U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/22/96 - 11/25/96 ** EVENT NUMBERS ** 31369 31370 31371 31372 31373 31374 31375 31376 31377 +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31369 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF CINCINNATI |NOTIFICATION DATE: 11/22/96 | | CITY: CINCINNATI REGION: 3 |NOTIFICATION TIME: 10:27 [ET]| | COUNTY: HAMILTON STATE: OH |EVENT DATE: 11/21/96 | |LICENSE#: 34-06903-05 AGREEMENT: N |EVENT TIME: 02:30[EST]| | DOCKET: |LAST UPDATE DATE: 11/22/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MADERA RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: V. MORRIS | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL MISADMINISTRATION | | | | A PATIENT WAS GIVEN A 48.1 mCi DOSE OF I-131 IN SOLUTION TO BE TAKEN ORALLY | | THROUGH A STRAW. THE PATIENT BEGAN INGESTING THE SOLUTION, THEN BLEW BACK | | THROUGH THE STRAW, CAUSING A PORTION OF THE SOLUTION TO BE SPLASHED UPON | | HER FACE, CLOTHING, AND BEDDING. THE LICENSEE ESTIMATES THAT THE PATIENT | | INJESTED APPROXIMATELY 38 mCi OF THE SOLUTION. THE ATTENDING PHYSICIAN HAS | | DETERMINED THAT THE DOSE INJESTED IS SUFFICIENT TO PERFORM THE INTENDED | | ACTION, SO NO ADDITIONAL DOSAGE WILL BE GIVEN. | | | | THE LICENSEE HAS ALREADY CONTACTED NRC REGION 3 (MADERA) REGARDING THIS | | EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31370 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/22/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:42 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/22/96 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: C. TABONE |LAST UPDATE DATE: 11/22/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RULAND 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE REMOVED CHECK VALVES FROM EMERGENCY DIESEL GENERATOR AIR START | | RECEIVERS | | | | THE LICENSEE DISCOVERED THAT CHECK VALVES HAD BEEN REMOVED FROM THE | | EMERGENCY DIESEL GENERATOR AIR START SYSTEM, CONTRARY TO THE SYSTEM | | DESCRIPTION IN THE FSAR. THE LICENSEE STATED THAT THESE VALVES MAY HAVE | | BEEN REMOVED AS PART OF A DESIGN MODIFICATION, BUT THAT DOCUMENTATION WAS | | POOR. THE CHECK VALVES HAVE BEEN REINSTALLED. | | | | THE LICENSEE ORIGINALLY DISCOVERED THIS CONDITION IN APRIL OF 1996. WHILE | | WORKING ON AN UNRELATED LER, THE LICENSEE NOTICED THAT THIS CONDITION HAD | | NOT BEEN REPORTED TO THE NRC. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED | | BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31371 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/22/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:05 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/25/96 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: JAMES PESCHEL |LAST UPDATE DATE: 11/22/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE IS MAKING A PART 21 NOTIFICATION. | | | | "IN ACCORDANCE WITH 10 CFR 21.21(d)(3)(i), NORTHEAST NUCLEAR ENERGY COMPANY | | (NNECO) IS PROVIDING NOTIFICATION TO THE NRC VIA THIS FACSIMILE AND | | CONCURRENT TELEPHONE CONVERSATION, REGARDING A POTENTIAL SIGNIFICANT SAFETY | | HAZARD (SSH) IDENTIFIED AT MILLSTONE STATION. | | | | "FIFTEEN DIFFERENT FUSE TYPES FROM THREE DIFFERENT MANUFACTURERS | | (GOULD-SHAWMUT, BUSSMAN, AND CEFCO) WERE FOUND TO HAVE AXIAL CRACKS. THE | | CRACKS OCCURRED AS A RESULT OF THE BRASS FERRULE RELIEVING INTERNAL STRESS. | | | | "DURING COMMUNICATIONS WITH MANUFACTURERS, IT WAS DETERMINED THAT THESE | | DEFECTS HAVE BEEN PRESENT WITHIN THE FUSE INDUSTRY FOR MANY YEARS AND THAT | | FUSES MANUFACTURED WITH BRASS ARE SUSCEPTIBLE TO THIS DEFECT. | | | | "NNECO DETERMINED THAT FUNCTIONAL TESTING SHOULD BE PERFORMED ON A SAMPLE | | OF THE FUSES. THE RESULTS FROM THE TESTING INDICATED THAT THE FUSES MET | | THEIR INTENDED FUNCTION OF INTERRUPTING THE CURRENT, HOWEVER TEN OUT OF | | FORTY SIX FUSES HAD FERRULES PHYSICALLY BLOW OFF THE END. THE FOLLOWING IS | | A LIST OF THOSE FUSES THAT THE FERRULE(S) CAME OFF THE END: | | | | GOULD-SHAWMUT | | | | A6Y2 TYPE II, 10KA IR | | A6Y5, 200KA IR | | TRM25, 10KA IR | | A4J10, 200KA IR (2) | | | | BUSSMAN | | | | FRN12, 200KA IR | | FRN-R25, 200KA IR | | FRN-R30, 200KA IR | | FRN-R35, 200KA IR | | FRN-R60, 200KA IR" | | | | "CONCLUSION: | | | | THE CRACKS COULD RESULT IN A LOSS OF SAFETY-RELATED EQUIPMENT DUE TO THE | | FERRULE COMING OFF OF THE FUSE, WHICH COULD THEN SHORT OUT OR DAMAGE OTHER | | SAFETY-RELATED ELECTRICAL DISTRIBUTION. THIS COULD BE A SSH CONCERN THAT | | SHOULD BE REPORTED THROUGH 10CFR21, WITH NOTIFICATION TO OTHER UTILITIES | | DUE TO THE GENERIC NATURE OF THE BASIC COMPONENT. | | | | "IN ACCORDANCE WITH 10CFR 21.21(d)(3)(ii), A WRITTEN REPORT WILL BE | | PROVIDED WITHIN 30 DAYS." | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31372 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 11/22/96 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 16:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/22/96 | +------------------------------------------------+EVENT TIME: 11:47[PST]| |NRC NOTIFIED BY: JIM NORTHNESS |LAST UPDATE DATE: 11/22/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A UNIT TRIP (MAIN GENERATOR LOCKOUT) FOLLOWING A FIRE IN | | AN AUXILIARY POWER GROUNDING TRANSFORMER. | | | | AT 1147 PST, A DIFFERENTIAL PRESSURE TRIP OCCURRED ON AUXILIARY TRANSFORMER | | #1-1 WHICH IN TURN INITIATED A MAIN UNIT TRIP. THE UNIT TRIP CAUSED A | | TURBINE TRIP-REACTOR TRIP. A FIRE WAS INITIALLY REPORTED AT THE AUXILIARY | | POWER GROUNDING TRANSFORMER, HOWEVER, THE FIRE WAS EXTINGUISHED WHEN PLANT | | POWER WAS TRANSFERRED TO STARTUP POWER. THE FIRE BRIGADE SEARCHED ALL | | VITAL AND NON-VITAL AREAS AND NO ACTIVE FIRE WAS DISCOVERED. THE COUNTY | | FIRE DEPARTMENT WAS CALLED AT THE OUTSET OF THE FIRE BUT NO ASSISTANCE WAS | | REQUIRED FROM THEM. TWO SYSTEM FAILURES WERE OBSERVED FOLLOWING THE TRIP: | | (1.) CIRCULATING WATER (CW) PUMP 12 FAILED TO RESTART CAUSING A LOSS OF THE | | MAIN CONDENSER (HEAT REMOVAL IS CURRENTLY VIA THE 10% ATMOSPHERIC DUMP | | VALVES - THERE IS NO INDICATION OF ANY PRIMARY-SECONDARY STEAM GENERATOR | | TUBE LEAKAGE) AND (2.) INTERMEDIATE RANGE CHANNEL N-36 HUNG UP HIGH AT | | APPROXIMATELY 7X10(-9) AMPS WHICH REQUIRED OPERATORS TO MANUALLY | | RE-ENERGIZE THE N-36 SOURCE RANGE CHANNEL [SHOULD AUTOMATICALLY RE-ENERGIZE | | AT 1X10(-10) AMPS DECREASING]. ALL CONTROL RODS FULLY INSERTED. NO PRIMARY | | OR SECONDARY RELIEFs OR SAFETIES LIFTED. ALL THREE EMERGENCY DIESEL | | GENERATORS ARE AVAILABLE AND IN STANDBY. THE LICENSEE CONSIDERS THE 500KV | | OFFSITE POWER SYSTEM UNAVAILABLE PENDING THE RESULT OF THE INVESTIGATION. | | THE AUXILIARY POWER GROUNDING TRANSFORMER WHICH IS LOCATED BENEATH THE | | ISOPHASE BUS DUCTS WAS SEVERELY DAMAGED. THE LICENSEE RESTARTED CW PUMP 12 | | IN AN EFFORT TO RESTORE CONDENSER VACUUM. FOLLOWING THE TRIP, BOTH MOTOR | | DRIVEN AND THE TURBINE DRIVEN AUXILIARY FEEDWATER (AFW) PUMPS AUTOSTARTED | | AS EXPECTED. OPERATORS SECURED THE TURBINE DRIVEN AFW PUMP AND ARE | | CONTROLLING STEAM GENERATOR LEVELS USING THE MOTOR DRIVEN AFW PUMPS IN | | MANUAL. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31373 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 11/22/96 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 16:45 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/20/96 | +------------------------------------------------+EVENT TIME: 17:35[EST]| |NRC NOTIFIED BY: STEVE MERRILL |LAST UPDATE DATE: 11/22/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 +------------------------------------------------------------------------------+ | UNIT 1 DISCOVERED A CONDITION WHICH MAY HAVE PREVENTED A MANUAL TRANSFER OF | | A DC POWER SUPPLY FOR THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP. | | | | "AS A RESULT OF A DESIGN BASIS REVIEW, A CONDITION WAS DISCOVERED WHICH MAY | | HAVE PREVENTED A MANUAL TRANSFER OF A DC POWER SUPPLY TO THE TURBINE DRIVEN | | AUXILIARY FEEDWATER PUMP REQUIRED TO MITIGATE CERTAIN DESIGN BASIS EVENTS. | | IT WAS IDENTIFIED THAT AN UNDERVOLTAGE RELEASE MECHANISM ON ONE OF TWO | | MOLDED CASE CIRCUIT BREAKERS CONNECTED IN SERIES IS REQUIRED TO FUNCTION TO | | SEPARATE THE 125VDC SWING BUS FROM A POSTULATED DC BUS FAULT. THE | | UNDERVOLTAGE RELEASE MECHANISMS ON THE DC TIE BREAKERS HAD NOT BEEN TESTED | | FOR AN EXTENDED PERIOD, POSSIBLY SINCE PLANT STARTUP. A TEST WAS PERFORMED | | WHICH CONFIRMED THAT AT LEAST ONE UNDERVOLTAGE DEVICE WAS INOPERABLE. THE | | ROOT CAUSE OF THE FAILURE HAS BEEN ATTRIBUTED TO LACK OF EFFECTIVE | | MAINTENANCE AND SURVEILLANCE OF THE BREAKER. ALTHOUGH TWO BREAKERS WOULD | | BE REQUIRED TO FAIL IN ORDER TO AFFECT THE BUS TRANSFER, THE ROOT CAUSE WAS | | DETERMINED TO BE APPLICABLE TO THE OTHER DC TIE BREAKERS. THE DC BUS | | TRANSFER FUNCTION WAS DECLARED OUT OF SERVICE. TWO OF THE BREAKERS WERE | | REMOVED, MAINTENANCE AND TESTING WAS PERFORMED AND THE BREAKERS WERE | | RETURNED TO SERVICE. THE TRANSFER FUNCTION HAS BEEN RESTORED AND IS | | CURRENTLY IN SERVICE." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31374 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/22/96 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 19:34 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 11/22/96 | +------------------------------------------------+EVENT TIME: 16:05[PST]| |NRC NOTIFIED BY: JOHN HAMMER |LAST UPDATE DATE: 11/22/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED THAT A SPARE BREAKER WAS IN A CONDITION NOT | | ADDRESSED BY THE PLANT SEISMIC ANALYSIS. | | | | "THE SPARE BREAKER IN THE WESTINGHOUSE SAFETY RELATED 4160V SWITCHGEAR | | (E-SM-8) WAS FOUND IN A PHYSICAL POSITION NOT ADDRESSED BY THE SEISMIC | | ANALYSIS (TEST/DISCONNECT POSITION). THE POTENTIAL EXISTS FOR THE | | UNSECURED BREAKER TO IMPACT THE SWITCHGEAR JARRING THE EQUIPMENT, | | PARTICULARLY THE RELAYS, DURING THE SEISMIC EVENT. THE BREAKER WAS | | IMMEDIATELY REMOVED FROM THE CUBICLE AND SECURED ACCORDING TO APPROVED | | PROCEDURES. THE REMAINDER OF THE POTENTIALLY AFFECTED SWITCHGEAR WAS | | WALKED DOWN AND NO OTHERS WERE FOUND OUT OF POSITION." | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31375 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 11/23/96 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 08:54 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 11/23/96 | +------------------------------------------------+EVENT TIME: 08:08[EST]| |NRC NOTIFIED BY: JAMES BARNES |LAST UPDATE DATE: 11/23/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | AT 0808, THE LICENSEE WAS NOTIFIED THAT THEIR NOAA OFFSITE RADIO ANNOUNCING | | SYSTEM IS INOPERABLE. THE SYSTEM IS BEING REPAIRED. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0953 BY JAMES BARNES ENTERED BY DICK JOLLIFFE * * * | | | | AT 0950, THE LICENSEE WAS NOTIFIED THAT THEIR NOAA OFFSITE RADIO ANNOUNCING | | SYSTEM HAS RESTORED TO OPERABLE STATUS. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. THE HOO NOTIFIED R2DO MARK LESSER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31376 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/24/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:42 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/23/96 | +------------------------------------------------+EVENT TIME: 10:00[CST]| |NRC NOTIFIED BY: STEVE SMALLFOOT |LAST UPDATE DATE: 11/24/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | STOLEN SECURITY WEAPON FOUND AT CRIME SCENE OFFSITE. IMMEDIATE | | COMPENSATORY MEASURES TAKEN AFTER NOTIFICATION BY LOCAL LAW ENFORCEMENT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND IS MAKING THIS | | COURTESY CALL BASED ON POTENTIAL MEDIA INTEREST. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31377 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 11/24/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:12 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 11/24/96 | +------------------------------------------------+EVENT TIME: 10:37[CST]| |NRC NOTIFIED BY: MIKE SWEGLE |LAST UPDATE DATE: 11/24/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM | | WAS NOT SUPPLYING THE TECH SPEC REQUIRED AIR FLOW DUE TO INACCURATE | | INSTALLED INSTRUMENTATION. | | | | "TESTING WAS PERFORMED ON THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM AND | | FLOW WAS DETERMINED TO BE 1607 SCFM (REQUIRED FLOW IS 2000 SCFM +/- 10%). | | FLOW WAS ADJUSTED TO 2012 SCFM SATISFYING TECH SPEC 4.8.D.3.c AND COMBINED | | FILTER DIFFERENTIAL PRESSURE WAS VERIFIED < 6 INCHES WATER AT 2012 SCFM | | SATISFYING TS 4.8.D.5.a. THE CONTROL ROOM EMERGENCY FILTRATION IS | | INOPERABLE AT THIS TIME SINCE THE FREON AND DOP TESTS WERE PERFORMED AT < | | 2000 SCFM +/- 10% (TS 4.8.D.3.a). THIS PLACES BOTH UNITS IN A 7 DAY LCO | | PER TECH SPEC 3.8.D ACTION 1.a AS OF 1037 TODAY. ACTIONS ARE CURRENTLY | | BEING IMPLEMENTED TO PERFORM THE FREON AND DOP TESTS LATER TODAY." | | | | THE LICENSEE DISCOVERED THE ABOVE CONDITION DURING AN EVALUATION OF | | INSTALLED INSTRUMENTATION. A TRAVERSING PITOT TUBE WAS USED TO CONFIRM | | THAT FLOW WAS LESS THAN INDICATED ON THE INSTALLED INSTRUMENTATION. A | | REVIEW OF COMPLETED SURVEILLANCE TESTS SHOWED THAT THE INSTALLED | | INSTRUMENTATION HAD BEEN PROPERLY CALIBRATED AT THE REQUIRED FREQUENCY. | | VENTILATION DAMPERS WERE READJUSTED TO INCREASE FLOW. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+