U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/11/96 - 04/12/96 ** EVENT NUMBERS ** 30244 30271 30272 30273 30274 30275 30276 30277 30278 30279 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 04/07/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 01:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/07/96 | +------------------------------------------------+EVENT TIME: 00:00[CST]| |NRC NOTIFIED BY: JACOBSON |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |ED BUTCHER EO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |McPEEK (NRR) IAT | | |DAVIDSON (NMSS) IAT | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SECURITY EVENT - UNAVAILABILITY OF SECURITY OFFICERS DUE TO STRIKE | | | | THERE IS NO IMPACT PERCEIVED DUE TO POST AUGMENTATION BY SECURITY | | SUPERVISORY PERSONNEL. (REFER TO THE HOO LOG BOOK FOR DETAILS.) | | | | * * * * 2334 APRIL 7, 1996, UPDATE BY JACOBSON TAKEN BY MACKINNON * * * * | | | | THE LICENSEE ISSUED A NEWS RELEASE TO A LOCAL TELEVISION STATION ABOUT THE | | SECURITY GUARDS BEING ON STRIKE. | | | | THE LICENSEE NOTIFIED THE REGION 4 PUBLIC AFFAIRS OFFICERS ABOUT THE NEWS | | RELEASE. THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE | | LICENSEE. THE R4DO (TOM STETKA) WAS NOTIFIED BY THE HOO. | | | | * * * 1128 APRIL 11, 1996, UPDATE FROM BOTTEMILLER TAKEN BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING A PORTION OF THIS EVENT. THE OFFSITE | | NOTIFICATION IS STILL APPLICABLE. THE LICENSEE IS RETRACTING THE SECURITY | | PORTION OF THIS EVENT BECAUSE THE MINIMUM STAFFING LEVEL DID NOT GO BELOW | | THE LEVEL REFERENCED IN THE GUIDELINES. THE LICENSEE DOES NOT PLAN TO | | ISSUE A 30-DAY REPORT. | | | | THE LICENSEE DISCUSSED THIS ISSUE WITH NRC REGION 4 SECURITY (TOM DEXTER) | | AND PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER | | NOTIFIED THE R4DO (VANDENBURGH). (REFER TO THE HOO LOG FOR A SITE CONTACT | | TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LONGVIEW INSPECTION |NOTIFICATION DATE: 04/10/96 | | CITY: REGION: 2 |NOTIFICATION TIME: 23:33 [ET]| | COUNTY: CAMDEN STATE: GA |EVENT DATE: 04/10/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 22:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID VERRELLI RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM HARDAMAN | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A STOLEN | | LONGVIEW INSPECTION SERVICE (OF VIRGINIA) TRUCK WHICH HAD BEEN TRANSPORTING | | A RADIOGRAPHY CAMERA WAS FOUND. | | | | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A TRUCK STOLEN | | FROM LONGVIEW INSPECTION SERVICE OF VIRGINIA AND TRANSPORTING A RADIOGRAPHY | | CAMERA WAS CAPTURED AT A TRAFFIC STOP IN CAMDEN COUNTY, GEORGIA. THE | | CAMERA, A TECH-OPS-660, CONTAINS AN IRIDIUM-192 SOURCE OF UNKNOWN STRENGTH. | | AT THIS TIME, IT IS NOT KNOWN IF THE SOURCE IS IN THE SHIELDED POSITION. | | THE TRUCK IS CURRENTLY PARKED AT THE SIDE OF ROAD UNDER POLICE GUARD. | | | | * * * 0022 APRIL 11, 1996, UPDATE FROM HARDAMAN RECEIVED BY TROCINE * * * | | | | THE CAMDEN COUNTY SHERIFF'S OFFICE WAS ABLE TO PROVIDE MONITORING | | ASSISTANCE AND DETERMINED THAT THE RADIOGRAPHY CAMERA SOURCE WAS IN THE | | SHIELDED POSITION. THERE WERE NO READINGS IN EXCESS OF ONE MILLIREM PER | | HOUR UNTIL THE SURVEYORS GOT UP ONTO THE TRUCK. THE VEHICLE IS CURRENTLY | | BEING TRANSPORTED TO AN IMPOUND LOT ON THE BACK OF A WRECKER. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO (VERRELLI). (REFER TO THE HOO | | LOG FOR CONTACT NAMES AND TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30272 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 07:03 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 05:03[CDT]| |NRC NOTIFIED BY: PAUL COX |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 | M/R Y 1 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO A ROD CONTROL MALFUNCTION DURING THE SHUTDOWN OF | | THE REACTOR FROM LESS THAN 1% POWER | | | | PRIOR TO THIS EVENT, THE UNIT HAD BEEN RAMPED DOWN, AND THE MAIN TURBINE | | HAD BEEN REMOVED FROM SERVICE IN PREPARATION FOR ISOLATION AND REPAIR OF A | | LEAK IN THE HEATER DRAIN SYSTEM. DURING THE SHUTDOWN OF THE REACTOR FROM | | LESS THAN 1% POWER, A ROD CONTROL MALFUNCTION OCCURRED. BANK 'D' CONTROL | | RODS FAILED TO CEASE INSERTING UPON REACHING THEIR OFFSET POSITION. IN | | ADDITION, CONTROL BANK 'B' RODS FAILED TO BEGIN STEPPING IN AT THE | | APPROPRIATE OVERLAP POINT. CONTROL BANK 'C' RODS RESPONDED NORMALLY. AS A | | RESULT OF THE ABNORMAL ROD RESPONSE, OPERATORS MANUALLY TRIPPED THE | | REACTOR. ALL RODS FULLY INSERTED. THERE WERE NO ENGINEERED SAFETY | | FEATURES ACTUATIONS. AUXILIARY FEEDWATER WAS BEING USED TO FEED THE STEAM | | GENERATORS BOTH BEFORE AND AFTER THE UNIT TRIP. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. OPERATORS ARE USING NORMAL | | CHARGING AND MAKEUP, PRESSURIZER HEATERS AND SPRAYS, AND THE REACTOR | | COOLANT PUMPS FOR PRIMARY SYSTEM INVENTORY, PRESSURE, AND TRANSPORT | | CONTROL. AUXILIARY FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS, | | AND SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER. ALL EMERGENCY CORE | | COOLING EQUIPMENT IS AVAILABLE IF NEEDED. | | | | THE CAUSE OF THE ROD CONTROL MALFUNCTION IS UNKNOWN AT THIS TIME. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30273 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 07:50 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 07:30[EDT]| |NRC NOTIFIED BY: BRYAN CROKE |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF EMERGENCY NOTIFICATION SYSTEM (ENS) AND LONG DISTANCE COMMERCIAL | | TELEPHONE LINES (REFER TO RELATED EVENT #30274.) | | | | THE LICENSEE REPORTED THE LOSS OF ENS AND LONG DISTANCE COMMERCIAL | | TELEPHONE LINES. COMMUNICATIONS HAVE BEEN ESTABLISHED THROUGH REMVEC | | (REGIONAL DISPATCH CENTER). THE CAUSE OF THE LOSS OF THE PHONE LINES IS | | BELIEVED TO HAVE BEEN CAUSED BY A TRUCK ACCIDENT WHICH DISABLED A LONG | | DISTANCE CARRIER FOR AT&T. | | | | THE NRC RESIDENT INSPECTOR IS AWARE OF THIS EVENT. (REFER TO THE HOO LOG | | FOR THE REMVEC TELEPHONE NUMBER.) | | | | * * * 0843 APRIL 11, 1996, UPDATE FROM CROKE RECEIVED BY TROCINE * * * | | | | THE LICENSEE CAN ALSO BE REACHED THROUGH YANKEE ATOMIC (THE CORPORATE | | OFFICE) IN BOLTON, MASSACHUSETTS. (REFER TO THE HOO LOG FOR THE CORPORATE | | OFFICE TELEPHONE NUMBER.) | | | | * * * 1109 APRIL 11, 1996, UPDATE FROM CROKE RECEIVED BY TROCINE * * * | | | | THE LICENSEE WAS INFORMED THAT THE COMMERCIAL LINES HAVE BEEN RESTORED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER INFORMED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30274 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: YANKEE ROWE REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 08:11 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 07:15[EDT]| |NRC NOTIFIED BY: DAVID JOYCE |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY NOTIFICATION SYSTEM (ENS) AND COMMERCIAL LINES INOPERABLE (REFER | | TO RELATED EVENT #30273.) | | | | THE LICENSEE REPORTED THE LOSS OF COMMERCIAL LONG DISTANCE AND ENS LINES. | | COMMUNICATIONS HAVE BEEN ESTABLISHED THROUGH THE CORPORATE OFFICE IN | | BOLTON, MASSACHUSETTS. THE CAUSE OF THE LOSS OF COMMUNICATIONS IS BELIEVED | | TO HAVE BEEN CAUSED BY A TRUCK ACCIDENT WHICH DISABLED A LONG DISTANCE | | CARRIER FOR AT&T. | | | | THE LICENSEE INFORMED THE VERMONT YANKEE RESIDENT INSPECTOR OF THIS EVENT. | | (REFER TO THE HOO LOG LOG FOR THE CORPORATE OFFICE TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30275 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 04/11/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 13:28 [ET]| |RX TYPE: [3] CE |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 11:45[CDT]| |NRC NOTIFIED BY: LITOLFF |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VANDENBURGH 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUXILIARY COMPONENT COOLING WATER SYSTEM MAY NOT HAVE BEEN ABLE TO | | ADEQUATELY PERFORM SAFETY FUNCTION | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON 4/11/96, A FLOW BALANCE TEST WAS PERFORMED ON WATERFORD 3 AUXILIARY | | COMPONENT COOLING WATER (ACCW) SYSTEM TRAIN 'B' DUE TO THE DISCOVERY THAT | | VALVES WERE POSITIONED DIFFERENTLY THAN DURING STARTUP TESTING. THE | | PURPOSE OF THE TEST WAS TO VERIFY THE SYSTEM COULD PERFORM ITS REQUIRED | | DESIGN FUNCTION TO PROVIDE 850 GPM TO THE ESSENTIAL CHILLERS WHILE | | MAINTAINING 5000 GPM FLOW THROUGH THE SHELL SIDE OF THE COMPONENT COOLING | | WATER (CCW) SYSTEM HEAT EXCHANGER. ACCW IS REQUIRED TO SUPPLY WATER TO THE | | ESSENTIAL CHILLERS POST-LOCA WHEN THE PRIMARY COOLING WATER SYSTEM (CCW) | | TEMPERATURE REACHES 105øF. | | | | THE TESTING PERFORMED WAS UNABLE TO DEMONSTRATE THAT ACCW TRAIN 'B' COULD | | PERFORM ITS DESIGN SAFETY FUNCTION. APPROXIMATELY 740 GPM WAS ACHIEVED TO | | THE ESSENTIAL CHILLER WITH A CORRESPONDING ACCW FLOW OF AT LEAST 5000 GPM. | | THE CAUSE OF THIS CONDITION AND PERIOD OF TIME IT HAS EXISTED IS UNKNOWN AT | | THIS TIME. ACCW TRAIN 'B' IS CURRENTLY OPERABLE BASED ON PRESENT AMBIENT | | CONDITIONS AND AMBIENT CONDITIONS EXPECTED FOR THE NEAR FUTURE (BASED ON | | HISTORICAL DATA). TESTING OF ACCW TRAIN 'A' IS CURRENTLY BEING PREPARED." | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30276 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 17:10[EDT]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOSLAK 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 +------------------------------------------------------------------------------+ | SINGLE FAILURE COULD RENDER RHR PUMP INOPERABLE | | | | THE FOLLOWING IS TEXT EXCERPTED FROM A LICENSEE SUBMITTAL: | | | | "THE APPENDIX R PROJECT TEAM, WHILE PERFORMING DESIGN VERIFICATION OF THE | | APPENDIX R PROGRAM, IDENTIFIED AN ISSUE (UNRELATED TO APPENDIX R) REGARDING | | THE RHR MINIMUM FLOW VALVE AND THE LOCA SINGLE FAILURE ANALYSIS. | | SPECIFICALLY, A POTENTIAL FOR RHR PUMP DAMAGE EXISTS, DUE TO LACK OF | | MINIMUM FLOW PROTECTION, WHICH IMPACTS THE LOCA ANALYSIS. | | | | THE RHR MINIMUM FLOW VALVES (V10-16A/B) ARE NORMALLY CLOSED. ONE MINIMUM | | FLOW LINE EXISTS PER TRAIN. THE TWO RHR PUMPS PER TRAIN ARE CROSS-POWERED | | (i.e. ONE PUMP IS POWERED FROM BUS 3 AND ONE FROM BUS 4). THE MINIMUM FLOW | | VALVE IN EACH TRAIN IS POWERED BY A SINGLE BUS (EITHER 3 OR 4). THEREFORE, | | IF BUS 4 IS LOST AS A RESULT OF A SINGLE FAILURE, THE 'A' TRAIN OF RHR IS | | LOST WITH THE EXCEPTION OF THE ONE CROSS-CONNECTED RHR PUMP WHICH IS | | POWERED FROM BUS 3 AND THE 'A' LPCI INJECTION VALVES WHICH ARE POWERED FROM | | THE 480 VOLT UPS. THE 'A' TRAIN MINIMUM FLOW VALVE V10-16A, HOWEVER, WOULD | | REMAIN CLOSED DUE TO THE LOSS OF BUS 4. FOR ACCIDENT SCENARIOS WHERE THE | | RHR PUMPS WOULD AUTOMATICALLY START, BUT MUST OPERATE ON MINIMUM FLOW UNTIL | | THE REACTOR IS DEPRESSURIZED, THE LOSS OF MINIMUM FLOW PROTECTION FOR THE | | CROSS-CONNECTED PUMP MUST BE CONSIDERED. | | | | THE LOCA ANALYSIS CONSIDERS THE MOST SEVERE SINGLE FAILURES AS DISCUSSED IN | | FSAR SECTION 6.5.2.1.4.3. THE POTENTIAL LOSS OF THE RHR PUMP POWERED BY | | THE CROSS-CONNECTED BUS, DUE TO FAILURE OF THE MINIMUM FLOW VALVE TO OPEN, | | WAS NOT CONSIDERED. DISCUSSION WITH [THE LICENSEE'S] LOCA GROUP INDICATES | | THAT AN INTERMEDIATE RECIRCULATION LINE BREAK WHICH DOES NOT DEPRESSURIZE | | QUICKLY, COUPLED WITH A SINGLE FAILURE OF THE DC BUS WHICH POWERS HPCI IS | | PROBABLY THE MOST LIMITING CASE. PRESENTLY, THE ANALYSIS ASSUMES THAT 1 | | CORE SPRAY PUMP, PLUS 1 RHR PUMP IN THE TRAIN NOT AFFECTED BY THE BREAK | | WOULD BE AVAILABLE FOR THIS CASE. THE AVAILABILITY OF THE RHR PUMP FOR | | THIS EVENT IS IN QUESTION BECAUSE THE POWER TO THE NORMALLY CLOSED MINIMUM | | FLOW VALVE WOULD BE LOST AND THE PUMP WOULD THEREFORE HAVE TO OPERATE DEAD | | HEADED FOR A SHORT PERIOD OF TIME UNTIL THE REACTOR WAS DEPRESSURIZED." | | | | THE LICENSEE STATED THAT THE CURRENT LOCA ANALYSIS PREDICTS A PEAK CLADDING | | TEMPERATURE (PCT) OF 1778øF BUT THAT THE PREDICTED TEMPERATURE WOULD RISE | | TO 1806øF IF THE RHR PUMP WAS ASSUMED TO FAIL. THE LICENSEE IS STILL | | PERFORMING AN ENGINEERING ANALYSIS OF THIS SCENARIO. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30277 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 18:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: KONOVALCHICK |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOSLAK RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE PLANS PRESS RELEASE REGARDING COCAINE FOUND IN PROTECTED AREA | | | | AT 1530, THE RADIATION PROTECTION SUPERVISOR WAS NOTIFIED THAT THE CONTENTS | | OF A PACKET FOUND ONSITE EARLIER IN THE DAY HAD TESTED POSITIVE FOR | | COCAINE. THE PACKET CONTAINED LESS THAN ONE OUNCE OF POWDER. THE PACKET | | HAD BEEN DISCOVERED BY A HEALTH PHYSICS TECHNICIAN IN A LOCKER WHERE HE WAS | | PLACING HIS BELONGINGS. THE LICENSEE QUARANTINED THE LOCKER ROOM AND | | PERFORMED A SEARCH OF ALL LOCKERS. THIS LOCKER ROOM IS PRIMARILY USED BY | | HEALTH PHYSICS TECHNICIANS. THE LICENSEE PLANS TO MAKE A PRESS RELEASE | | REGARDING THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 2222 ON 04/11/96, FROM SAUER TAKEN BY STRANSKY * * * | | | | THE LICENSEE CALLED TO CORRECT SOME INFORMATION PROVIDED IN THE INITIAL | | REPORT. THE PACKET WAS FOUND BY THE HEALTH PHYSICS TECHNICIAN IN A LOCKER | | THAT HAD PREVIOUSLY BEEN ASSIGNED TO HIM BUT THAT HE HAD VACATED SOME TIME | | AGO. THE LICENSEE ALSO REPORTED THAT A DRUG SNIFFING DOG WAS BROUGHT IN TO | | SEARCH THE LOCKER ROOM, BUT NO ADDITIONAL DRUGS WERE FOUND. THE LICENSEE | | WILL PURSUE THIS MATTER FURTHER. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30278 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 19:01 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 18:15[EDT]| |NRC NOTIFIED BY: NEFF |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOSLAK RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A COMPROMISE OF SAFEGUARDS INFORMATION. IMMEDIATE | | COMPENSATORY ACTIONS WERE TAKEN UPON DISCOVERY. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. (REFER TO THE HOO LOG FOR | | DETAILS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30279 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/12/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 00:35 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 23:37[EDT]| |NRC NOTIFIED BY: ROY GREEN |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE LOSS OF REACTOR | | COOLANT LEAKAGE DETECTION WHEN AN ELECTRICAL PROTECTION ASSEMBLY (EPA) | | BREAKER TRIPPED (REFER TO EVENT #30261 FOR A SIMILAR EVENT THAT OCCURRED | | ON APRIL 10, 1996.) | | | | AT 2337 ON APRIL 11, 1996, EPA BREAKER 2VBS*ACB2A TRIPPED RESULTING IN A | | HALF SCRAM, HALF MAIN STEAM ISOLATION VALVE (MSIV) ISOLATION, AND DIVISION | | 1 NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM (NSSSS) ISOLATION. THE ISOLATION | | CAUSED A TOTAL LOSS OF THE REACTOR COOLANT LEAKAGE DETECTION SYSTEM, AND | | THIS REQUIRED THE ENTRY INTO TECHNICAL SPECIFICATION 3.0.3. TECHNICAL | | SPECIFICATION 3.0.3 REQUIRES THE LICENSEE TO RESTORE THE SYSTEM TO OPERABLE | | STATUS OR TO COMMENCE A UNIT SHUTDOWN WITHIN 1 HOUR, PLACE THE UNIT IN | | STARTUP WITHIN THE NEXT 6 HOURS, AND PLACE THE UNIT IN HOT SHUTDOWN WITHIN | | THE FOLLOWING 6 HOURS. A REACTOR SHUTDOWN WAS COMMENCED AT 0012 ON APRIL | | 12, 1996. ALL EMERGENCY CORE COOLING SYSTEMS ARE AVAILABLE, AND THE GRID | | IS STABLE. | | | | THE EPA BREAKER TRIP ALSO CAUSED THE FOLLOWING ENGINEERED SAFETY FEATURES | | ACTUATIONS: SECONDARY CONTAINMENT ISOLATION; STANDBY GAS TREATMENT SYSTEM | | INITIATION; DIVISION 1 CONTROL ROOM SPECIAL FILTER TRAIN AUTOMATIC START; | | AND NSSSS GROUP 2, 3, 4, 5, 6, 8, AND 9 ISOLATIONS ON DIVISION 1. LOSS OF | | COOLANT ACCIDENT OVERRIDE SWITCHES WERE USED TO RESTORE INSTRUMENT AIR TO | | THE MSIVs, AND RECIRCULATION PUMP COOLING WATER ISOLATION VALVES WERE | | DE-ENERGIZED AND MANUALLY OPENED REQUIRING ENTRY INTO TECHNICAL | | SPECIFICATION 3.6.3 AT 2343 ON APRIL 11, 1996. TECHNICAL SPECIFICATION | | 3.6.3 REQUIRES THE LICENSEE TO HAVE THE PENETRATION ISOLATED WITHIN 4 HOURS | | OR TO PLACE THE UNIT IN HOT SHUTDOWN WITHIN THE FOLLOWING 12 HOURS. | | | | THIS EVENT IS SIMILAR TO AN EVENT WHICH OCCURRED ON THE SAME UNIT ON APRIL | | 10, 1996. (REFER TO EVENT #30461 FOR ADDITIONAL INFORMATION.) THE | | LICENSEE HAD BEEN DEVELOPING A PROCEDURE TO REPAIR THE FAILED EPA BREAKER | | WITH THE UNIT ON LINE AND THE BREAKER ENERGIZED. WHILE THE PROCEDURE WAS | | BEING DEVELOPED, THE BREAKER HAD BEEN RECLOSED. NOW THAT THE BREAKER HAS | | TRIPPED OPEN AGAIN, IT WILL NOT RECLOSE. THEREFORE, THE LICENSEE IS | | MODIFYING ITS PLAN AND WILL NOW REPLACE THE FAILED EPA BREAKER. A NEW | | BREAKER HAS ALREADY BEEN BENCH CALIBRATED. THE LICENSEE CURRENTLY BELIEVES | | THAT THE BREAKER FAILURE MAY HAVE RESULTED FROM A CONTROL MODULE PROBLEM. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/11/96 - 04/12/96 ** EVENT NUMBERS ** 30244 30271 30272 30273 30274 30275 30276 30277 30278 30279 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 04/07/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 01:42 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/07/96 | +------------------------------------------------+EVENT TIME: 00:00[CST]| |NRC NOTIFIED BY: JACOBSON |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH |ED BUTCHER EO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |McPEEK (NRR) IAT | | |DAVIDSON (NMSS) IAT | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SECURITY EVENT - UNAVAILABILITY OF SECURITY OFFICERS DUE TO STRIKE | | | | THERE IS NO IMPACT PERCEIVED DUE TO POST AUGMENTATION BY SECURITY | | SUPERVISORY PERSONNEL. (REFER TO THE HOO LOG BOOK FOR DETAILS.) | | | | * * * * 2334 APRIL 7, 1996, UPDATE BY JACOBSON TAKEN BY MACKINNON * * * * | | | | THE LICENSEE ISSUED A NEWS RELEASE TO A LOCAL TELEVISION STATION ABOUT THE | | SECURITY GUARDS BEING ON STRIKE. | | | | THE LICENSEE NOTIFIED THE REGION 4 PUBLIC AFFAIRS OFFICERS ABOUT THE NEWS | | RELEASE. THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE | | LICENSEE. THE R4DO (TOM STETKA) WAS NOTIFIED BY THE HOO. | | | | * * * 1128 APRIL 11, 1996, UPDATE FROM BOTTEMILLER TAKEN BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING A PORTION OF THIS EVENT. THE OFFSITE | | NOTIFICATION IS STILL APPLICABLE. THE LICENSEE IS RETRACTING THE SECURITY | | PORTION OF THIS EVENT BECAUSE THE MINIMUM STAFFING LEVEL DID NOT GO BELOW | | THE LEVEL REFERENCED IN THE GUIDELINES. THE LICENSEE DOES NOT PLAN TO | | ISSUE A 30-DAY REPORT. | | | | THE LICENSEE DISCUSSED THIS ISSUE WITH NRC REGION 4 SECURITY (TOM DEXTER) | | AND PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS CENTER | | NOTIFIED THE R4DO (VANDENBURGH). (REFER TO THE HOO LOG FOR A SITE CONTACT | | TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30271 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LONGVIEW INSPECTION |NOTIFICATION DATE: 04/10/96 | | CITY: REGION: 2 |NOTIFICATION TIME: 23:33 [ET]| | COUNTY: CAMDEN STATE: GA |EVENT DATE: 04/10/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 22:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DAVID VERRELLI RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM HARDAMAN | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A STOLEN | | LONGVIEW INSPECTION SERVICE (OF VIRGINIA) TRUCK WHICH HAD BEEN TRANSPORTING | | A RADIOGRAPHY CAMERA WAS FOUND. | | | | THE GEORGIA ENVIRONMENTAL PROTECTION DIVISION REPORTED THAT A TRUCK STOLEN | | FROM LONGVIEW INSPECTION SERVICE OF VIRGINIA AND TRANSPORTING A RADIOGRAPHY | | CAMERA WAS CAPTURED AT A TRAFFIC STOP IN CAMDEN COUNTY, GEORGIA. THE | | CAMERA, A TECH-OPS-660, CONTAINS AN IRIDIUM-192 SOURCE OF UNKNOWN STRENGTH. | | AT THIS TIME, IT IS NOT KNOWN IF THE SOURCE IS IN THE SHIELDED POSITION. | | THE TRUCK IS CURRENTLY PARKED AT THE SIDE OF ROAD UNDER POLICE GUARD. | | | | * * * 0022 APRIL 11, 1996, UPDATE FROM HARDAMAN RECEIVED BY TROCINE * * * | | | | THE CAMDEN COUNTY SHERIFF'S OFFICE WAS ABLE TO PROVIDE MONITORING | | ASSISTANCE AND DETERMINED THAT THE RADIOGRAPHY CAMERA SOURCE WAS IN THE | | SHIELDED POSITION. THERE WERE NO READINGS IN EXCESS OF ONE MILLIREM PER | | HOUR UNTIL THE SURVEYORS GOT UP ONTO THE TRUCK. THE VEHICLE IS CURRENTLY | | BEING TRANSPORTED TO AN IMPOUND LOT ON THE BACK OF A WRECKER. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO (VERRELLI). (REFER TO THE HOO | | LOG FOR CONTACT NAMES AND TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30272 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 07:03 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 05:03[CDT]| |NRC NOTIFIED BY: PAUL COX |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 | M/R Y 1 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO A ROD CONTROL MALFUNCTION DURING THE SHUTDOWN OF | | THE REACTOR FROM LESS THAN 1% POWER | | | | PRIOR TO THIS EVENT, THE UNIT HAD BEEN RAMPED DOWN, AND THE MAIN TURBINE | | HAD BEEN REMOVED FROM SERVICE IN PREPARATION FOR ISOLATION AND REPAIR OF A | | LEAK IN THE HEATER DRAIN SYSTEM. DURING THE SHUTDOWN OF THE REACTOR FROM | | LESS THAN 1% POWER, A ROD CONTROL MALFUNCTION OCCURRED. BANK 'D' CONTROL | | RODS FAILED TO CEASE INSERTING UPON REACHING THEIR OFFSET POSITION. IN | | ADDITION, CONTROL BANK 'B' RODS FAILED TO BEGIN STEPPING IN AT THE | | APPROPRIATE OVERLAP POINT. CONTROL BANK 'C' RODS RESPONDED NORMALLY. AS A | | RESULT OF THE ABNORMAL ROD RESPONSE, OPERATORS MANUALLY TRIPPED THE | | REACTOR. ALL RODS FULLY INSERTED. THERE WERE NO ENGINEERED SAFETY | | FEATURES ACTUATIONS. AUXILIARY FEEDWATER WAS BEING USED TO FEED THE STEAM | | GENERATORS BOTH BEFORE AND AFTER THE UNIT TRIP. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. OPERATORS ARE USING NORMAL | | CHARGING AND MAKEUP, PRESSURIZER HEATERS AND SPRAYS, AND THE REACTOR | | COOLANT PUMPS FOR PRIMARY SYSTEM INVENTORY, PRESSURE, AND TRANSPORT | | CONTROL. AUXILIARY FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS, | | AND SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER. ALL EMERGENCY CORE | | COOLING EQUIPMENT IS AVAILABLE IF NEEDED. | | | | THE CAUSE OF THE ROD CONTROL MALFUNCTION IS UNKNOWN AT THIS TIME. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30273 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 07:50 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 07:30[EDT]| |NRC NOTIFIED BY: BRYAN CROKE |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LOSS OF EMERGENCY NOTIFICATION SYSTEM (ENS) AND LONG DISTANCE COMMERCIAL | | TELEPHONE LINES (REFER TO RELATED EVENT #30274.) | | | | THE LICENSEE REPORTED THE LOSS OF ENS AND LONG DISTANCE COMMERCIAL | | TELEPHONE LINES. COMMUNICATIONS HAVE BEEN ESTABLISHED THROUGH REMVEC | | (REGIONAL DISPATCH CENTER). THE CAUSE OF THE LOSS OF THE PHONE LINES IS | | BELIEVED TO HAVE BEEN CAUSED BY A TRUCK ACCIDENT WHICH DISABLED A LONG | | DISTANCE CARRIER FOR AT&T. | | | | THE NRC RESIDENT INSPECTOR IS AWARE OF THIS EVENT. (REFER TO THE HOO LOG | | FOR THE REMVEC TELEPHONE NUMBER.) | | | | * * * 0843 APRIL 11, 1996, UPDATE FROM CROKE RECEIVED BY TROCINE * * * | | | | THE LICENSEE CAN ALSO BE REACHED THROUGH YANKEE ATOMIC (THE CORPORATE | | OFFICE) IN BOLTON, MASSACHUSETTS. (REFER TO THE HOO LOG FOR THE CORPORATE | | OFFICE TELEPHONE NUMBER.) | | | | * * * 1109 APRIL 11, 1996, UPDATE FROM CROKE RECEIVED BY TROCINE * * * | | | | THE LICENSEE WAS INFORMED THAT THE COMMERCIAL LINES HAVE BEEN RESTORED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER INFORMED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30274 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: YANKEE ROWE REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 08:11 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 07:15[EDT]| |NRC NOTIFIED BY: DAVID JOYCE |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |AENS 50.72(b)(1)(v) ENS INOPERABLE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY NOTIFICATION SYSTEM (ENS) AND COMMERCIAL LINES INOPERABLE (REFER | | TO RELATED EVENT #30273.) | | | | THE LICENSEE REPORTED THE LOSS OF COMMERCIAL LONG DISTANCE AND ENS LINES. | | COMMUNICATIONS HAVE BEEN ESTABLISHED THROUGH THE CORPORATE OFFICE IN | | BOLTON, MASSACHUSETTS. THE CAUSE OF THE LOSS OF COMMUNICATIONS IS BELIEVED | | TO HAVE BEEN CAUSED BY A TRUCK ACCIDENT WHICH DISABLED A LONG DISTANCE | | CARRIER FOR AT&T. | | | | THE LICENSEE INFORMED THE VERMONT YANKEE RESIDENT INSPECTOR OF THIS EVENT. | | (REFER TO THE HOO LOG LOG FOR THE CORPORATE OFFICE TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30275 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 04/11/96 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 13:28 [ET]| |RX TYPE: [3] CE |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 11:45[CDT]| |NRC NOTIFIED BY: LITOLFF |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VANDENBURGH 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUXILIARY COMPONENT COOLING WATER SYSTEM MAY NOT HAVE BEEN ABLE TO | | ADEQUATELY PERFORM SAFETY FUNCTION | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON 4/11/96, A FLOW BALANCE TEST WAS PERFORMED ON WATERFORD 3 AUXILIARY | | COMPONENT COOLING WATER (ACCW) SYSTEM TRAIN 'B' DUE TO THE DISCOVERY THAT | | VALVES WERE POSITIONED DIFFERENTLY THAN DURING STARTUP TESTING. THE | | PURPOSE OF THE TEST WAS TO VERIFY THE SYSTEM COULD PERFORM ITS REQUIRED | | DESIGN FUNCTION TO PROVIDE 850 GPM TO THE ESSENTIAL CHILLERS WHILE | | MAINTAINING 5000 GPM FLOW THROUGH THE SHELL SIDE OF THE COMPONENT COOLING | | WATER (CCW) SYSTEM HEAT EXCHANGER. ACCW IS REQUIRED TO SUPPLY WATER TO THE | | ESSENTIAL CHILLERS POST-LOCA WHEN THE PRIMARY COOLING WATER SYSTEM (CCW) | | TEMPERATURE REACHES 105øF. | | | | THE TESTING PERFORMED WAS UNABLE TO DEMONSTRATE THAT ACCW TRAIN 'B' COULD | | PERFORM ITS DESIGN SAFETY FUNCTION. APPROXIMATELY 740 GPM WAS ACHIEVED TO | | THE ESSENTIAL CHILLER WITH A CORRESPONDING ACCW FLOW OF AT LEAST 5000 GPM. | | THE CAUSE OF THIS CONDITION AND PERIOD OF TIME IT HAS EXISTED IS UNKNOWN AT | | THIS TIME. ACCW TRAIN 'B' IS CURRENTLY OPERABLE BASED ON PRESENT AMBIENT | | CONDITIONS AND AMBIENT CONDITIONS EXPECTED FOR THE NEAR FUTURE (BASED ON | | HISTORICAL DATA). TESTING OF ACCW TRAIN 'A' IS CURRENTLY BEING PREPARED." | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30276 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 17:24 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 17:10[EDT]| |NRC NOTIFIED BY: BROOKS |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOSLAK 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 +------------------------------------------------------------------------------+ | SINGLE FAILURE COULD RENDER RHR PUMP INOPERABLE | | | | THE FOLLOWING IS TEXT EXCERPTED FROM A LICENSEE SUBMITTAL: | | | | "THE APPENDIX R PROJECT TEAM, WHILE PERFORMING DESIGN VERIFICATION OF THE | | APPENDIX R PROGRAM, IDENTIFIED AN ISSUE (UNRELATED TO APPENDIX R) REGARDING | | THE RHR MINIMUM FLOW VALVE AND THE LOCA SINGLE FAILURE ANALYSIS. | | SPECIFICALLY, A POTENTIAL FOR RHR PUMP DAMAGE EXISTS, DUE TO LACK OF | | MINIMUM FLOW PROTECTION, WHICH IMPACTS THE LOCA ANALYSIS. | | | | THE RHR MINIMUM FLOW VALVES (V10-16A/B) ARE NORMALLY CLOSED. ONE MINIMUM | | FLOW LINE EXISTS PER TRAIN. THE TWO RHR PUMPS PER TRAIN ARE CROSS-POWERED | | (i.e. ONE PUMP IS POWERED FROM BUS 3 AND ONE FROM BUS 4). THE MINIMUM FLOW | | VALVE IN EACH TRAIN IS POWERED BY A SINGLE BUS (EITHER 3 OR 4). THEREFORE, | | IF BUS 4 IS LOST AS A RESULT OF A SINGLE FAILURE, THE 'A' TRAIN OF RHR IS | | LOST WITH THE EXCEPTION OF THE ONE CROSS-CONNECTED RHR PUMP WHICH IS | | POWERED FROM BUS 3 AND THE 'A' LPCI INJECTION VALVES WHICH ARE POWERED FROM | | THE 480 VOLT UPS. THE 'A' TRAIN MINIMUM FLOW VALVE V10-16A, HOWEVER, WOULD | | REMAIN CLOSED DUE TO THE LOSS OF BUS 4. FOR ACCIDENT SCENARIOS WHERE THE | | RHR PUMPS WOULD AUTOMATICALLY START, BUT MUST OPERATE ON MINIMUM FLOW UNTIL | | THE REACTOR IS DEPRESSURIZED, THE LOSS OF MINIMUM FLOW PROTECTION FOR THE | | CROSS-CONNECTED PUMP MUST BE CONSIDERED. | | | | THE LOCA ANALYSIS CONSIDERS THE MOST SEVERE SINGLE FAILURES AS DISCUSSED IN | | FSAR SECTION 6.5.2.1.4.3. THE POTENTIAL LOSS OF THE RHR PUMP POWERED BY | | THE CROSS-CONNECTED BUS, DUE TO FAILURE OF THE MINIMUM FLOW VALVE TO OPEN, | | WAS NOT CONSIDERED. DISCUSSION WITH [THE LICENSEE'S] LOCA GROUP INDICATES | | THAT AN INTERMEDIATE RECIRCULATION LINE BREAK WHICH DOES NOT DEPRESSURIZE | | QUICKLY, COUPLED WITH A SINGLE FAILURE OF THE DC BUS WHICH POWERS HPCI IS | | PROBABLY THE MOST LIMITING CASE. PRESENTLY, THE ANALYSIS ASSUMES THAT 1 | | CORE SPRAY PUMP, PLUS 1 RHR PUMP IN THE TRAIN NOT AFFECTED BY THE BREAK | | WOULD BE AVAILABLE FOR THIS CASE. THE AVAILABILITY OF THE RHR PUMP FOR | | THIS EVENT IS IN QUESTION BECAUSE THE POWER TO THE NORMALLY CLOSED MINIMUM | | FLOW VALVE WOULD BE LOST AND THE PUMP WOULD THEREFORE HAVE TO OPERATE DEAD | | HEADED FOR A SHORT PERIOD OF TIME UNTIL THE REACTOR WAS DEPRESSURIZED." | | | | THE LICENSEE STATED THAT THE CURRENT LOCA ANALYSIS PREDICTS A PEAK CLADDING | | TEMPERATURE (PCT) OF 1778øF BUT THAT THE PREDICTED TEMPERATURE WOULD RISE | | TO 1806øF IF THE RHR PUMP WAS ASSUMED TO FAIL. THE LICENSEE IS STILL | | PERFORMING AN ENGINEERING ANALYSIS OF THIS SCENARIO. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30277 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 18:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: KONOVALCHICK |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOSLAK RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE PLANS PRESS RELEASE REGARDING COCAINE FOUND IN PROTECTED AREA | | | | AT 1530, THE RADIATION PROTECTION SUPERVISOR WAS NOTIFIED THAT THE CONTENTS | | OF A PACKET FOUND ONSITE EARLIER IN THE DAY HAD TESTED POSITIVE FOR | | COCAINE. THE PACKET CONTAINED LESS THAN ONE OUNCE OF POWDER. THE PACKET | | HAD BEEN DISCOVERED BY A HEALTH PHYSICS TECHNICIAN IN A LOCKER WHERE HE WAS | | PLACING HIS BELONGINGS. THE LICENSEE QUARANTINED THE LOCKER ROOM AND | | PERFORMED A SEARCH OF ALL LOCKERS. THIS LOCKER ROOM IS PRIMARILY USED BY | | HEALTH PHYSICS TECHNICIANS. THE LICENSEE PLANS TO MAKE A PRESS RELEASE | | REGARDING THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 2222 ON 04/11/96, FROM SAUER TAKEN BY STRANSKY * * * | | | | THE LICENSEE CALLED TO CORRECT SOME INFORMATION PROVIDED IN THE INITIAL | | REPORT. THE PACKET WAS FOUND BY THE HEALTH PHYSICS TECHNICIAN IN A LOCKER | | THAT HAD PREVIOUSLY BEEN ASSIGNED TO HIM BUT THAT HE HAD VACATED SOME TIME | | AGO. THE LICENSEE ALSO REPORTED THAT A DRUG SNIFFING DOG WAS BROUGHT IN TO | | SEARCH THE LOCKER ROOM, BUT NO ADDITIONAL DRUGS WERE FOUND. THE LICENSEE | | WILL PURSUE THIS MATTER FURTHER. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30278 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/11/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 19:01 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 18:15[EDT]| |NRC NOTIFIED BY: NEFF |LAST UPDATE DATE: 04/11/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOSLAK RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A COMPROMISE OF SAFEGUARDS INFORMATION. IMMEDIATE | | COMPENSATORY ACTIONS WERE TAKEN UPON DISCOVERY. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. (REFER TO THE HOO LOG FOR | | DETAILS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30279 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/12/96 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 00:35 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 23:37[EDT]| |NRC NOTIFIED BY: ROY GREEN |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS MOSLAK RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE LOSS OF REACTOR | | COOLANT LEAKAGE DETECTION WHEN AN ELECTRICAL PROTECTION ASSEMBLY (EPA) | | BREAKER TRIPPED (REFER TO EVENT #30261 FOR A SIMILAR EVENT THAT OCCURRED | | ON APRIL 10, 1996.) | | | | AT 2337 ON APRIL 11, 1996, EPA BREAKER 2VBS*ACB2A TRIPPED RESULTING IN A | | HALF SCRAM, HALF MAIN STEAM ISOLATION VALVE (MSIV) ISOLATION, AND DIVISION | | 1 NUCLEAR STEAM SUPPLY SHUTOFF SYSTEM (NSSSS) ISOLATION. THE ISOLATION | | CAUSED A TOTAL LOSS OF THE REACTOR COOLANT LEAKAGE DETECTION SYSTEM, AND | | THIS REQUIRED THE ENTRY INTO TECHNICAL SPECIFICATION 3.0.3. TECHNICAL | | SPECIFICATION 3.0.3 REQUIRES THE LICENSEE TO RESTORE THE SYSTEM TO OPERABLE | | STATUS OR TO COMMENCE A UNIT SHUTDOWN WITHIN 1 HOUR, PLACE THE UNIT IN | | STARTUP WITHIN THE NEXT 6 HOURS, AND PLACE THE UNIT IN HOT SHUTDOWN WITHIN | | THE FOLLOWING 6 HOURS. A REACTOR SHUTDOWN WAS COMMENCED AT 0012 ON APRIL | | 12, 1996. ALL EMERGENCY CORE COOLING SYSTEMS ARE AVAILABLE, AND THE GRID | | IS STABLE. | | | | THE EPA BREAKER TRIP ALSO CAUSED THE FOLLOWING ENGINEERED SAFETY FEATURES | | ACTUATIONS: SECONDARY CONTAINMENT ISOLATION; STANDBY GAS TREATMENT SYSTEM | | INITIATION; DIVISION 1 CONTROL ROOM SPECIAL FILTER TRAIN AUTOMATIC START; | | AND NSSSS GROUP 2, 3, 4, 5, 6, 8, AND 9 ISOLATIONS ON DIVISION 1. LOSS OF | | COOLANT ACCIDENT OVERRIDE SWITCHES WERE USED TO RESTORE INSTRUMENT AIR TO | | THE MSIVs, AND RECIRCULATION PUMP COOLING WATER ISOLATION VALVES WERE | | DE-ENERGIZED AND MANUALLY OPENED REQUIRING ENTRY INTO TECHNICAL | | SPECIFICATION 3.6.3 AT 2343 ON APRIL 11, 1996. TECHNICAL SPECIFICATION | | 3.6.3 REQUIRES THE LICENSEE TO HAVE THE PENETRATION ISOLATED WITHIN 4 HOURS | | OR TO PLACE THE UNIT IN HOT SHUTDOWN WITHIN THE FOLLOWING 12 HOURS. | | | | THIS EVENT IS SIMILAR TO AN EVENT WHICH OCCURRED ON THE SAME UNIT ON APRIL | | 10, 1996. (REFER TO EVENT #30461 FOR ADDITIONAL INFORMATION.) THE | | LICENSEE HAD BEEN DEVELOPING A PROCEDURE TO REPAIR THE FAILED EPA BREAKER | | WITH THE UNIT ON LINE AND THE BREAKER ENERGIZED. WHILE THE PROCEDURE WAS | | BEING DEVELOPED, THE BREAKER HAD BEEN RECLOSED. NOW THAT THE BREAKER HAS | | TRIPPED OPEN AGAIN, IT WILL NOT RECLOSE. THEREFORE, THE LICENSEE IS | | MODIFYING ITS PLAN AND WILL NOW REPLACE THE FAILED EPA BREAKER. A NEW | | BREAKER HAS ALREADY BEEN BENCH CALIBRATED. THE LICENSEE CURRENTLY BELIEVES | | THAT THE BREAKER FAILURE MAY HAVE RESULTED FROM A CONTROL MODULE PROBLEM. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+