160 VAC BUS WAS INADVERTENTLY DEENERGIZED WHILE | | TROUBLESHOOTING A PROBLEM WITH A BREAKER CELL SWITCH ON A SUPPLY BREAKER. | | THE LOSS OF POWER CAUSED THE TURBINE-DRIVEN AUXILIARY FEEDWATER DISCHARGE | | VALVES TO STROKE OPEN DUE TO AN UNDERVOLTAGE SIGNAL FROM THE SEQUENCER. THE | | TRAIN B EDG WAS IN MAINTENANCE MODE FOR THE TROUBLESHOOTING AND DID NOT | | START. THE PROBLEM WAS ISOLATED AND THE BUS WAS REENERGIZED. THE TURBINE | | DRIVEN AUXILIARY FEEDWATER PUMP WAS TAGGED OUT AND DID NOT START. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28524 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 11:14 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 08:52[CST]| |NRC NOTIFIED BY: DON SMITH |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION BASED ON SEWAGE RELEASE TO THE TENNESSEE RIVER | | | | AT 0852 ON 3/14/95 THE ALABAMA DEPARTMENT OF ENVIRONMENTAL MANAGEMENT | | (ADEM) WAS NOTIFIED OF A SEWAGE UPSET WHICH ENTERED THE TENNESSEE RIVER. | | | | ON 3/13/95 AT 1410, BROWNS FERRY SITE ENVIRONMENTAL WAS NOTIFIED OF A LINE | | BREAK IN THE AREA OF THE SEWAGE LIFT STATION BY SITE PERSONNEL. UPON | | INVESTIGATION IT WAS DETERMINED THAT THE LEAKAGE WAS RAW SEWAGE AND THAT IT | | WAS ENTERING THE INTAKE FORE BAY WHICH IS CONSIDERED WATERS OF THE UNITED | | STATES. THE AREA WAS IMMEDIATELY DIKED AND INPUTS ISOLATED TO MINIMIZE THE | | UPSET. 100-150 GALLONS OF SEWAGE IS ESTIMATED AS ENTERING THE TENNESSEE | | RIVER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28525 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 14:28 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 12:00[EST]| |NRC NOTIFIED BY: GRIMARD |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES 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 +------------------------------------------------------------------------------+ | THE SECONDARY COMPONENT COOLING ISOLATION VALVES FAILED THEIR LEAK TEST AND | | WERE DECLARED INOPERABLE. | | | | THIS WAS DETERMINED DURING A SURVEILLANCE TEST WHICH WAS CONDUCTED TO | | MEASURE THE LEAKAGE PAST VALVES IN THE SECONDARY COMPONENT COOLING SYSTEM. | | THIS SYSTEM IS REQUIRED TO BE OPERABLE AS PART OF THE "B" EMERGENCY | | COMPONENT COOLING SYSTEM TRAIN. THE VALVES ARE REQUIRED TO SHUT AND PREVENT | | LOSS OF INVENTORY FROM THE SYSTEM IN THE EVENT OF PIPING FAILURES IN | | CERTAIN NON-SEISMIC PORTIONS OF THE SYSTEM. DURING THE CONDUCT OF THIS | | PROCEDURE, IT WAS DETERMINED THAT THE VALVES EXCEEDED THE LEAK | | CRITERIA(<50GAL/12HRS) AND WHERE DECLARED INOPERABLE. THE MEASURED LEAK | | RATE WAS 2.27GPM. | | | | THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28526 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 17:33 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 14:38[CST]| |NRC NOTIFIED BY: MCNEILL |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE STATE DEPARTMENT OF HEALTH OF AN UNPLANNED | | RELEASE THAT EXCEEDED THEIR RELEASE PERMIT LIMITS. | | | | THIS OCCURRED WHILE THEY WERE DUMPING THEIR NEUTRALIZING TANK INTO THEIR | | DISCHARGE CANAL. WHILE THEY WERE DISCHARGING THIS TANK, THEY WERE ALSO | | GRAVITY FEEDING WATER TO IT FROM THE RECEIVING TANK(USED TO STORE RESINS | | FROM DEMIN) DUE TO A VALVE BEING IN THE OPEN POSITION. THIS BACKWASHING | | ADDED TO THE NEUTRALIZING TANK APPROXIMATELY 80 GPM OF WATER FOR | | APPROXIMATELY 45 MINS (APPROXIMATELY 3600 GAL) UNTIL THEY CLOSED THE VALVE. | | THEY CONTINUED TO FINISH THE DUMP OF THE NEUTRALIZING TANK TO THEIR | | DISCHARGE CANAL WHICH GOES TO LAKE DARDANELLE. THE LIQUID RELEASE, WHICH | | WAS TERMINATED, WAS MADE UP OF THE FOLLOWING ISOTOPES; TRITIUM, IRON 55, | | CESIUM 134 AND CESIUM 137. THE ACTIVITY OF THE LIQUID, EXCLUDING THE | | TRITIUM AND DISSOLVED NOBLE GASES, WAS 2.9x10-9 CURIES/SEC, LIQUID TRITIUM | | WAS 3.67x10-8 CURIES/SEC AND TOTAL ACTIVITY WAS 3.96x10-8 CURIES. THE TOTAL | | ACTIVITY WAS 1.79x10-4% OF THEIR QUARTERLY TS LIMITS. THEIR RELEASE PERMIT | | ALLOWS 1.074x10-4 CURIES AND A VOLUME LIMIT, WHICH THEY EXCEEDED, OF 13,630 | | LITERS. NO MONITOR ALARMS SOUNDED DURING THE RELEASE. THERE WERE NO PRESS | | RELEASES MADE. | | | | THE RI AND THE STATE WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28527 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 17:33 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 17:07[EST]| |NRC NOTIFIED BY: GILLESPIE |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS DECKER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE SOUTH CAROLINA DEPARTMENT OF ENVIRONMENTAL CONTROL AND THE OCONEE | | COUNTY POLICE WERE NOTIFIED OF AN EIGHT-GALLON ANTIFREEZE SPILL. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "AT 1432EST ON 3/14/95, A CRANE WAS BEING DISASSEMBLED. THE CRANE BEING | | USED FOR DISASSEMBLY TIPPED, CAUSING THE CRANE BEING DISASSEMBLED TO IMPACT | | THE GROUND. THIS CAUSED THE COOLANT SYSTEM TO BE DAMAGED AND RESULTED IN | | AN ANTIFREEZE SPILL FROM THE DISASSEMBLED CRANE. SPILL SIZE WAS ESTIMATED | | AT 8 GALLONS TO THE SOIL. LOCAL GOVERNMENTAL AGENCIES HAVE BEEN NOTIFIED. | | CONTAMINATED DIRT CLEAN UP IS IN PROGRESS." | | END OF TEXT. | | | | THE LICENSEE WAS REQUIRED TO NOTIFY OTHER GOVERNMENT AGENCIES WHEN THE | | SPILL EXCEEDED THE ONE-POUND "CERCLA" LIMIT. THE CONTAMINATED SOIL IS | | BEING PLACED INTO 50-GALLON DRUMS AND REMOVED FROM THE SITE. THE LICENSEE | | NOTIFIED NRC(DOT). THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28528 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/14/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 18:02 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 17:28[EST]| |NRC NOTIFIED BY: NELSON |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THE AUTO AUX FEED WATER SYSTEM IS INOPERABLE. | | | | THEY DETERMINED THIS WHEN THEY DISCOVERED THAT THE SYSTEM WAS LACKING | | PROPER ELECTRICAL SEPARATION. THIS COULD HAVE RESULTED IN THE LOSS OF THE | | AUTO AUX FEED WATER SYSTEM. THIS CONDITION WAS DETERMINED DURING A SYSTEM | | WALKDOWN AND WILL BE CORRECTED PRIOR TO STARTUP. THE RI AND STATE AND LOCAL | | AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28529 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 18:54 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 18:15[EST]| |NRC NOTIFIED BY: HARDEN |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED AN LCO ACTION STATEMENT DUE TO ONE PORV BEING INOPERABLE. | | | | THE LICENSEE DETERMINED THAT THE CONTROL CIRCUIT FOR PORV "PRV-1042B" MAY | | NOT HAVE ADEQUATE 1E TO NON-1E ELECTRICAL ISOLATION FROM THE NON-1E DATA | | LOGGER SYSTEM. THIS COULD BE A CONDITION OUTSIDE THE DESIGN BASIS. AS A | | CONSERVATIVE MEASURE THE "PRV1042B" HAS BEEN DECLARED INOPERABLE. THE OTHER | | PORV "PRV1043B" HAS BEEN VERIFIED TO HAVE QUALIFIED 1E TO NON-1E ISOLATION. | | THEY ARE CONTINUING THEIR INVESTIGATION INTO THIS MATTER. THE LICENSEE'S TS | | 3.1.8.1 A2 & A3 APPLY WHEN "PRV1042B" IS INOPERABLE. IT REQUIRES THAT THE | | BLOCK VALVE BE CLOSED AND PERMITS THEM TO OPERATE 72 HRS WITH ONE INOP | | PORV. IF THE CONDITION IS NOT CORRECTED WITHIN 72 HRS THEY HAVE 12 HRS TO | | HOT S/D. THE PLANT NORMALLY OPERATES WITH BOTH PORV BLOCK VALVES CLOSED. | | THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28530 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/14/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 19:02 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 18:43[EST]| |NRC NOTIFIED BY: BAIN |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL MODES RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED A POSSIBLE PROBLEM WITH THE REACTOR PROTECTION | | SYSTEM DUE TO INSTRUMENT DRIFT. | | | | THEY DISCOVERED DURING A REVIEW THAT INSTRUMENT DRIFT AND PROCEDURAL | | INADEQUACY MAY HAVE RESULTED IN LOW FLOW TRIPS BEING SET NON-CONSERVATIVELY | | ON TWO OR MORE CHANNELS. THIS WAS DUE TO THE INSTRUMENT DRIFT BEING GREATER | | THAN WHAT WAS ASSUMED IN THEIR UNCERTAINTY ANALYSIS. THE UNCERTAINTY MAY | | NOT HAVE BEEN APPROPRIATELY ACCOUNTED FOR IN THE PROCEDURE WHICH | | ENGINEERING USES TO CALCULATE THE TRIP SETPOINTS. THEY ARE CONTINUING THIS | | REVIEW. | | | | THE RI, STATE AND LOCAL AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28531 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/14/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 20:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/14/95 | +------------------------------------------------+EVENT TIME: 20:00[EST]| |NRC NOTIFIED BY: PTACEK |LAST UPDATE DATE: 03/14/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THEY DID NOT HAVE ADEQUATE CABLE SEPARATION | | FOR THE CABLES SUPPORTING S/G LEVEL CHANNELS. | | | | THE LICENSEE IDENTIFIED FOUR CABLE TRAYS WHICH TRAVERSED QUADRANTS THREE | | AND FOUR OF UNIT 1 CONTAINMENT BUILDING AT THE 625' ELEVATION. IT WAS ALSO | | DETERMINED THAT THE INSTRUMENT CABLES SUPPORTING THE S/G LEVEL CHANNELS IN | | QUADRANTS TWO AND THREE(BLP-120 AND BLP-130) RUN PARALLEL TO THE PREVIOUSLY | | MENTIONED CABLE TRAYS AT A DISTANCE OF LESS THAN 20 FT. IN A SIMILAR | | MANNER, THE STEAM GENERATOR LEVEL CHANNEL ASSOCIATED WITH QUADRANT FOUR | | (1-BLP-142) ALSO RUNS PARALLEL TO THE PREVIOUSLY MENTIONED CABLE TRAYS AT A | | DISTANCE OF LESS THAN 20 FT. THE DISTANCE BETWEEN THE POINTS WHERE THE | | QUADRANT TWO/THREE INSTRUMENT CABLES DRAW NEAR THE CABLE TRAYS VERSUS THE | | QUADRANT FOUR CABLE IS GREATER THAN 60 FEET. | | | | THE FOLLOWING ACTIONS WILL BE TAKEN: | | 1. VERIFY THE THERMISTOR STRING IN CABLE TRAY IS OPERABLE. | | 2. PLANT PERSONNEL WILL SURVEIL CONTAINMENT TEMPERATURES HOURLY. | | 3. ACTIONS WILL BE TAKEN TO INSTALL FIRE STOPS IN THE AFFECTED CABLE TRAYS | | IN THE NEAR FUTURE. | | | | A FIRE IS NOT EXPECTED TO DAMAGE THE REDUNDANT CIRCUITS ASSUMED FOR SAFE | | SHUTDOWN ON THE FOLLOWING; | | 1. CABLE TRAYS IN QUESTION ARE PROVIDED WITH THERMISTOR STRINGS WHICH ALARM | | IN THE EVENT THAT A FIRE IS SENSED. THEY PROVIDE THE NECESSARY DETECTION | | MECHANISM TO LIMIT THE POTENTIAL PROPAGATION OF A FIRE. | | 2. ADDITIONAL SURVEILLANCE OF CONTAINMENT AIR TEMPERATURES WILL BE | | PERFORMED ON A HOURLY BASIS. THIS METHOD WILL BE USED AS AN ALTERNATE TO | | POSTING FIRE WATCHES INSIDE CONTAINMENT BUILDING FOR ALARA PURPOSES. | | 3. INSTRUMENTATION CABLES IN QUESTION ARE INSIDE RIGID METAL CONDUIT. | | 4. TRANSIENT COMBUSTIBLE MATERIALS IN THE AREA ARE STRICTLY CONTROLLED. | | 5. MANUAL FIRE SUPPRESSION(E.G., FIRE EXTINGUISHER OUTSIDE CONTAINMENT) | | READILY AVAILABLE FOR FIRE BRIGADE USE. | | | | THE APPENDIX R SAFE SHUTDOWN ANALYSIS ASSUMES THAT TWO STEAM GENERATORS | | WILL BE AVAILABLE TO PROVIDE HEAT REMOVAL CAPABILITY IN THE EVENT OF A | | FIRE. BASED ON A REVIEW OF THE CABLING RUNS ASSOCIATED WITH THE QUADRANT | | TWO/THREE AND QUADRANT ONE INSTRUMENT CABLES, IT IS CONCLUDED THAT THE | | ABILITY TO REMOVE DECAY HEAT WILL NOT BE JEOPARDIZED PROVIDED OPERATOR | | ACTION IS TAKEN. THE LICENSEE'S NUCLEAR ENGINEERING DEPARTMENT HAS | | DETERMINED THAT THE COMBUSTION RATE WITHIN THE CABLE TRAYS IS APPROXIMATELY | | 10 FT/HR. BASED ON KNOWN DISTANCE BETWEEN THE AFFECTED QUADRANTS TWO/THREE | | CABLES AND THE QUADRANT ONE CABLE(60 FT), PLANT PERSONNEL WOULD HAVE | | ADEQUATE TIME TO EXTINGUISH A POTENTIAL FIRE BEFORE THE OTHER QUADRANT | | INSTRUMENTATION WAS AFFECTED. BASED ON THIS REVIEW, IT IS BELIEVED THAT NO | | ADVERSE IMPACT WILL RESULT FROM THIS CONDITION PROVIDED ADMINISTRATIVE | | ACTIONS ARE TAKEN. | +------------------------------------------------------------------------------+