U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/25/96 - 04/26/96 ** EVENT NUMBERS ** 30339 30358 30359 30360 30361 30362 30363 30364 30365 30366 30367 30368 30369 30370 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30339 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/22/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 22:59 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/22/96 | +------------------------------------------------+EVENT TIME: 19:14[EDT]| |NRC NOTIFIED BY: RAY LEIB |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CASTO 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 +------------------------------------------------------------------------------+ | POTENTIAL UNANALYZED CONDITION WHILE PERFORMING BLACKOUT TESTING | | | | AS PART OF BLACKOUT TESTING (PROCEDURE SI-126), THE LICENSEE PLACED THE | | '2AA' 6.9-kV SHUTDOWN BOARD ONTO ITS ALTERNATE FEEDER BREAKER, WHICH IS FED | | BY THE 'A' COMMON STATION TRANSFORMER AND WHICH WAS ALSO FEEDING THE '1BB' | | AND '2BB' 6.9-kV SHUTDOWN BOARDS. THE 'A' STATION TRANSFORMER IS DESIGNED | | TO BE LOADED WITH A MAXIMUM OF TWO SHUTDOWN BOARDS. IN ADDITION, THE '2AA' | | EMERGENCY DIESEL GENERATOR (EDG) WAS PLACED IN TEST MODE AS PART OF THE | | TEST PROCEDURE AND WAS, THEREFORE, UNAVAILABLE. THE LICENSEE STATED THAT | | THE '2AA' SHUTDOWN BOARD WAS LOADED ONTO THE ALTERNATE POWER SUPPLY FOR | | APPROXIMATELY TWO MINUTES DURING THE PERFORMANCE OF THE BLACKOUT TESTING. | | | | AT 2222, THE LICENSEE DETERMINED THAT THE ELECTRICAL CONFIGURATION DURING | | THE TEST MAY HAVE RESULTED IN THE INOPERABILITY OF TWO OFFSITE POWER | | SUPPLIES TO CLASS-1E ELECTRICAL DISTRIBUTION SYSTEMS. THIS CONDITION, WHEN | | COMBINED WITH AN INOPERABLE EDG, WOULD HAVE REQUIRED THAT THE UNIT ENTER | | TECHNICAL SPECIFICATION ACTION STATEMENT 3.0.3. THE LICENSEE STATED THAT | | THIS TEST HAS BEEN PERFORMED IN THE PAST AND THAT THIS ISSUE HAS ONLY BEEN | | RECENTLY DISCOVERED. THE LICENSEE CONTINUES TO EVALUATE THE ISSUE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE ON 4/25/96 AT 1415 EDT FROM MEADE TAKEN BY KARSCH * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. UPON FURTHER EVALUATION, THE | | LICENSEE DETERMINED THAT ENTRY INTO TECH SPEC 3.0.3 WAS NOT NECESSARY. | | THE 3 SHUTDOWN BOARDS FED BY TRANSFORMER "A" WOULD NOT HAVE OVERLOADED THE | | TRANSFORMER AS ORIGINALLY THOUGHT. IN ADDITION TO THE 3 SHUTDOWN BOARDS | | FED BY TRANSFORMER "A", A FOURTH SHUTDOWN BOARD FED BY TRANSFORMER "C" WAS | | ALSO AVAILABLE. THIS SATISFIED THE REQUIREMENT FOR 2 INDEPENDENT OFFSITE | | FEEDS FOR THE 1E ONSITE DISTRIBUTION SYSTEM. ONLY THE MUCH LESS | | RESTRICTIVE TECH SPEC FOR 1 INOPERABLE EDG WAS IN FORCE, WHICH IS NOT | | REPORTABLE. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO | | NOTIFIED R2DO BELISLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30358 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/25/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:38 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/24/96 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: GREG DEAN |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSED REACTOR OPERATOR TESTED POSITIVE FOR A CONTROLLED SUBSTANCE. | | THE INDIVIDUAL WAS NOT PERFORMING PLANT OPERATIONS AT THE TIME HE TESTED | | POSITIVE. DUE TO CONCERNS ABOUT HIS BEHAVIOR, HIS SITE ACCESS HAD BEEN | | TERMINATED ON 3/26/96 PENDING THE TEST RESULTS. FURTHER ACTION BY THE | | LICENSEE IS PENDING. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30359 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 13:57 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 13:45[EDT]| |NRC NOTIFIED BY: BOB DELANEY |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BOB DENNIG, NRR EO | |ACHE 50.72(b)(1)(vi) CHEM HAZ(TOX GAS REL) |SULLIVAN FEMA | |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 93 POWER OPERATION | 93 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNUSUAL EVENT DECLARED DUE TO INVALID CONTROL ROOM TOXIC GAS ALARM - | | | | AT 1357, THE LICENSEE DECLARED AN UNUSUAL EVENT WHEN A TOXIC GAS ALARM WAS | | RECEIVED IN THE COMMON CONTROL ROOM. ONE COMMON CONTROL ROOM TOXIC GAS | | MONITOR INDICATED 50 PPM AMMONIA; THE SECOND MONITOR INDICATED 10 PPM | | AMMONIA; AND THE THIRD MONITOR INDICATED 0 PPM AMMONIA. | | | | CONTROL ROOM OPERATORS MANUALLY ISOLATED THE COMMON CONTROL ROOM HVAC | | SYSTEM AND SHIFTED IT TO THE RECIRC MODE. THE LICENSEE SAMPLED THE CONTROL | | ROOM ATMOSPHERE AND CONTROL ROOM VENTILATION DUCT WORK AND DETERMINED THAT | | NO TOXIC FUMES WERE PRESENT IN THE CONTROL ROOM. | | | | THE LICENSEE CONTACTED THE NEARBY CHEMICAL PLANT TO INQUIRE ABOUT AN | | AMMONIA RELEASE; THE CHEMICAL PLANT REPRESENTATIVE WAS GOING TO CHECK INTO | | IT AND REPORT BACK TO LIMERICK. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE DECLARATION OF THE UNUSUAL EVENT. | | | | AT 1400, CONTROL ROOM OPERATORS SHIFTED THE CONTROL ROOM HVAC SYSTEM BACK | | TO NORMAL MODE AND TERMINATED THE UNUSUAL EVENT. THE LICENSEE WILL NOTIFY | | STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR OF THE TERMINATION | | OF THE UNUSUAL EVENT. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT. THIS EVENT HAD NO | | EFFECT ON OPERATIONS OF UNITS 1 OR 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30360 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 04/25/96 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 14:21 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 08:35[PDT]| |NRC NOTIFIED BY: SHAWN JERROW |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAD AN ESF ACTUATION WHEN THEY LOST POWER TO THE DIVISION 1 | | ISOLATION ACTUATION LOGIC PANEL. | | | | DURING PLANNED MAINTENANCE ON DIVISION 1 INVERTER "IN-3" (NORMAL POWER | | SUPPLY TO SAFETY RELATED POWER PANEL #E-PP-7A-A), A BREAKER FOR A TEMPORARY | | POWER SUPPLY TO E-PP-7A-A WAS INADVERTENTLY OPENED. PANEL #E-PP-7A-A | | SUPPLIES POWER TO RC-1, THE DIVISION 1 ISOLATION ACTUATION LOGIC PANEL. | | DEENERGIZING THIS PANEL RESULTED IN THE FOLLOWING AUTOMATIC ESF ACTUATIONS: | | START OF "WMA-FN-54A" (CONTROL ROOM EMERGENCY VENTILATION SYSTEM), REACTOR | | BUILDING VENTILATION ISOLATION, AND START OF STANDBY GAS TREATMENT SYSTEM. | | THE FOLLOWING CONTAINMENT ISOLATIONS OCCURRED: "CSP-V-1 AND "CEP-V-1A" | | (CONTAINMENT PURGE SUPPLY AND EXHAUST), "RCC-V-5" AND "RCC-V-21" | | (CONTAINMENT COOLING SUPPLY AND RETURN), AND "EDR-V-395" AND "FDR-V-220" | | (REACTOR BUILDING SUMPS DISCHARGE TO RADWASTE). ALL ACTUATIONS OCCURRED AS | | EXPECTED, AND ALL SYSTEMS AND COMPONENTS HAVE BEEN RETURNED TO A NORMAL | | CONFIGURATION FOR CURRENT PLANT CONDITIONS. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30361 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 14:30 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 13:55[EDT]| |NRC NOTIFIED BY: HUMMEL |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL OF THE EMERGENCY SIRENS IN COLUMBIANA COUNTY, OHIO, WERE OUT OF SERVICE | | AS OF 1355. THEY WERE ALL RETURNED TO SERVICE AT 1423. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30362 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/25/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 15:02 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 14:59[EDT]| |NRC NOTIFIED BY: AL OLECHNOWICZ |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SEISMIC CATEGORY II OVER SEISMIC CATEGORY I CONDITION IN REFUELING OUTAGES | | | | THE DESIGNATED LAYDOWN AREA FOR THE MAIN TURBINE LOW PRESSURE EXHAUST HOODS | | IS THE SOUTHEAST CORNER OF THE TURBINE BUILDING DECK. LOCATED BELOW THE | | SOUTHEAST CORNER OF THE TURBINE BUILDING DECK IS THE WEST 480 VOLT | | SWITCHGEAR ROOM. SAFETY RELATED SWITCHGEAR #22E, LOCATED IN THE WEST | | 480 VOLT SWITCHGEAR ROOM, CONTROLS VITAL EQUIPMENT NEEDED FOR RESIDUAL | | HEAT REMOVAL AND THEREFORE, IS REQUIRED FOR THE PLANT SAFE SHUTDOWN | | CONDITION DURING A REFUELING OUTAGE. | | | | DURING THE INITIAL PHASE OF THE DESIGN BASIS CONFIGURATION REVIEW FOR | | UNIT 2, THE LICENSEE DETERMINED THAT THE 195 TON UNIT 2 TURBINE BUILDING | | CRANE COULD LIFT ONE OF THE MAIN TURBINE LOW PRESSURE EXHAUST HOODS | | DIRECTLY ABOVE THE #22E SWITCHGEAR WHICH COULD BE ADVERSELY AFFECTED BY THE | | DROP OF A HEAVY LOAD ON THE SOUTHEAST CORNER OF THE TURBINE BUILDING DECK. | | | | THE LICENSEE HAS DETERMINED THAT HEAVY LOADS WERE LIFTED ABOVE THE | | #22E SWITCHGEAR DURING REFUELING OUTAGES #5 AND POSSIBLY DURING REFUELING | | OUTAGES #4 AND #7. DROPPING OF THIS HEAVY LOAD ONTO SWITCHGEAR #22E COULD | | HAVE RENDERED IT INOPERABLE AND COULD HAVE COMPROMISED THE CAPABILITY FOR | | RESIDUAL HEAT REMOVAL. | | | | ON 12/22/80, THE NRC ISSUED A GENERIC LETTER REQUESTING A REVIEW OF THE | | CONTROLS OF HEAVY LOADS AGAINST THE GUIDELINES OF NUREG 0612, SUPPLEMENTED | | BY GENERIC LETTER #81-07, AND IDENTIFICATION OF CHANGES REQUIRED TO FULLY | | SATISFY THESE GUIDELINES. THE LICENSEE RESPONDED TO THIS NRC GENERIC | | LETTER IN A LICENSEE LETTER DATED 07/20/81. | | | | THE SEISMIC CATEGORY II OVER SEISMIC CATEGORY I CONDITION DESCRIBED ABOVE | | WAS NOT INCLUDED IN THE LICENSEE NUREG 0612 EVALUATIONS OF CONTROLS OF | | HEAVY LEADS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30363 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:46 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 15:25[EDT]| |NRC NOTIFIED BY: WILLIAN SPAHN |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE KELLY RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TOO LOW A VOLTAGE RATING ON FUSES MIGHT NOT ISOLATE A FAULT RENDERING THE | | REACTOR AUTOMATIC DEPRESSURIZATION SYSTEM INOPERABLE. | | | | THE LICENSEE DETERMINED THAT THE FUSES IN DC ELECTRICAL DISTRIBUTION SYSTEM | | TO THE OPERATORS FOR THE SAFETY RELIEF VALVES ARE RATED AT 125 VDC. THIS | | DISTRIBUTION SYSTEM CAN REACH A MAXIMUM VOLTAGE OF 135 VDC. IF THIS | | MAXIMUM VOLTAGE OCCURS IN CONJUNCTION WITH A FAULT IN THE SYSTEM THE FUSES | | MIGHT FAIL TO ISOLATE THAT FAULT. THIS WOULD CAUSE THE MAIN DISTRIBUTION | | CIRCUIT BREAKER TO TRIP. TRIPPING OF THIS CIRCUIT BREAKER RENDERS | | INOPERABLE ALL AUTOMATIC AND MANUAL-REMOTE OPERATION OF THESE VALVES | | ADVERSELY IMPACTING LOW PRESSURE SAFETY INJECTION. | | | | THE LICENSEE PLANS TO UPGRADE THESE FUSES TO A HIGHER VOLTAGE RATING. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL GOVERNMENT | | AGENCIES AS SPECIFIED IN THEIR PROCEDURES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30364 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 16:13 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 13:50[EDT]| |NRC NOTIFIED BY: JIM ROBINSON |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY CORE COOLING SYSTEM ACCUMULATORS CROSS CONNECTED ON EACH PLANT | | | | AT 1350, BASED ON REVIEW OF NUCLEAR ENTRIES AND VENDOR INFORMATION, | | THE LICENSEE DETERMINED THAT A CONDITION EXISTED THAT, ALONE COULD HAVE | | PREVENTED THE FULFILLMENT OF SAFETY FUNCTION OF A SYSTEM NEEDED TO MITIGATE | | THE CONSEQUENCES OF AN ACCIDENT. PROCEDURES ALLOW THE NITROGEN SUPPLY FOR | | THE 4 EMERGENCY CORE COOLING SYSTEM ACCUMULATORS TO BE CROSS CONNECTED ON | | EACH PLANT TO EQUALIZE PRESSURE. THIS EVOLUTION HAS BEEN PERFORMED ON PAST | | OCCASIONS. | | | | UNDER LARGE BREAK LOSS OF COOLANT ACCIDENT CONDITIONS, CROSS CONNECTION OF | | THE NITROGEN SUPPLY FOR THE 4 ACCUMULATORS COULD RESULT IN THE PRESSURE | | FROM 2 CONNECTED ACCUMULATORS BEING BLED OFF THROUGH THE FAULTED REACTOR | | COOLANT SYSTEM LOOP. | | | | THE LICENSEE IS REVISING PLANT PROCEDURES TO ELIMINATE USE OF CROSS | | CONNECTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30365 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 14:50[CDT]| |NRC NOTIFIED BY: MIKE SMITH |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |DTHR 73.71(c) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - | | | | TWO COPIES OF THE SITE'S SECURITY PLAN LOST IN THE US MAIL. SEE HOO LOG | | FOR DETAILS. THE LICENSEE IS INVESTIGATING MITIGATIVE ACTIONS. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30366 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:14 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 15:20[CDT]| |NRC NOTIFIED BY: DAN RAGAN |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARTIN FARBER 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT - | | | | SECURITY KEYS WERE UNACCOUNTED FOR. IMMEDIATE COMPENSATORY ACTIONS WERE | | TAKEN. SEE HOO LOG FOR DETAILS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30367 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:44 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 16:06[CDT]| |NRC NOTIFIED BY: JAN BOSTELMAN |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT OPERATIONS OUTSIDE OF DESIGN BASIS DURING 1995 REFUELING OUTAGE - | | | | THE LICENSEE IS REQUIRED TO ANALYZE RADIOLOGICAL DOSE CONSEQUENCES TO | | CONTROL ROOM OPERATORS AS A RESULT OF UPDATED SAFETY ANALYSIS REVIEW | | (USAR) CHAPTER 14 EVENTS AS SPECIFIED IN 10CFR50, APPENDIX A, CRITERION 19. | | THE INTENT OF THE CRITERION IS TO DEMONSTRATE CONTROL ROOM HABITABILITY. | | | | A DISCREPANCY BETWEEN THE FUEL HANDLING EQUIPMENT OPERATION PROCEDURE | | (#OI-FH-1) AND DESIGN BASIS CONTROL ROOM HABITABILITY RADIOLOGICAL | | CONSEQUENCES CALCULATION ASSUMPTIONS (USAR 14.18) WAS IDENTIFIED IN THE | | CONDITION REPORTING SYSTEM. SPECIFICALLY, CHANGES WHICH WERE MADE TO | | #OI-FH-1 TO REMOVE THE REQUIREMENT FOR HAVING ONE TRAIN OF THE CONTROL | | ROOM FILTRATION SYSTEM IN OPERATION PRIOR TO REFUELING OPERATIONS WERE | | UNSUBSTANTIATED. THE ANALYSIS OF RECORD FOR FUEL HANDLING ACCIDENT | | RADIOLOGICAL RELEASES CREDITS AT LEAST ONE TRAIN OF CONTROL ROOM FILTRATION | | BEING IN OPERATION AND NOT JUST OPERABLE. CONSEQUENTLY, #OI-FH-1 ALLOWED | | OPERATIONS DURING THE SPRING 1995 REFUELING OUTAGE WITH THE SYSTEM BEING | | OPERABLE BUT NOT OPERATING OUTSIDE OF AN ASSUMPTION IN THE DESIGN BASIS | | FOR FUEL HANDLING ACCIDENT RADIOLOGICAL DOSE CONSEQUENCES TO OPERATORS. | | | | TO ASSURE MITIGATION OF RADIOLOGICAL RELEASES IN THE EVENT OF A FUEL | | HANDLING ACCIDENT, A PROCEDURE CHANGE TO #OI-FH-1 WILL BE IMPLEMENTED TO | | REQUIRE THE CONTROL ROOM FILTRATION SYSTEM BE IN EMERGENCY MODE PRIOR TO | | MOVING IRRADIATED FUEL. THE NEXT REFUELING OUTAGE IS SCHEDULED TO BEGIN IN | | 09/96. LONG TERM CORRECTIVE ACTIONS WILL INCLUDE REVISING CONTROL ROOM | | RADIOLOGICAL CONSEQUENCES ANALYSIS AS A RESULT OF FUEL HANDLING ACCIDENTS | | IN CONTAINMENT OR THE AUXILIARY BUILDING. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30368 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 20:07 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 18:25[CDT]| |NRC NOTIFIED BY: JOHN MEYERS |LAST UPDATE DATE: 04/25/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | -SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (MCPR) MAY BE NON-CONSERVATIVE- | | | | GENERAL ELECTRIC, IN A LETTER DATED 4/22/96, INFORMED THE LICENSEE OF A | | NON-CONSERVATISM IN THE SAFETY LIMIT MCPR ANALYSIS. THIS CONCLUSION WAS | | BASED ON UNVERIFIED CALCULATIONS PERFORMED BY GENERAL ELECTRIC. THE SAFETY | | LIMIT MCPR IS NOW CALCULATED BY GE TO BE 1.07 AT THE END-OF-FUEL-CYCLE FOR | | 2 LOOP OPERATION. THE TECHNICAL SPECIFICATION SAFETY LIMIT FOR 2 LOOP | | OPERATION IS 1.06 AT END-OF-FUEL-CYCLE OPERATIONS. THEREFORE, THE EXISTING | | TECHNICAL SPECIFICATION SAFETY LIMIT MCPR MAY BE NONCONSERVATIVE BY 0.01 BY | | END-OF-FUEL-CYCLE. | | | | THE LICENSEE HAS ADMINISTRATIVELY SET THE SAFETY LIMIT MCPR AT 1.07 FOR | | 2 LOOP OPERATION AND 1.08 FOR SINGLE LOOP OPERATION. THE LICENSEE HAS | | INCREASED THE OPERATING MCPR LIMIT BY 0.01 IN THE PROCESS COMPUTER | | CALCULATION FOR MCPR. | | | | GE IDENTIFIED THAT THIS PROBLEM ALSO EXISTS AT RIVER BEND AND HOPE CREEK. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30369 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COGEMA MINING, INC, CASPER, WY |NOTIFICATION DATE: 04/25/96 | | CITY: CASPER REGION: 4 |NOTIFICATION TIME: 17:23 [ET]| | COUNTY: STATE: WY |EVENT DATE: 04/25/96 | |LICENSE#: SUA-1341 AGREEMENT: N |EVENT TIME: 12:00[MDT]| | DOCKET: |LAST UPDATE DATE: 04/25/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN PELLET RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JOHN VASELIN | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -HIGH CHLORIDE & CONDUCTIVITY LEVELS FROM URANIUM MINE WATER MONITOR WELL- | | | | PERIMETER MONITOR WELL #M-2 IS USED TO SAMPLE GROUND WATER IN THE AREA | | AROUND THE OUTSIDE OF THE CLOSED IRIGARAY URANIUM MINE LOCATED 90 MILES | | NORTH EAST OF CASPER, WYOMING. GROUND WATER IS SAMPLED ONCE EVERY TWO | | MONTHS AND ANALYZED FOR CHLORIDES, CONDUCTIVITY, ALKALINITY, pH, URANIUM, | | AND WATER LEVEL. | | | | ON 04/23/96, A TEST OF A WATER SAMPLE FROM WELL #M-2 INDICATED 19.5 PPM FOR | | CHLORIDES (THE LICENSE UPPER LIMIT IS 18.0 PPM FOR CHLORIDES) AND | | 967 MICROMHOS/CM (THE LICENSE UPPER LIMIT IS 685 MICROMHOS/CM). | | | | ON 04/25/96, ANOTHER WATER SAMPLE FROM WELL #M-2 INDICATED 20.6 PPM FOR | | CHLORIDES AND 998 MICROMHOS/CM FOR CONDUCTIVITY. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | | | LICENSEE PLANS TO SUBMIT A WRITTEN REPORT TO THE NRC WITHIN 7 DAYS. | | | | NOTE: SEE HOO LOG FOR LICENSEE TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30370 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 04/26/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 00:45 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 21:07[EDT]| |NRC NOTIFIED BY: JAMES ABRAHAM |LAST UPDATE DATE: 04/26/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEORGE AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP - REACTOR TRIP | | | | WHILE PERFORMING MAINTENANCE ON GENERATOR OUTPUT BREAKER 52-9, PERSONNEL IN | | THE SWITCHYARD REPORTED A FLASH ON THE "A" PHASE OF THE DISCONNECTS OF | | BREAKER 52-7, THE REMAINING OUTPUT BREAKER. EACH BREAKER IS SIZED FOR FULL | | GENERATOR LOAD, BUT BOTH BREAKERS ARE USUALLY IN SERVICE. THE TURBINE | | TRIPPED BECAUSE OF A GENERATOR LOCKOUT AND THEN THE REACTOR TRIPPED AT | | 2107. | | | | ALL RODS FULLY INSERTED AND REACTOR COOLANT PUMPS REMAINED OPERATIONAL. | | SEVERAL BUSSES LOST POWER AT THE TIME OF THE TRIP AND SECONDARY SYSTEM | | EQUIPMENT WAS SECURED DUE TO THE LOSS OF NORMAL SERVICE WATER. THE "A" | | ESSENTIAL SERVICE WATER PUMP STARTED AND SUPPLIED ITS HEADER. A MOMENTARY | | LOSS OF POWER WAS SENSED ON THE "B" SAFETY BUS. THE "B" EDG STARTED AND | | LOADED TO THE BUS AS EXPECTED. THE "A" SAFETY BUS DID NOT LOSE POWER, | | HOWEVER THE "A" EDG WAS FOUND TO BE IN THE "OPERATIONAL MODE" BUT WITH THE | | MAINTENANCE MODE LIGHTS ON. THIS CONDITION IS INDICATIVE OF A CIRCUITRY | | PROBLEM. AUXILIARY FEEDWATER ACTUATED DUE TO LOW LEVEL IN THE STEAM | | GENERATORS AND ALL THREE PUMPS ACTUATED PROPERLY. DECAY HEAT IS BEING | | REMOVED VIA THE STEAM GENERATOR PORVs AS REQUIRED. ISOLATION SIGNALS WERE | | RECEIVED FOR BOTH THE CONTAINMENT AND CONTROL ROOM ISOLATION SYSTEMS, | | PROBABLY DUE TO THE LOSS OF POWER TO ASSOCIATED RADIATION MONITORS. THERE | | WAS NO SAFETY INJECTION SIGNAL, HOWEVER AT 2152 IT WAS NOTICED THAT THE | | RWST SUCTION VALVES TO THE CHARGING SAFETY INJECTION PUMPS WERE OPEN. THE | | VCT OUTLET VALVES WERE REOPENED AND THE RWST VALVES WERE SHUT. RWST LEVEL | | HAD DROPPED TO 94% ON THE LOWEST INDICATION WHICH IS GREATER THAT THE | | TECHNICAL SPECIFICATION REQUIRED MINIMUM OF 92%. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | +------------------------------------------------------------------------------+