U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/25/96 - 09/26/96 ** EVENT NUMBERS ** 30935 30949 30951 31055 31056 31057 31058 31059 31060 31061 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30935 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 08/29/96 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 10:13 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 11/06/95 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR 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 +------------------------------------------------------------------------------+ | A CHECK VALVE IN THE HIGH PRESSURE INJECTION FLOW PATH IS POTENTIALLY | | INOPERABLE | | | | ON NOVEMBER 6, 1995, UNIT 1 WAS IN COLD SHUTDOWN FOR A REFUELING OUTAGE. | | DURING A SYSTEM FLOW TEST, VALVE 1HP-153, A VELAN STOP CHECK VALVE IN A | | HIGH PRESSURE INJECTION EMERGENCY CORE COOLING SYSTEM INJECTION FLOW PATH, | | FAILED TO PASS THE REQUIRED FLOW RATE. THE VALVE WAS INSPECTED, CLEANED, | | POLISHED INTERNALLY, AND SUCCESSFULLY RETESTED PRIOR TO UNIT RESTART. VALVE | | 1HP-153 HAD PREVIOUSLY FAILED A FLOW TEST ON MAY 6, 1995, WHILE UNIT 1 WAS | | AT COLD SHUTDOWN. AT THAT TIME, IT WAS RETESTED WITHOUT MAINTENANCE AND | | ALSO PASSED. | | | | SINCE VALVE 1HP-153 PASSED THE REQUIRED FLOW DURING A SYSTEM TEST ON MAY 6, | | 1995, AND SUBSEQUENTLY FAILED TO PASS THE REQUIRED FLOW DURING A SYSTEM | | TEST ON NOVEMBER 6, 1995, THE POTENTIAL FOR VALVE INOPERABILITY EXISTED | | BETWEEN THESE DATES. IF THIS VALVE WERE INOPERABLE, THEN A SINGLE FAILURE | | OF ANOTHER HIGH PRESSURE INJECTION SYSTEM COMPONENT COULD HAVE PREVENTED | | MITIGATION OF CERTAIN SMALL BREAK LOSS OF COOLANT ACCIDENT SCENARIOS. A | | PAST OPERABILITY EVALUATION IS IN PROGRESS AND IS EXPECTED TO FIND THE | | VALVE OPERABLE. HOWEVER, THE EVALUATION IS BEING PERFORMED BY A VENDOR AND | | HAS NOT BEEN COMPLETED IN THE EXPECTED TIME FRAME. | | | | THIS EVENT IS BEING REPORTED DUE TO THE REASONABLE DOUBT WHICH EXISTS | | REGARDING THE PAST OPERABILITY OF THE VALVE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1040EDT 9/25/96 FROM DAVID NIX TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | "VALVE 1HP-153 IS A CHECK VALVE IN THE HIGH PRESSURE INJECTION (HPI) | | EMERGENCY CORE COOLING SYSTEM INJECTION FLOWPATH. THIS VALVE IS REQUIRED | | TO OPEN AND PASS SUFFICIENT FLOW TO THE REACTOR COOLANT SYSTEM (RCS) DURING | | A DESIGN BASIS ACCIDENT. THE LIMITING ACCIDENT WITH RESPECT TO HPI SYSTEM | | FLOW REQUIREMENTS IS A SMALL BREAK LOSS OF COOLANT ACCIDENT (SBLOCA). IT | | WAS DETERMINED THAT THIS VALVE MAY POTENTIALLY HAVE BEEN INOPERABLE, AS A | | RESULT OF FAILING TO PASS THE REQUIRED FLOW DURING SYSTEM TESTING, AND THAT | | THE HPI SYSTEM MAY NOT HAVE BEEN CAPABLE OF PERFORMING ITS CORE COOLING | | SAFETY FUNCTION. COMPLETION OF THE OPERABILITY EVALUATION WAS DEPENDENT ON | | COMPLETION OF A VENDOR ANALYSIS OF THE APPLICABLE SBLOCA SCENARIOS, | | ASSUMING THE DEGRADED FLOW RESULTING FROM VALVE 1HP-153. AS A RESULT, IT | | WAS DETERMINED THAT THIS CONDITION SHOULD BE CONSERVATIVELY REPORTED UNTIL | | COMPLETION OF THE VENDOR ANALYSIS, AND A REPORT UNDER 10CFR | | 50.72(b)(iii)(D) WAS MADE ON AUGUST 29, 1996, AT 10:13am." | | | | "THE VENDOR ANALYSIS OF THE SBLOCA SCENARIOS HAS NOW BEEN COMPLETED. THIS | | VENDOR ANALYSIS CONCLUDES THAT THE HPI SYSTEM COULD HAVE SATISFACTORILY | | MITIGATED THE SBLOCA SCENARIOS, ASSUMING A HPI SYSTEM COMPONENT SINGLE | | FAILURE, EVEN WITH THE FLOW REDUCTION CAUSED BY VALVE 1HP-153. THEREFORE, | | THIS EVENT DOES NOT MEET THE REPORTING REQUIREMENTS OF 10CFR 50.72 | | (b)(iii)(D)." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO(LESSER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30949 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BICRON |NOTIFICATION DATE: 09/02/96 | | CITY: NEWBURY REGION: 3 |NOTIFICATION TIME: 14:22 [ET]| | COUNTY: STATE: OH |EVENT DATE: 08/02/96 | |LICENSE#: 34-06558-05 AGREEMENT: N |EVENT TIME: 10:15[EDT]| | DOCKET: |LAST UPDATE DATE: 09/25/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN JACOBSON RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JEFF KENNEDY | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BICRON OF NEWBURY, OHIO, REPORTED A LOST 0.012-MICROCURIE AMERICIUM-241 | | SOURCE. | | | | BICRON UTILIZES AMERICIUM-241 SOURCES TO MANUFACTURE SODIUM IODIDE | | DETECTORS WITH A PULSAR UNIT INSIDE TO GIVE A STEADY COUNT RATE. DURING | | THE PERFORMANCE OF THIS PROCESS AT APPROXIMATELY 1015 ON AUGUST 2, 1996, A | | 0.012-MICROCURIE AMERICIUM-241 CAPSULE POPPED OUT OF THE HANDS OF AN | | OPERATOR AND DISAPPEARED. (THE REPORTING LIMIT IS 0.01 MICROCURIES.) IN | | AN EFFORT TO SEARCH FOR THE MISSING CAPSULE, THE LICENSEE COMPLETELY | | DISMANTLED THE SMALL ROOM THAT THE OPERATOR WAS WORKING IN, BUT THE | | 3/8-INCH DIAMETER BY 3/8-INCH LONG SOURCE (DETECTOR UNIT) WAS NOT FOUND. | | THE LICENSEE CURRENTLY BELIEVES THAT THE SOURCE MAY HAVE GOTTEN CAUGHT IN | | THE CUFF OF THE OPERATOR'S LAB COAT WHEN IT FELL FROM THE OPERATOR'S HANDS | | AND THAT IT MAY HAVE SUBSEQUENTLY BEEN LOST FROM THERE. THE LICENSEE DOES | | NOT BELIEVE THAT THERE IS AN EXTERIOR EXPOSURE RISK ASSOCIATED WITH THIS | | EVENT. | | | | THE LICENSEE NOTIFIED NRC REGION 3 (MICHAEL FONZER) LAST WEEK AND PLANS TO | | FOLLOWUP WITH A WRITTEN NOTICE. (REFER TO THE HOO LOG FOR A LICENSEE | | CONTACT ADDRESS AND TELEPHONE NUMBERS.) | | | | * * * UPDATE 1340 9/25/96 FROM KENNEDY TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS RECOVERED THE LOST SOURCE. THE NRC REGION 3 OFFICE HAS | | BEEN CONTACTED BY THE LICENSEE REGARDING THIS EVENT. HOO NOTIFIED R3DO | | (WRIGHT). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30951 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 09/03/96 | |UNIT: [1] [ ] [3] STATE: SC |NOTIFICATION TIME: 12:41 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 09/03/96 | +------------------------------------------------+EVENT TIME: 12:10[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISSED VENT VALVE TESTING RESULTED IN INOPERABILITY OF THE UNIT 1 AND 3 | | BORATED WATER STORAGE TANKS (BWST). | | | | DURING A REVIEW OF THE OCONEE INSERVICE TESTING PROGRAM ON AUGUST 26, 1996, | | IT WAS DISCOVERED THAT THE REQUIRED TESTING FREQUENCY HAD BEEN EXCEEDED FOR | | VALVES 1LP-61 AND 3LP-61, VENT VALVES FOR THE UNIT 1 AND 3 BWSTs. AT THAT | | TIME, THESE VALVES WERE DECLARED INOPERABLE, AND AN EVALUATION OF SYSTEM | | IMPACT WAS UNDERTAKEN. | | | | THE VENT VALVES FOR THE BWSTs ARE REQUIRED TO BE CAPABLE OF OPENING AND | | ADMITTING SUFFICIENT AIR TO MAINTAIN THE PRESSURE IN THE BWSTs ABOVE THE | | DESIGN VACUUM WHEN LIQUID IS REMOVED FROM THE TANKS. THE BWSTs PROVIDE A | | SOURCE OF BORATED WATER FOR THE EMERGENCY CORE COOLING SYSTEMS DURING | | CERTAIN DESIGN BASIS ACCIDENTS. | | | | AT 1210 ON SEPTEMBER 3, 1996, FURTHER ENGINEERING REVIEW REVEALED THAT THE | | INOPERABILITY OF VALVES 1LP-61 AND 3LP-61 RENDERED THE UNIT 1 AND 3 BWSTs | | INOPERABLE. TECHNICAL SPECIFICATION 3.2.2 REQUIRES THE LICENSEE TO RESTORE | | OPERABILITY OF THE BWSTs WITHIN ONE HOUR OR PLACE THE UNITS IN A HOT | | SHUTDOWN CONDITION WITHIN SIX HOURS. | | | | CURRENTLY, EFFORTS ARE IN PROGRESS TO REMOVE VALVES 1LP-61 AND 3LP-61 FROM | | THE BWST VENT PIPING TO RESTORE OPERABILITY OF THE BWST. THE LICENSEE | | PLANS TO PROVIDE ADDITIONAL DETAILS IN A LICENSEE EVENT REPORT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 1040EDT 9/25/96 FROM DAVID NIX TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | "VALVES 1LP-61 AND 3LP-61 ARE VENT VALVES FOR THE UNITS 1 AND 3 BORATED | | WATER STORAGE TANKS (BWST). THESE VALVES ARE REQUIRED TO OPEN AND BREAK | | VACUUM WHEN LIQUID IS DISCHARGED FROM THE TANK. THE BWST PROVIDES A SOURCE | | OF BORATED WATER FOR THE EMERGENCY CORE COOLING SYSTEMS. IT HAD BEEN | | PREVIOUSLY DETERMINED THAT THESE VALVES WERE TECHNICALLY INOPERABLE, AS A | | RESULT OF EXCEEDING THE ALLOWED PERIODICITY FOR AN INSERVICE TESTING | | SURVEILLANCE, AND THAT THEY MAY NOT HAVE BEEN CAPABLE OF PERFORMING THEIR | | SAFETY FUNCTION. ACCORDINGLY, THESE VALVES WERE REMOVED FROM THE SYSTEM TO | | 50.72 (b)(2)(iii)(D) WAS MADE ON SEPTEMBER 3, 1996, AT 12:41pm." | | | | "SUBSEQUENT TESTING HAS DETERMINED THAT VALVES 1LP-61 AND 3LP-61 COULD HAVE | | PERFORMED THEIR SAFETY FUNCTION OF OPENING AND ADMITTING SUFFICIENT AIR TO | | MAINTAIN THE PRESSURE OF THE BORATED WATER STORAGE TANK. THEREFORE, THIS | | EVENT DOES NOT MEET THE REPORTING REQUIREMENTS OF 10 CFR 50.72 (b)(iii)(D). | | HOWEVER, THIS EVENT WILL BE REPORTED BY LICENSEE EVENT REPORT UNDER 10CFR | | 50.73(a)(2)(i)(B)." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED R2DO(LESSER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 09/25/96 | |UNIT: [ ] [ ] [3] STATE: CA |NOTIFICATION TIME: 00:17 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 09/24/96 | +------------------------------------------------+EVENT TIME: 20:35[PDT]| |NRC NOTIFIED BY: POWERS |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 HOT STANDBY | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAS STARTED COOLDOWN TO MODE 5 IN ORDER TO REPAIR AN RTD | | THERMOWELL AS REQUIRED BY TS 3.4.1.3 DUE TO PRESSURE BOUNDARY LEAKAGE. | | | | AT 21:01 ON 9/23/96 A UNIT SHUTDOWN WAS INITIATED TO PERFORM AN RCS | | INSPECTION BASED UPON AN INCREASING TREND IN RCS LEAKAGE. AT 03:59 ON 9/24, | | THE UNIT WAS MANUALLY TRIPPED AT 15% POWER. IT WAS THEN DETERMINED AFTER | | THE INSPECTION THAT THE RCS LEAK DEVELOPED FROM A SPARE RCS RTD THERMOWELL | | LOCATED ON THE DISCHARGE PIPING OF REACTOR COOLANT PUMP 3P004. THE LICENSEE | | IS REPORTING THE EVENT AT THIS TIME SINCE THEY ARE SHUTTING THE REACTOR | | DOWN TO MODE 5 TO MAKE REPAIRS. WHILE SHUTTING DOWN, THEY ALSO HAD A | | FAILURE WITH THE NUMBER 1 STARTUP CHANNEL DUE TO A LOOSE CARD, BUT IT HAS | | BEEN RETURNED TO SERVICE. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31056 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 09/25/96 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 04:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/25/96 | +------------------------------------------------+EVENT TIME: 00:43[PDT]| |NRC NOTIFIED BY: ANDERSON |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED AN UNACCOUNTED FOR SECURITY WEAPON. IMMEDIATE | | COMPENSATORY MEASURES TAKEN ON DISCOVERY. THE RI WILL BE NOTIFIED. SEE HOO | | LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31057 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/25/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 14:48 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/25/96 | +------------------------------------------------+EVENT TIME: 11:04[EDT]| |NRC NOTIFIED BY: GREGORY F. RUPPERT |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLIFF ANDERSON RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM INOPERABLE DUE TO LOOSE SPEED SENSOR CONNECTION | | | | UNIT 1 HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM WAS STARTED FROM THE | | MAIN CONTROL ROOM FOR A "HPCI PUMP VALVE AND FLOW" TEST. THERE WAS NO | | SPEED INDICATION, HOWEVER ALL OTHER RESPONSES WERE AS EXPECTED. THE HPCI | | SYSTEM WAS SECURED AND DECLARED INOPERABLE. INVESTIGATION REVEALED A LOOSE | | SPEED SENSOR CONNECTION. REPAIRS ARE IN PROGRESS AND ARE EXPECTED TO BE | | COMPLETED WITHIN 24 HOURS. AN INOPERABLE HPCI SYSTEM PUTS THE PLANT IN A | | 14 DAY LCO. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31058 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 09/25/96 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 09/25/96 | +------------------------------------------------+EVENT TIME: 14:18[EDT]| |NRC NOTIFIED BY: TREPANIER |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANDERSON 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF SHUTDOWN COOLING FOR 40 MINUTES DUE TO INVALID REACTOR VESSEL HIGH | | PRESSURE SIGNAL. | | | | AT 1418, OPERATORS OBSERVED A SHUTDOWN COOLING HIGH PRESSURE ALARM AND A | | PCIS GROUP 3 (RHR SHUTDOWN COOLING) ISOLATION. SHUTDOWN COOLING SUCTION | | VALVES MO-1001-47 AND 50 AND THE INBOARD RHR INJECTION VALVE MO-1001-29A | | ISOLATED, AND THE TWO RUNNING RHR PUMPS TRIPPED, AS EXPECTED. RCS | | TEMPERATURE INCREASED FROM 99øF TO 111øF DURING THIS EVENT. | | | | THE LICENSEE REPORTED THAT I & C TECHNICIANS WERE BACKFILLING A REACTOR | | VESSEL INSTRUMENTATION REFERENCE LEG AT THE TIME OF THE EVENT, AND SOMEHOW | | PRESSURIZED THE TRANSMITTER FOR THE SHUTDOWN COOLING HIGH PRESSURE | | ISOLATION LOGIC (THE ISOLATION SETPOINT IS 70 PSIG). THE LICENSEE RESTORED | | THE INSTRUMENT RACK TO ITS NORMAL CONFIGURATION, AND RESET THE ISOLATION | | SIGNAL. SHUTDOWN COOLING WAS REESTABLISHED AT 1458. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 09/25/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/25/96 | +------------------------------------------------+EVENT TIME: 14:50[CDT]| |NRC NOTIFIED BY: VOLKER |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE DUE TO OIL LEAK | | | | DURING PERFORMANCE OF THE MONTHLY HPCI OPERABILITY TEST, THE LICENSEE | | DISCOVERED AN OIL LEAK FROM THE HPCI TURBINE STOP VALVE (HPCI-HOV-HOV10). | | THE LICENSEE DETERMINED THAT THIS OIL LEAK WOULD PROHIBIT EXTENDED | | OPERATION OF THE HPCI TURBINE, AND DECLARED THE HPCI SYSTEM INOPERABLE. ALL | | OTHER ECCS SYSTEMS ARE OPERABLE AT THIS TIME, AND THE LICENSEE IS CURRENTLY | | VERIFYING THE OPERABILITY OF THE AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) | | LOGIC. THE INOPERABILITY OF THE HPCI SYSTEM PLACES THE UNIT IN A SEVEN-DAY | | LIMITING CONDITION FOR OPERATION IN ACCORDANCE WITH TECHNICAL SPECIFICATION | | 3.5.C.2. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31060 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 09/25/96 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 17:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/25/96 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: BARGERON |LAST UPDATE DATE: 09/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SHYMLOCK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRESSURIZER CODE SAFETY VALVES FOUND OUT OF TOLERANCE | | | | ON SEPTEMBER 22, 1996, THE LICENSEE RECIEVED THE INITIAL AS-FOUND LIFT | | SETPOINT TEST RESULTS FOR THE THREE PRESSURIZER CODE SAFETY VALVES. THESE | | VALVES HAD BEEN SHIPPED TO WYLE LABS FOR TESTING AND ADJUSTMENT. THE | | RESULTS INDICATED THAT ALL THREE VALVES HAD AS-FOUND LIFT SETPOINTS IN | | EXCESS OF THE 2485 PSIG + 1% TOLERANCE. THE HIGHEST AS-FOUND SETTING WAS | | 3.2% ABOVE THE SETPOINT. ALL VALVES WILL BE RESET TO WITHIN TOLERANCE | | BEFORE BEING REINSTALLED. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY | | THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31061 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/26/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 04:16 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/26/96 | +------------------------------------------------+EVENT TIME: 01:55[CDT]| |NRC NOTIFIED BY: MATTSON |LAST UPDATE DATE: 09/26/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 7 DAY LCO ACTION STATEMENT WHEN HPCI WAS DECLARED | | INOPERABLE. | | | | HPCI WAS DECLARED INOPERABLE WHEN THE HPCI PUMP DISCHARGE TEMPERATURE | | EXCEEDED 150øF. THE CAUSE OF THIS INCREASE IS BEING INVESTIGATED. ALL OTHER | | ECCS EQUIPMENT WAS OPERABLE. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+