U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/12/96 - 04/15/96 ** EVENT NUMBERS ** 30246 30277 30279 30280 30281 30282 30283 30284 30285 30286 30287 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30246 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/07/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:26 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/07/96 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: JOE SKLARCZYK |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |DTMP 73.71(b)(1) SABOTAGE |EDWARD BUTCHER EO | | |EUGENE MCPEEK IAT | | |ROBERTA WARREN IAT | | |RICH BARRET ERB | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL SABOTAGE | | | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. SEE THE HOO LOG FOR FURTHER DETAILS ON | | THIS EVENT. | | | | * * * UPDATE AT 1117 ON 04/12/96, FROM MAREK TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT AFTER FURTHER INVESTIGATION AND | | INTERVIEWS WITH THE PERSONNEL INVOLVED. DETAILS ARE AVAILABLE IN THE HOO | | LOG. THE HOO NOTIFIED THE R3DO (BURGESS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 04/12/96 | |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. | | | | * * * UPDATE AT 1455 ON 04/12/96, FROM GALLAHER TAKEN BY STRANSKY * * * | | | | THE LICENSEE CALLED TO REPORT THAT NO PRESS RELEASE WOULD BE MADE REGARDING | | THIS EVENT. THE HOO NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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 CURRENTLY 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.) FOLLOWING | | THE PREVIOUS EVENT, THE LICENSEE BEGAN TO DEVELOP 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. | | | | * * * UPDATE AT 1118 ON APRIL 12, 1996 FROM BOOTH RECEIVED BY TROCINE * * * | | | | SEVERAL LIMITING CONDITIONS FOR OPERATION (LCO) HAVE CHANGED SINCE THE TIME | | ON THE INITIAL NOTIFICATION. THE LICENSEE IS CURRENTLY MAINTAINING THE | | UNIT AT APPROXIMATELY 92% REACTOR POWER. THE UNIT EXITED THE TECHNICAL | | SPECIFICATION 3.0.3 REQUIRED SHUTDOWN CONDITION BY RESTORING POWER TO THE | | REACTOR COOLANT LEAKAGE MONITORING DETECTION SYSTEM. | | | | SUBSEQUENT TO THE INITIAL NOTIFICATION, THE SECOND OF TWO STANDBY GAS | | TREATMENT TRAINS WAS DECLARED INOPERABLE DUE TO LOW TEMPERATURES WITHIN THE | | REACTOR BUILDING. THIS PLACED THE UNIT IN A CONDITION THAT REQUIRES HOT | | SHUTDOWN STATUS BY 1609 ON APRIL 12, 1969, PER TECHNICAL SPECIFICATION | | 3.6.5.3. THIS CONDITION IS EXPECTED TO BE EXITED PRIOR TO THIS TIME, AND | | PLANT SHUTDOWN IS NOT ANTICIPATED. | | | | SUBSEQUENT TO THE INITIAL NOTIFICATION, POWER WAS NOT RESTORED TO VARIOUS | | FAILED OPEN CONTAINMENT ISOLATION VALVES WITHIN THE REQUIRED 4 HOURS | | ALLOWED BY TECHNICAL SPECIFICATION 3.6.3, AND THIS PLACED THE PLANT IN A | | CONDITION THAT REQUIRED HOT SHUTDOWN STATUS BY 1543 ON APRIL 12, 1996. THIS | | CONDITION WAS EXITED AT 0906 ON APRIL 12, 1996. | | | | REPAIRS TO THE INITIATING EVENT FAULTY EQUIPMENT (THE EPA BREAKER) ARE | | EXPECTED TO BE COMPLETED TODAY PRIOR TO THE EXPIRATION OF THE LCO FOR | | TECHNICAL SPECIFICATION 3.8.4.4. APPARENTLY, THE EPA BREAKER HAS BEEN | | REPLACED, AND THE LICENSEE IS IN THE PROCESS OF PERFORMING POST-MAINTENANCE | | TESTING. THIS 72-HOUR LCO EXPIRES AT 0011 ON APRIL 13, 1996. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 13:45 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 00:00[PDT]| |NRC NOTIFIED BY: McGAWN |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VANDENBURGH RDO | |NLTR LICENSEE 24 HR REPORT | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - SAFEGUARDS SYSTEM DEGRADATION RELATED TO AREA BOUNDARY | | | | NO ADVERSE CONSEQUENCES TO THE PLANT HAVE OCCURRED. SEE HOO LOG FOR | | DETAILS. THIS IS A VIOLATION OF LICENSE CONDITION 2.E. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30281 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 14:27 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: MINER |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LICENSED EMPLOYEE WAS ARRESTED FOR DRIVING UNDER THE INFLUENCE. THE | | EMPLOYEE HAS ENTERED THE LICENSEE'S EMPLOYEE ASSISTANCE PROGRAM. SEE HOO | | LOG FOR DETAILS. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30282 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/12/96 | +------------------------------------------------+EVENT TIME: 11:32[CDT]| |NRC NOTIFIED BY: McCALLUM |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURGESS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 1 STARTUP | 1 STARTUP | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VARIOUS CONTAINMENT ISOLATIONS DUE TO TRIP OF RPS MOTOR-GENERATOR SET | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON APRIL 12, 1996, AT 1132 CDT, A CONTRACTOR WAS PAINTING NEAR THE UNIT 1 | | '1B' REACTOR PROTECTION SYSTEM (RPS) MOTOR-GENERATOR (MG) SET AND | | INADVERTENTLY TRIPPED THE ELECTRIC POWER MONITORING ASSEMBLY WHICH RESULTED | | IN THE LOSS OF THE '1B' RPS MG SET, A REACTOR HALF SCRAM, AND ISOLATIONS OF | | GROUPS 1 THROUGH 7 AND 10, EXCEPT REACTOR BUILDING CLOSED COOLING WATER | | SYSTEM, PRIMARY CONTAINMENT CHILL WATER SYSTEM, AND THE MAIN STEAM | | ISOLATION VALVES (MSIV). | | | | ON THE LOSS OF THE '1B' RPS MG SET, UNIT 1 RESPONDED AS DESIGNED. A B1/B2 | | REACTOR HALF SCRAM WAS RECEIVED, AND ALL PRIMARY CONTAINMENT ISOLATION | | INBOARD AND OUTBOARD VALVES REACTED TO THEIR DESIGNED POSITIONS FOR GROUPS | | 1 THROUGH 7 AND 10 ISOLATION SIGNALS. AS DESIGNED, THE MSIVs, PRIMARY | | CONTAINMENT CHILL WATER SYSTEM, AND REACTOR BUILDING CLOSED COOLING WATER | | SYSTEM DID NOT ISOLATE. AT APPROXIMATELY 1133, THE '1B' RPS BUS WAS TAKEN | | TO ITS ALTERNATE POWER SUPPLY. THE AREA TEMPERATURES WERE MONITORED FOR | | ABNORMAL TEMPERATURE INCREASES, AND NO ABNORMALITIES WERE IDENTIFIED. AT | | 1133, THE GROUP 1 MSIV ISOLATION LOGIC WAS BYPASSED, AND A 1-HOUR TIME | | CLOCK WAS ENTERED. | | | | THE CAUSE OF THE LOSS OF RPS WAS IDENTIFIED AS AN INADVERTENT | | DEENERGIZATION OF THE ELECTRIC POWER MONITORING ASSEMBLY. AT 1209, THE | | '1B' RPS MG SET WAS PROPERLY LINED UP AND PLACED BACK INTO OPERATION. AT | | 1215, THE UNIT 1 REACTOR BUILDING VENTILATION WAS ESTABLISHED, AND AT 1225, | | THE GROUP 1 MSIV ISOLATION LOGIC WAS TAKEN OUT OF BYPASS. | | | | UPON RETURNING THE PRIMARY CONTAINMENT ISOLATION INBOARD AND OUTBOARD | | VALVES TO THEIR APPROPRIATE POSITIONS, THE FOLLOWING ABNORMALITIES WERE | | IDENTIFIED: THE DIVISION 1 POST-LOCA OXYGEN MONITOR INDICATION APPEARED | | ERRATIC, THE '1B' REACTOR BUILDING VENTILATION EXHAUST FAN AUTOMATICALLY | | TRIPPED WHEN AN ATTEMPT WAS MADE TO RESTART THE FAN, AND THE REACTOR | | BUILDING VENTILATION SUPPLY DAMPER SHOWED DUAL INDICATION WHEN REOPENED. | | THE DAMPER WAS CYCLED CLOSED, THEN BACK OPEN, AND THE APPROPRIATE FULL OPEN | | INDICATION WAS RECEIVED. THE '1B' REACTOR BUILDING VENTILATION EXHAUST FAN | | CONTROL SWITCH WAS TAKEN TO PULL-TO-LOCK, AND THE '1C' SUPPLY AND EXHAUST | | FANS WERE STARTED. ACTION REQUESTS HAVE BEEN WRITTEN TO CORRECT THESE | | DISCREPANCIES. | | | | THE LOSS OF THE MG SET ALSO AFFECTED UNIT 2 BY CLOSING THE REACTOR BUILDING | | VENTILATION DAMPERS AND STARTING THE UNIT 2 STANDBY GAS TREATMENT SYSTEM | | TRAIN. THE MAIN STEAM LINE TUNNEL TEMPERATURES WERE MONITORED TO ENSURE NO | | STEAM LEAK WAS CREATING THE INCREASING STEAM TUNNEL TEMPERATURES. THE | | DIVISION 2 ISOLATION SIGNAL FOR A GROUP 1 MSIV ISOLATION WAS DEFEATED AT | | 1133 TO PREVENT AN MSIV ISOLATION, AND A 1-HOUR TIME CLOCK WAS ESTABLISHED | | PER LOA-VR-101. AT 1200, LGA-02 WAS ENTERED ON ABOVE MAXIMUM NORMAL | | TEMPERATURE (WHICH REACHED 149øF IN THE MAIN STEAM LINE PIPE TUNNEL). THE | | REACTOR WATER CLEANUP SYSTEM ISOLATIONS WERE ALSO DEFEATED TO PREVENT AN | | ISOLATION (1-HOUR TIME CLOCK ESTABLISHED) DURING THE STARTUP OF THE REACTOR | | BUILDING VENTILATION SYSTEM. AREA TEMPERATURES WERE MONITORED TO ENSURE | | THAT THE INCREASE IN REACTOR BUILDING TEMPERATURES WAS THE RESULT OF THE | | LOSS OF REACTOR BUILDING VENTILATION AND NOT DUE TO A PRIMARY SYSTEM | | BREACH. AT 1215, UNIT 2 ESTABLISHED REACTOR BUILDING VENTILATION, AND AT | | 1228, TEMPERATURES HAD STABILIZED TO ALLOW THE REMOVAL OF THE ISOLATION | | JUMPERS." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30283 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 20:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/12/96 | +------------------------------------------------+EVENT TIME: 16:50[PDT]| |NRC NOTIFIED BY: PIERCE |LAST UPDATE DATE: 04/12/96 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SIX OF TEN MAIN STEAM SAFETY VALVE LIFT SETPOINTS WERE FOUND OUT OF | | TOLERANCE. | | | | WHILE REVIEWING THE RESULTS OF AUGMENTED TESTING OF UNIT 1 MAIN STEAM | | SAFETY VALVES, THE LICENSEE DETERMINED THAT SIX OF THE TEN VALVES WHICH | | WERE TESTED HAD AS-FOUND LIFT SETPOINTS THAT EXCEEDED THE TECHNICAL | | SPECIFICATION SETPOINT TOLERANCE OF ñ3%. PRELIMINARY ANALYSIS OF THIS DATA | | INDICATES THAT THIS CONSTITUTES A CONDITION OUTSIDE THE DESIGN BASIS OF THE | | PLANT. THE AUGMENTED TESTING WAS BEING PERFORMED IN ACCORDANCE WITH | | AGREEMENTS REACHED WITH THE NRC TO ADDRESS PRIOR SETPOINT DRIFT CONCERNS. | | THE LICENSEE PLANS TO TEST THE REMAINING TEN MAIN STEAM SAFETY VALVES ON | | UNIT 1. THE LICENSEE REPORTED THAT THESE SAFETY VALVES ARE DRESSER MODEL | | #3707R. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30284 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/13/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 20:25 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 04/13/96 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: BAUDHAUER |LAST UPDATE DATE: 04/13/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY-RELATED BATTERY CHARGERS MAY NOT BE QUALIFIED FOR ALL INPUT VOLTAGES | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THIS REPORT IS FOR SUSPECTED OPERATION OUTSIDE OF THE DESIGN BASIS. | | SAFETY-RELATED BATTERY CHARGERS USED AT CRYSTAL RIVER UNIT 3 ARE REQUIRED | | TO OPERATE WITHIN A SPECIFIED RANGE OF AC INPUT VOLTAGE. THE VENDOR | | PREVIOUSLY CERTIFIED THE BATTERY CHARGERS AS QUALIFIED TO OPERATE WITHIN | | THE REQUIRED VALUES. ON 04/11/96, THE VENDOR STATED IN WRITING THAT THE | | BATTERY CHARGERS WERE NOT ACTUALLY TESTED TO THE CRYSTAL RIVER UNIT 3 | | REQUIRED VALUES AND, THEREFORE, REQUIRE ADDITIONAL TESTING TO ASSURE THE | | BATTERY CHARGERS WILL MEET DESIGN REQUIREMENTS." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30285 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/14/96 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 09:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/14/96 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: CLAYTON CHA |LAST UPDATE DATE: 04/14/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN HANNON, NRR EO | | |JIM MUSE FEMA | | |RICH BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNUSUAL EVENT DECLARED ON UNIT 2 DUE TO 2 OF 2 EDGs BEING INOPERABLE - | | | | UNIT 1 IS AT 100% POWER WITH 2 OF 2 EDGs OPERABLE. UNIT 2 IS IN MODE 6 IN | | A REFUELING OUTAGE WITH THE ENTIRE CORE OFFLOADED INTO THE SPENT FUEL POOL. | | THE UNIT 2 'CD' EDG (1 OF 2 EDGs) IS INOPERABLE FOR MAINTENANCE ACTIVITIES. | | | | AT 1000, THE LICENSEE DECLARED THE SECOND OF 2 UNIT 2 EDGs ('AB') | | INOPERABLE FOR MAINTENANCE ACTIVITIES AND DECLARED AN UNUSUAL EVENT ON | | UNIT 2 IN ACCORDANCE WITH THE EMERGENCY PLAN DUE TO 2 OF 2 UNIT 2 EDGs | | BEING INOPERABLE WITH UNIT 2 IN MODE 6 WITH THE CORE DEFUELED. | | | | THERE IS NO UNIT 2 TECH SPEC LCO ACTION STATEMENT APPLICABLE TO 2 OF 2 EDGs | | BEING INOPERABLE WITH UNIT 2 IN MODE 6 WITH THE CORE DEFUELED. | | | | THE LICENSEE DECLARED THE UNIT 2 'AB' EDG INOPERABLE WHILE THE UNIT 2 'CD' | | EDG WAS INOPERABLE SO AS NOT TO EXTEND THE LENGTH OF THE UNIT 2 REFUELING | | OUTAGE BEYOND THE PRESENT SCHEDULED UNIT 2 RESTART DATE OF 05/05/96. | | | | THE NORMAL ELECTRICAL POWER SUPPLY (OFFSITE POWER) FOR BOTH UNITS FOR | | THE SPENT FUEL POOL COOLING SYSTEM IS AVAILABLE, AND THE UNIT 1 BACKUP | | POWER SUPPLY (2 EDGs) FOR THE SPENT FUEL COOLING SYSTEM IS AVAILABLE. | | THE UNIT 2 BACKUP POWER SUPPLY (2 EDGs) FOR THE SPENT FUEL POOL COOLING | | SYSTEM IS INOPERABLE. | | | | THE LICENSEE PLANS TO COMPLETE THE MAINTENANCE ACTIVITIES ON THE "CD' EDG, | | DECLARE IT OPERABLE, AND TERMINATE THE UNUSUAL EVENT WITHIN 2 DAYS. | | | | THE LICENSEE NOTIFIED STATE & LOCAL OFFICIALS & THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30286 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/14/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 16:31 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 04/14/96 | +------------------------------------------------+EVENT TIME: 14:30[EDT]| |NRC NOTIFIED BY: BANDHAUER |LAST UPDATE DATE: 04/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CLOSED CYCLE COOLING WATER PUMP INADVERTENTLY STARTED DURING A TEST. | | | | DURING PERFORMANCE OF A SURVEILLANCE TEST, AN OPERATOR MISSED A STEP IN THE | | PROCEDURE FAILING TO BLOCK THE ACTUATION OF THE '1A' CLOSED CYCLE COOLING | | WATER PUMP. WHEN THE OPERATOR PROCEEDED WITH THE TEST, THE PUMP STARTED | | AND OPERATED PROPERLY. NO COMPONENTS WERE DAMAGED AS A RESULT OF THIS | | EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30287 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/14/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 16:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/14/96 | +------------------------------------------------+EVENT TIME: 15:10[EDT]| |NRC NOTIFIED BY: COLEMAN |LAST UPDATE DATE: 04/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HALF SCRAM SIGNAL AND VARIOUS ESF ACTUATIONS DUE TO ELECTRICAL FAULT | | | | WITH THE REACTOR VESSEL FLOODED AND THE HEAD REMOVED FOR FUEL MOVEMENT, THE | | NORMAL SUPPLY TRANSFORMER TO THE 'D' 600-VAC ELECTRICAL BUS TRIPPED DUE TO | | DIFFERENTIAL OVERCURRENT. THE LOSS OF THE 'D' 600-VAC BUS CAUSED A LOSS OF | | POWER TO THE 'B' RPS BUS RESULTING IN A HALF SCRAM SIGNAL, THE CLOSURE OF | | THE RHR SHUTDOWN COOLING SUCTION ISOLATION VALVE (#1-E11-F009), THE | | AUTOMATIC START OF ALL FOUR TRAINS OF THE STANDBY GAS TREATMENT SYSTEM, AND | | A CONTROL ROOM VENTILATION SYSTEM REALIGNMENT. | | | | THE LICENSEE RESTORED POWER TO THE 'D' 600-VAC BUS AT 1525 USING THE | | ALTERNATE POWER SUPPLY, AND THE RHR SHUTDOWN COOLING SYSTEM WAS RESTORED TO | | SERVICE AT 1625. THE SPENT FUEL POOL COOLING SYSTEM AND THE DECAY HEAT | | REMOVAL SYSTEM CONTINUED TO OPERATE THROUGHOUT THE EVENT. NO INCREASE IN | | REACTOR VESSEL WATER TEMPERATURE WAS DETECTED AS A RESULT OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/12/96 - 04/15/96 ** EVENT NUMBERS ** 30246 30277 30279 30280 30281 30282 30283 30284 30285 30286 30287 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30246 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/07/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:26 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/07/96 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: JOE SKLARCZYK |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |DTMP 73.71(b)(1) SABOTAGE |EDWARD BUTCHER EO | | |EUGENE MCPEEK IAT | | |ROBERTA WARREN IAT | | |RICH BARRET ERB | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL SABOTAGE | | | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. SEE THE HOO LOG FOR FURTHER DETAILS ON | | THIS EVENT. | | | | * * * UPDATE AT 1117 ON 04/12/96, FROM MAREK TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT AFTER FURTHER INVESTIGATION AND | | INTERVIEWS WITH THE PERSONNEL INVOLVED. DETAILS ARE AVAILABLE IN THE HOO | | LOG. THE HOO NOTIFIED THE R3DO (BURGESS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 04/12/96 | |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. | | | | * * * UPDATE AT 1455 ON 04/12/96, FROM GALLAHER TAKEN BY STRANSKY * * * | | | | THE LICENSEE CALLED TO REPORT THAT NO PRESS RELEASE WOULD BE MADE REGARDING | | THIS EVENT. THE HOO NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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 CURRENTLY 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.) FOLLOWING | | THE PREVIOUS EVENT, THE LICENSEE BEGAN TO DEVELOP 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. | | | | * * * UPDATE AT 1118 ON APRIL 12, 1996 FROM BOOTH RECEIVED BY TROCINE * * * | | | | SEVERAL LIMITING CONDITIONS FOR OPERATION (LCO) HAVE CHANGED SINCE THE TIME | | ON THE INITIAL NOTIFICATION. THE LICENSEE IS CURRENTLY MAINTAINING THE | | UNIT AT APPROXIMATELY 92% REACTOR POWER. THE UNIT EXITED THE TECHNICAL | | SPECIFICATION 3.0.3 REQUIRED SHUTDOWN CONDITION BY RESTORING POWER TO THE | | REACTOR COOLANT LEAKAGE MONITORING DETECTION SYSTEM. | | | | SUBSEQUENT TO THE INITIAL NOTIFICATION, THE SECOND OF TWO STANDBY GAS | | TREATMENT TRAINS WAS DECLARED INOPERABLE DUE TO LOW TEMPERATURES WITHIN THE | | REACTOR BUILDING. THIS PLACED THE UNIT IN A CONDITION THAT REQUIRES HOT | | SHUTDOWN STATUS BY 1609 ON APRIL 12, 1969, PER TECHNICAL SPECIFICATION | | 3.6.5.3. THIS CONDITION IS EXPECTED TO BE EXITED PRIOR TO THIS TIME, AND | | PLANT SHUTDOWN IS NOT ANTICIPATED. | | | | SUBSEQUENT TO THE INITIAL NOTIFICATION, POWER WAS NOT RESTORED TO VARIOUS | | FAILED OPEN CONTAINMENT ISOLATION VALVES WITHIN THE REQUIRED 4 HOURS | | ALLOWED BY TECHNICAL SPECIFICATION 3.6.3, AND THIS PLACED THE PLANT IN A | | CONDITION THAT REQUIRED HOT SHUTDOWN STATUS BY 1543 ON APRIL 12, 1996. THIS | | CONDITION WAS EXITED AT 0906 ON APRIL 12, 1996. | | | | REPAIRS TO THE INITIATING EVENT FAULTY EQUIPMENT (THE EPA BREAKER) ARE | | EXPECTED TO BE COMPLETED TODAY PRIOR TO THE EXPIRATION OF THE LCO FOR | | TECHNICAL SPECIFICATION 3.8.4.4. APPARENTLY, THE EPA BREAKER HAS BEEN | | REPLACED, AND THE LICENSEE IS IN THE PROCESS OF PERFORMING POST-MAINTENANCE | | TESTING. THIS 72-HOUR LCO EXPIRES AT 0011 ON APRIL 13, 1996. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (MOSLAK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [2] [3] STATE: CA |NOTIFICATION TIME: 13:45 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 04/11/96 | +------------------------------------------------+EVENT TIME: 00:00[PDT]| |NRC NOTIFIED BY: McGAWN |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VANDENBURGH RDO | |NLTR LICENSEE 24 HR REPORT | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - SAFEGUARDS SYSTEM DEGRADATION RELATED TO AREA BOUNDARY | | | | NO ADVERSE CONSEQUENCES TO THE PLANT HAVE OCCURRED. SEE HOO LOG FOR | | DETAILS. THIS IS A VIOLATION OF LICENSE CONDITION 2.E. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30281 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 14:27 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/10/96 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: MINER |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A LICENSED EMPLOYEE WAS ARRESTED FOR DRIVING UNDER THE INFLUENCE. THE | | EMPLOYEE HAS ENTERED THE LICENSEE'S EMPLOYEE ASSISTANCE PROGRAM. SEE HOO | | LOG FOR DETAILS. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30282 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 04/12/96 | +------------------------------------------------+EVENT TIME: 11:32[CDT]| |NRC NOTIFIED BY: McCALLUM |LAST UPDATE DATE: 04/12/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BURGESS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 1 STARTUP | 1 STARTUP | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VARIOUS CONTAINMENT ISOLATIONS DUE TO TRIP OF RPS MOTOR-GENERATOR SET | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON APRIL 12, 1996, AT 1132 CDT, A CONTRACTOR WAS PAINTING NEAR THE UNIT 1 | | '1B' REACTOR PROTECTION SYSTEM (RPS) MOTOR-GENERATOR (MG) SET AND | | INADVERTENTLY TRIPPED THE ELECTRIC POWER MONITORING ASSEMBLY WHICH RESULTED | | IN THE LOSS OF THE '1B' RPS MG SET, A REACTOR HALF SCRAM, AND ISOLATIONS OF | | GROUPS 1 THROUGH 7 AND 10, EXCEPT REACTOR BUILDING CLOSED COOLING WATER | | SYSTEM, PRIMARY CONTAINMENT CHILL WATER SYSTEM, AND THE MAIN STEAM | | ISOLATION VALVES (MSIV). | | | | ON THE LOSS OF THE '1B' RPS MG SET, UNIT 1 RESPONDED AS DESIGNED. A B1/B2 | | REACTOR HALF SCRAM WAS RECEIVED, AND ALL PRIMARY CONTAINMENT ISOLATION | | INBOARD AND OUTBOARD VALVES REACTED TO THEIR DESIGNED POSITIONS FOR GROUPS | | 1 THROUGH 7 AND 10 ISOLATION SIGNALS. AS DESIGNED, THE MSIVs, PRIMARY | | CONTAINMENT CHILL WATER SYSTEM, AND REACTOR BUILDING CLOSED COOLING WATER | | SYSTEM DID NOT ISOLATE. AT APPROXIMATELY 1133, THE '1B' RPS BUS WAS TAKEN | | TO ITS ALTERNATE POWER SUPPLY. THE AREA TEMPERATURES WERE MONITORED FOR | | ABNORMAL TEMPERATURE INCREASES, AND NO ABNORMALITIES WERE IDENTIFIED. AT | | 1133, THE GROUP 1 MSIV ISOLATION LOGIC WAS BYPASSED, AND A 1-HOUR TIME | | CLOCK WAS ENTERED. | | | | THE CAUSE OF THE LOSS OF RPS WAS IDENTIFIED AS AN INADVERTENT | | DEENERGIZATION OF THE ELECTRIC POWER MONITORING ASSEMBLY. AT 1209, THE | | '1B' RPS MG SET WAS PROPERLY LINED UP AND PLACED BACK INTO OPERATION. AT | | 1215, THE UNIT 1 REACTOR BUILDING VENTILATION WAS ESTABLISHED, AND AT 1225, | | THE GROUP 1 MSIV ISOLATION LOGIC WAS TAKEN OUT OF BYPASS. | | | | UPON RETURNING THE PRIMARY CONTAINMENT ISOLATION INBOARD AND OUTBOARD | | VALVES TO THEIR APPROPRIATE POSITIONS, THE FOLLOWING ABNORMALITIES WERE | | IDENTIFIED: THE DIVISION 1 POST-LOCA OXYGEN MONITOR INDICATION APPEARED | | ERRATIC, THE '1B' REACTOR BUILDING VENTILATION EXHAUST FAN AUTOMATICALLY | | TRIPPED WHEN AN ATTEMPT WAS MADE TO RESTART THE FAN, AND THE REACTOR | | BUILDING VENTILATION SUPPLY DAMPER SHOWED DUAL INDICATION WHEN REOPENED. | | THE DAMPER WAS CYCLED CLOSED, THEN BACK OPEN, AND THE APPROPRIATE FULL OPEN | | INDICATION WAS RECEIVED. THE '1B' REACTOR BUILDING VENTILATION EXHAUST FAN | | CONTROL SWITCH WAS TAKEN TO PULL-TO-LOCK, AND THE '1C' SUPPLY AND EXHAUST | | FANS WERE STARTED. ACTION REQUESTS HAVE BEEN WRITTEN TO CORRECT THESE | | DISCREPANCIES. | | | | THE LOSS OF THE MG SET ALSO AFFECTED UNIT 2 BY CLOSING THE REACTOR BUILDING | | VENTILATION DAMPERS AND STARTING THE UNIT 2 STANDBY GAS TREATMENT SYSTEM | | TRAIN. THE MAIN STEAM LINE TUNNEL TEMPERATURES WERE MONITORED TO ENSURE NO | | STEAM LEAK WAS CREATING THE INCREASING STEAM TUNNEL TEMPERATURES. THE | | DIVISION 2 ISOLATION SIGNAL FOR A GROUP 1 MSIV ISOLATION WAS DEFEATED AT | | 1133 TO PREVENT AN MSIV ISOLATION, AND A 1-HOUR TIME CLOCK WAS ESTABLISHED | | PER LOA-VR-101. AT 1200, LGA-02 WAS ENTERED ON ABOVE MAXIMUM NORMAL | | TEMPERATURE (WHICH REACHED 149øF IN THE MAIN STEAM LINE PIPE TUNNEL). THE | | REACTOR WATER CLEANUP SYSTEM ISOLATIONS WERE ALSO DEFEATED TO PREVENT AN | | ISOLATION (1-HOUR TIME CLOCK ESTABLISHED) DURING THE STARTUP OF THE REACTOR | | BUILDING VENTILATION SYSTEM. AREA TEMPERATURES WERE MONITORED TO ENSURE | | THAT THE INCREASE IN REACTOR BUILDING TEMPERATURES WAS THE RESULT OF THE | | LOSS OF REACTOR BUILDING VENTILATION AND NOT DUE TO A PRIMARY SYSTEM | | BREACH. AT 1215, UNIT 2 ESTABLISHED REACTOR BUILDING VENTILATION, AND AT | | 1228, TEMPERATURES HAD STABILIZED TO ALLOW THE REMOVAL OF THE ISOLATION | | JUMPERS." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30283 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/12/96 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 20:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/12/96 | +------------------------------------------------+EVENT TIME: 16:50[PDT]| |NRC NOTIFIED BY: PIERCE |LAST UPDATE DATE: 04/12/96 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SIX OF TEN MAIN STEAM SAFETY VALVE LIFT SETPOINTS WERE FOUND OUT OF | | TOLERANCE. | | | | WHILE REVIEWING THE RESULTS OF AUGMENTED TESTING OF UNIT 1 MAIN STEAM | | SAFETY VALVES, THE LICENSEE DETERMINED THAT SIX OF THE TEN VALVES WHICH | | WERE TESTED HAD AS-FOUND LIFT SETPOINTS THAT EXCEEDED THE TECHNICAL | | SPECIFICATION SETPOINT TOLERANCE OF ñ3%. PRELIMINARY ANALYSIS OF THIS DATA | | INDICATES THAT THIS CONSTITUTES A CONDITION OUTSIDE THE DESIGN BASIS OF THE | | PLANT. THE AUGMENTED TESTING WAS BEING PERFORMED IN ACCORDANCE WITH | | AGREEMENTS REACHED WITH THE NRC TO ADDRESS PRIOR SETPOINT DRIFT CONCERNS. | | THE LICENSEE PLANS TO TEST THE REMAINING TEN MAIN STEAM SAFETY VALVES ON | | UNIT 1. THE LICENSEE REPORTED THAT THESE SAFETY VALVES ARE DRESSER MODEL | | #3707R. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30284 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/13/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 20:25 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 04/13/96 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: BAUDHAUER |LAST UPDATE DATE: 04/13/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY-RELATED BATTERY CHARGERS MAY NOT BE QUALIFIED FOR ALL INPUT VOLTAGES | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THIS REPORT IS FOR SUSPECTED OPERATION OUTSIDE OF THE DESIGN BASIS. | | SAFETY-RELATED BATTERY CHARGERS USED AT CRYSTAL RIVER UNIT 3 ARE REQUIRED | | TO OPERATE WITHIN A SPECIFIED RANGE OF AC INPUT VOLTAGE. THE VENDOR | | PREVIOUSLY CERTIFIED THE BATTERY CHARGERS AS QUALIFIED TO OPERATE WITHIN | | THE REQUIRED VALUES. ON 04/11/96, THE VENDOR STATED IN WRITING THAT THE | | BATTERY CHARGERS WERE NOT ACTUALLY TESTED TO THE CRYSTAL RIVER UNIT 3 | | REQUIRED VALUES AND, THEREFORE, REQUIRE ADDITIONAL TESTING TO ASSURE THE | | BATTERY CHARGERS WILL MEET DESIGN REQUIREMENTS." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30285 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/14/96 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 09:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/14/96 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: CLAYTON CHA |LAST UPDATE DATE: 04/14/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN HANNON, NRR EO | | |JIM MUSE FEMA | | |RICH BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNUSUAL EVENT DECLARED ON UNIT 2 DUE TO 2 OF 2 EDGs BEING INOPERABLE - | | | | UNIT 1 IS AT 100% POWER WITH 2 OF 2 EDGs OPERABLE. UNIT 2 IS IN MODE 6 IN | | A REFUELING OUTAGE WITH THE ENTIRE CORE OFFLOADED INTO THE SPENT FUEL POOL. | | THE UNIT 2 'CD' EDG (1 OF 2 EDGs) IS INOPERABLE FOR MAINTENANCE ACTIVITIES. | | | | AT 1000, THE LICENSEE DECLARED THE SECOND OF 2 UNIT 2 EDGs ('AB') | | INOPERABLE FOR MAINTENANCE ACTIVITIES AND DECLARED AN UNUSUAL EVENT ON | | UNIT 2 IN ACCORDANCE WITH THE EMERGENCY PLAN DUE TO 2 OF 2 UNIT 2 EDGs | | BEING INOPERABLE WITH UNIT 2 IN MODE 6 WITH THE CORE DEFUELED. | | | | THERE IS NO UNIT 2 TECH SPEC LCO ACTION STATEMENT APPLICABLE TO 2 OF 2 EDGs | | BEING INOPERABLE WITH UNIT 2 IN MODE 6 WITH THE CORE DEFUELED. | | | | THE LICENSEE DECLARED THE UNIT 2 'AB' EDG INOPERABLE WHILE THE UNIT 2 'CD' | | EDG WAS INOPERABLE SO AS NOT TO EXTEND THE LENGTH OF THE UNIT 2 REFUELING | | OUTAGE BEYOND THE PRESENT SCHEDULED UNIT 2 RESTART DATE OF 05/05/96. | | | | THE NORMAL ELECTRICAL POWER SUPPLY (OFFSITE POWER) FOR BOTH UNITS FOR | | THE SPENT FUEL POOL COOLING SYSTEM IS AVAILABLE, AND THE UNIT 1 BACKUP | | POWER SUPPLY (2 EDGs) FOR THE SPENT FUEL COOLING SYSTEM IS AVAILABLE. | | THE UNIT 2 BACKUP POWER SUPPLY (2 EDGs) FOR THE SPENT FUEL POOL COOLING | | SYSTEM IS INOPERABLE. | | | | THE LICENSEE PLANS TO COMPLETE THE MAINTENANCE ACTIVITIES ON THE "CD' EDG, | | DECLARE IT OPERABLE, AND TERMINATE THE UNUSUAL EVENT WITHIN 2 DAYS. | | | | THE LICENSEE NOTIFIED STATE & LOCAL OFFICIALS & THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30286 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/14/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 16:31 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 04/14/96 | +------------------------------------------------+EVENT TIME: 14:30[EDT]| |NRC NOTIFIED BY: BANDHAUER |LAST UPDATE DATE: 04/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CLOSED CYCLE COOLING WATER PUMP INADVERTENTLY STARTED DURING A TEST. | | | | DURING PERFORMANCE OF A SURVEILLANCE TEST, AN OPERATOR MISSED A STEP IN THE | | PROCEDURE FAILING TO BLOCK THE ACTUATION OF THE '1A' CLOSED CYCLE COOLING | | WATER PUMP. WHEN THE OPERATOR PROCEEDED WITH THE TEST, THE PUMP STARTED | | AND OPERATED PROPERLY. NO COMPONENTS WERE DAMAGED AS A RESULT OF THIS | | EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30287 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/14/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 16:52 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/14/96 | +------------------------------------------------+EVENT TIME: 15:10[EDT]| |NRC NOTIFIED BY: COLEMAN |LAST UPDATE DATE: 04/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |VERRELLI RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HALF SCRAM SIGNAL AND VARIOUS ESF ACTUATIONS DUE TO ELECTRICAL FAULT | | | | WITH THE REACTOR VESSEL FLOODED AND THE HEAD REMOVED FOR FUEL MOVEMENT, THE | | NORMAL SUPPLY TRANSFORMER TO THE 'D' 600-VAC ELECTRICAL BUS TRIPPED DUE TO | | DIFFERENTIAL OVERCURRENT. THE LOSS OF THE 'D' 600-VAC BUS CAUSED A LOSS OF | | POWER TO THE 'B' RPS BUS RESULTING IN A HALF SCRAM SIGNAL, THE CLOSURE OF | | THE RHR SHUTDOWN COOLING SUCTION ISOLATION VALVE (#1-E11-F009), THE | | AUTOMATIC START OF ALL FOUR TRAINS OF THE STANDBY GAS TREATMENT SYSTEM, AND | | A CONTROL ROOM VENTILATION SYSTEM REALIGNMENT. | | | | THE LICENSEE RESTORED POWER TO THE 'D' 600-VAC BUS AT 1525 USING THE | | ALTERNATE POWER SUPPLY, AND THE RHR SHUTDOWN COOLING SYSTEM WAS RESTORED TO | | SERVICE AT 1625. THE SPENT FUEL POOL COOLING SYSTEM AND THE DECAY HEAT | | REMOVAL SYSTEM CONTINUED TO OPERATE THROUGHOUT THE EVENT. NO INCREASE IN | | REACTOR VESSEL WATER TEMPERATURE WAS DETECTED AS A RESULT OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+