U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/11/96 - 01/16/96 ** EVENT NUMBERS ** 29573 29708 29823 29824 29825 29826 29827 29828 29829 29830 29831 29832 29833 29834 29835 29836 29837 29838 29839 29840 29841 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29573 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/08/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 10:38 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/08/95 | +------------------------------------------------+EVENT TIME: 10:35[EST]| |NRC NOTIFIED BY: DONOVAN |LAST UPDATE DATE: 01/12/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 +------------------------------------------------------------------------------+ | REACTOR BUILDING CLOSED COOLING WATER (RBCCW) SYSTEM FLOW RATE EXCEEDED THE | | DESIGN FLOW RATE THROUGH THE SHUTDOWN COOLING HEAT EXCHANGERS. | | | | RBCCW FLOW TO THE SHUTDOWN COOLING SYSTEM HEAT EXCHANGERS EXCEEDED DESIGN | | FLOW RATE THROUGH THE SHUTDOWN COOLING HEAT EXCHANGERS. DESIGN FLOW RATE | | PER HEAT EXCHANGER IS 1800 gpm. DURING TESTING OF THE FLOW | | INSTRUMENTATION, IT WAS FOUND THAT SHUTDOWN COOLING HEAT EXCHANGER "A" HAD | | A RBCCW FLOW RATE THROUGH IT OF 2500 gpm, AND SHUTDOWN COOLING HEAT | | EXCHANGER "B" HAD A RBCCW FLOW RATE THROUGH IT OF 2700 gpm. THE LICENSEE | | WAS TESTING THE FLOW INSTRUMENTATION TO FIND OUT THE FLOW RATES FOR A | | SUBMITTAL OF A NEW SHUTDOWN COOLING TECHNICAL SPECIFICATION REGARDING SPENT | | FUEL POOL COOLING. IMMEDIATE CORRECTIVE ACTION WAS TO REDUCE THE RBCCW | | FLOW RATE THROUGH EACH HEAT EXCHANGER TO 1800 gpm. LONG-TERM CORRECTIVE | | ACTION WILL BE TO SEE IF ANY DAMAGE WAS DONE TO THE HEAT EXCHANGER TUBES. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THIS EVENT. THE NRC | | RESIDENT INSPECTOR WAS ALSO INFORMED BY THE LICENSEE. | | | | * * * UPDATE ON 1/12/96 AT 0914 EST FROM DON CLEARY TAKEN BY KARSCH * * * | | | | THE LICENSEE'S FSAR DOES NOT SPECIFY A FLOW RATE FOR SHUTDOWN COOLING HEAT | | EXCHANGERS. ANALYSIS DETERMINED THAT THE OBSERVED FLOW RATE WILL NOT CAUSE | | ANY DAMAGE TO THE SYSTEM COMPONENTS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE R1DO (SHANBAKY) | | WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29708 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 12/12/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 20:30 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/12/95 | +------------------------------------------------+EVENT TIME: 19:20[CST]| |NRC NOTIFIED BY: ROYCE BROWN |LAST UPDATE DATE: 01/11/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LINDA HOWELL 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 +------------------------------------------------------------------------------+ | - PLANT SECURITY REPORT - | | | | A CONTRACTOR WAS FOUND TO HAVE A QUESTIONABLE BACKGROUND AFTER BEING | | GRANTED INTERIM UNESCORTED PLANT ACCESS FOR ABOUT TWO MONTHS. CONTRACTOR'S | | PLANT ACCESS HAS BEEN TEMPORARILY DENIED. LICENSEE IS INVESTIGATING THIS | | EVENT. LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. SEE HOO LOG FOR | | DETAILS. | | | | * * * UPDATE ON 1/11/96 AT 1102 EST FROM SCOTT HEAD TAKEN BY KARSCH * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. DISCUSSIONS WITH REGION 4 RESULTED | | IN CLARIFICATION OF THE LICENSEE'S UNDERSTANDING OF THE REGULATIONS. | | FURTHER INVESTIGATION CONCLUDED THAT THIS EVENT REPRESENTS AN ISOLATED | | OCCURRENCE RATHER THAN AN INDICATION OF A PROGRAMMATIC BREAKDOWN. THE ROOT | | CAUSES ARE NOT ASSOCIATED WITH THE PROGRAM ITSELF. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE R4DO (SPITZBERG) WAS | | NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29823 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/11/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:58 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/11/96 | +------------------------------------------------+EVENT TIME: 11:50[EST]| |NRC NOTIFIED BY: RICHARD DONOVAN |LAST UPDATE DATE: 01/11/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THE EMERGENCY DIESEL GENERATOR (EDG) DAY | | TANK'S SEISMIC ANCHORAGE IS INADEQUATE. (ONLY ONE EDG IS AFFECTED, THE GAS | | TURBINE IS NOT AFFECTED). THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | * * * 1220 JANUARY 11, 1996, UPDATE FROM DONOVAN TAKEN BY TROCINE * * * | | | | THE LICENSEE CALLED TO CORRECT THE EVENT CLASSIFICATION FROM A ONE-HOUR | | NON-EMERGENCY REPORT TO A FOUR-HOUR NON-EMERGENCY REPORT BECAUSE THE UNIT | | IS CURRENTLY SHUT DOWN FOR A REFUELING OUTAGE. THE UNIT IS NOT IN ANY | | TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT OF | | THE INADEQUATE EDG DAY TANK SEISMIC ANCHORAGE BECAUSE THERE IS NO FUEL IN | | THE VESSEL. CORRECTIVE ACTIONS ARE STILL BEING DETERMINED. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (SHANBAKY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29824 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 01/11/96 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 16:19 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/11/96 | +------------------------------------------------+EVENT TIME: 12:14[CST]| |NRC NOTIFIED BY: VIC SIMONIS |LAST UPDATE DATE: 01/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TRANSPORT OF A POTENTIALLY CONTAMINATED INJURED WORKER TO AN OFFSITE | | MEDICAL FACILITY | | | | WHILE PERFORMING PRE-SHIPMENT PREPARATION OF A HIGH INTEGRITY CONTAINER, A | | LICENSEE EMPLOYEE FELL APPROXIMATELY SIX FEET FROM SCAFFOLDING. THE | | INDIVIDUAL WAS TRANSPORTED TO MATAGORDA GENERAL HOSPITAL WITH A POTENTIALLY | | BROKEN LEFT LEG AND RIGHT ARM. THE ONSITE EMERGENCY RESPONDENT AND HEALTH | | PHYSICS PERSONNEL DECIDED NOT TO DELAY TRANSPORT TO COMPLETE WHOLE BODY | | FRISKING. (THE BACK OF THE INDIVIDUAL ON THE STRETCHER WAS NOT SURVEYED.) | | THE HOSPITAL WAS NOTIFIED TO RECEIVE A POTENTIALLY CONTAMINATED PATIENT. | | HOWEVER, PRIOR TO ARRIVING AT THE HOSPITAL, THE INDIVIDUAL WAS DETERMINED | | NOT TO BE CONTAMINATED. THE HEALTH PHYSICS TECHNICIAN ON BOARD THE | | AMBULANCE NOTIFIED THE HOSPITAL VIA MOBILE PHONE THAT THE INDIVIDUAL WAS | | NOT CONTAMINATED. THE INJURED MAN IS CURRENTLY UNDER THE CARE OF MATAGORDA | | GENERAL HOSPITAL, AND INITIAL REPORTS FROM THE HOSPITAL INDICATE THAT THE | | INDIVIDUAL'S ARM IS NOT BROKEN. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND IS STILL EVALUATING | | WHETHER OR NOT A PRESS RELEASE WILL BE ISSUED. | | | | * * * UPDATE ON 1/12/96 AT 1110 EST FROM SCOTT HEAD TAKEN BY KARSCH * * * | | | | THE INJURED PERSON DID NOT HAVE ANY BROKEN BONES. THE NRC OPERATIONS | | CENTER NOTIFIED THE R4DO (SPITZBERG). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29825 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: APPLIED RADIANT ENERGY CORPORATION |NOTIFICATION DATE: 01/11/96 | | CITY: LYNCHBURG REGION: 2 |NOTIFICATION TIME: 16:35 [ET]| | COUNTY: STATE: VA |EVENT DATE: 01/10/96 | |LICENSE#: 45-11496-01 AGREEMENT: N |EVENT TIME: 16:45[EST]| | DOCKET: |LAST UPDATE DATE: 01/11/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JACK CRLENJAK RDO | | |MICHAEL WEBER (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JAMES MYRON | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |MAAD 36.83(a)(4) FAILED CABLE/DRIVE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MECHANICAL FAULT IN DRIVE MECHANISM AT APPLIED RADIANT ENERGY CORPORATION | | (AN UNDERWATER, CATEGORY III, GAMMA IRRADIATOR FACILITY LOCATED IN | | LYNCHBURG, VIRGINIA). | | | | THIS UNDERWATER IRRADIATOR FACILITY UTILIZES 25 WESF (WASTE ENCAPSULATED | | STORAGE FACILITY) CAPSULES OF CESIUM-137 WITH A CURRENT ACTIVITY OF 900,000 | | TO 1,000,000 CURIES. IT ALSO UTILIZES APPROXIMATELY 15,000 CURIES OF | | COBALT-60. THE CESIUM-137 MATERIAL IS LOCATED IN A PLAQUE FRAME WHICH | | MOVES LATERALLY UNDERWATER. | | | | AT APPROXIMATELY 1645, ON JANUARY 10, 1996, THE LICENSEE IDENTIFIED A | | FAILURE OF THE DRIVE MECHANISM THAT MOVES THE CESIUM-137 PLAQUE FRAME | | LATERALLY AT THE BOTTOM OF THE POOL. THIS PREVENTED THE FREE LATERAL | | MOVEMENT OF THE PLAQUE FRAME CONTAINING THE CESIUM-137. THE LICENSEE'S | | INVESTIGATION HAS IDENTIFIED THE CAUSE OF THE DRIVE MECHANISM FAILURE TO BE | | A BROKEN BEARING. THE LICENSEE IS CURRENTLY IN THE PROCESS OF OBTAINING A | | NEW BEARING AND REPLACING THE BROKEN ONE. THE IRRADIATOR CANNOT BE USED IN | | PRODUCTION UNTIL THE REPAIRS HAVE BEEN COMPLETED. REPAIRS ARE TENTATIVELY | | SCHEDULED FOR COMPLETION ON JANUARY 15, 1996. | | | | THERE HAS BEEN NO CHANGE IN RADIATION SAFETY AS A RESULT OF THIS EVENT. | | THERE HAS BEEN NO LEAKAGE OR DANGER OF CONTAMINATION, AND THERE HAVE BEEN | | NO INDIVIDUAL OVEREXPOSURES. THE SHIELDING HAS NOT BEEN COMPROMISED. | | | | THE LICENSEE TRIED TO CONTACT THE REGION 2 OFFICE TODAY AND PLANS TO NOTIFY | | THE REGION 2 OFFICE TOMORROW MORNING. REFER TO THE HOO LOG FOR CONTACT | | NAME, ADDRESS, AND TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29826 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 01/11/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 18:28 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 01/11/96 | +------------------------------------------------+EVENT TIME: 16:37[EST]| |NRC NOTIFIED BY: NEUMAN |LAST UPDATE DATE: 01/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT CIRCUITS FOR CONTROLLING EMERGENCY FEEDWATER FLOW TO BOTH | | STEAM GENERATORS PASS THROUGH A COMMON FIRE AREA AND ARE NOT PROTECTED WITH | | ANY FIRE BARRIER PROTECTION IN THAT COMMON AREA | | | | DURING ONGOING APPENDIX-R TSI-MATERIAL RELATED WORK, IT WAS DISCOVERED THAT | | CONDUITS EFS56 AND EFS57 (WHICH CONTAIN CIRCUITS FOR CONTROLLING EMERGENCY | | FEEDWATER FLOW TO BOTH STEAM GENERATORS) PASS THROUGH A COMMON FIRE AREA | | AND ARE NOT PROTECTED WITH ANY FIRE BARRIER PROTECTION IN THAT COMMON AREA. | | THE FIRE BARRIER PROTECTION MATERIAL OUTSIDE THE REACTOR BUILDING (TSI | | MATERIAL) IS CURRENTLY CONSIDERED INOPERABLE, AND THE LICENSEE PLANS TO | | CONTINUE EMERGENCY COMPENSATORY ACTIONS (ROVING FIRE WATCH) UNTIL THE | | TSI-MATERIAL ISSUE IS RESOLVED. THE EMERGENCY FEEDWATER ISSUE WILL BECOME | | PART OF THE OVERALL FIRE SAFETY ISSUE. A SPECIFIC EVALUATION OF THE IMPACT | | OF THIS EMERGENCY FEEDWATER ISSUE ON EMERGENCY FEEDWATER OPERABILITY WILL | | BE COMPLETED PRIOR TO ASCENSION INTO A MODE THAT REQUIRES EMERGENCY | | FEEDWATER OPERABILITY. THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION | | LIMITING CONDITIONS FOR OPERABILITY AT THIS TIME. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29827 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 01/11/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 20:31 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 01/11/96 | +------------------------------------------------+EVENT TIME: 18:20[EST]| |NRC NOTIFIED BY: JOHN A. MERCORIO |LAST UPDATE DATE: 01/11/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INBOARD ISOLATION OF REACTOR CORE ISOLATION COOLING (RCIC) DURING ROUTINE | | SURVEILLANCE TESTING. | | | | AT 1820, A UNIT 1 RCIC INBOARD ISOLATION OCCURRED ON A HIGH STEAM FLOW | | SIGNAL DURING ROUTINE INSTRUMENTATION AND CONTROL SURVEILLANCE TESTING. | | INCORRECT PERFORMANCE OF TESTING ACTIVITIES CAUSED THE ISOLATION SIGNAL. | | THE SYSTEM RESPONDED AS DESIGNED, AND THE ISOLATION WENT TO COMPLETION. | | THIS PLACED THE UNIT IN A 14-DAY TECHNICAL SPECIFICATION LIMITING CONDITION | | FOR OPERATION. | | | | THE INSTRUMENTATION AND CONTROL TESTING WAS STOPPED IMMEDIATELY, AND THE | | RCIC SYSTEM ISOLATION WAS RESET. THE RCIC SYSTEM WAS RETURNED TO ITS | | NORMAL LINEUP AND WAS DECLARED OPERABLE AT 1900. THE TECHNICAL | | SPECIFICATION LIMITING CONDITION FOR OPERATION WAS ALSO EXITED AT THAT | | TIME. ALL OTHER EMERGENCY CORE COOLING SYSTEMS ARE CURRENTLY OPERABLE AND | | AVAILABLE, AND THE RCIC SYSTEM WAS THE ONLY SYSTEM AFFECTED BY THIS | | TRANSIENT. THERE WAS NO RADIOACTIVE RELEASE AS A RESULT OF THIS EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29828 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/12/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 14:53 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/12/96 | +------------------------------------------------+EVENT TIME: 13:10[CST]| |NRC NOTIFIED BY: ED KLUNDT |LAST UPDATE DATE: 01/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE FIRE LOADING IN THE OLD COMPUTER ROOM WAS DISCOVERED TO BE OVER THE | | SAFETY EVALUATION REPORT LIMIT BY A FACTOR OF GREATER THAN 2.5. | | | | IN 1987, A SAFETY EVALUATION REPORT (SER) WAS APPROVED BY THE NRC FOR LACK | | OF SUPPRESSION IN FIRE ZONE 4.0 (THE OLD COMPUTER ROOM). THIS SER WAS | | APPROVED BASED UPON LOW FIRE LOADING (21,000 BTU/FTý) ALONG WITH A | | DETECTION SYSTEM AND FIRE BARRIERS ADEQUATE FOR THE LOADING. CURRENTLY, | | THE FIRE LOADING IS GREATER THAN 200,000 BTU/FTý, APPROXIMATELY 2.5 TIMES | | GREATER THAN THE SER LOAD LIMIT OF 80,000 BTU/FTý. THEREFORE, THE LICENSEE | | BELIEVES THAT THE UNIT OUTSIDE ITS DESIGN BASIS. AS A COMPENSATORY | | MEASURE, A ONCE-PER-HOUR FIRE WATCH HAS BEEN ESTABLISHED. THE UNIT IS NOT | | IN ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29829 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 01/12/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/12/96 | +------------------------------------------------+EVENT TIME: 14:41[EST]| |NRC NOTIFIED BY: ROGER STIFFLER |LAST UPDATE DATE: 01/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 83 POWER OPERATION | 83 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A ONE GALLON PER MINUTE CIRCULATION WATER SYSTEM | | LEAK TO THE GROUND NEXT TO THE COOLING TOWER | | | | AT 1441, THE LICENSEE NOTIFIED THE OHIO ENVIRONMENTAL PROTECTION AGENCY OF | | A CIRCULATION WATER SYSTEM LEAK TO THE GROUND NEXT TO THE COOLING TOWER. | | THE LEAK WAS DISCOVERED AT APPROXIMATELY 2145 ON JANUARY 11, 1996. THE | | CIRCULATION WATER IS LEAKING OUT THROUGH THE SEAL BETWEEN TWO CONCRETE | | BLOCKS, AND IT IS ESTIMATED TO BE LESS THAN ONE GALLON PER MINUTE. THE | | LICENSEE IS MONITORING THE LEAK AND EXPECTS THAT THE LEAK WILL SEAL ITSELF | | WHEN THE WEATHER WARMS UP. IF NOT, THE LICENSEE PLANS TO CAULK THE LEAK. | | | | THE LICENSEE HAS ALSO NOTIFIED THE NRC RESIDENT INSPECTOR | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29830 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/12/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:14 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/12/96 | +------------------------------------------------+EVENT TIME: 19:01[EST]| |NRC NOTIFIED BY: ARCHIE FAULKNER |LAST UPDATE DATE: 01/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF GREATER THAN 10% OF THE 71 EMERGENCY SIRENS DUE TO SNOW PACKING | | | | A SCHEDULED SIREN ACTIVATION TEST WAS CONDUCTED ON JANUARY 10, 1996, WITH | | PRELIMINARY RESULTS INDICATING THAT 6 SIRENS HAD FAILED TO SOUND. THIS | | NUMBER OF FAILURES IS BELOW THE 1-HOUR REPORTING CRITERIA WHICH IS 8 SIREN | | FAILURES (GREATER THAN 10% OF THE 71 SIRENS WITHIN THE 10-MILE EMERGENCY | | PROTECTION ZONE). IN ADDITION TO THE 6 SIRENS THAT HAD FAILED TO SOUND, 5 | | SIRENS INDICATED NO FEEDBACK ON THE ROTATIONAL SENSORS. THIS IS NOT | | CONSIDERED TO BE A SIREN FAILURE UNTIL TECHNICIANS VERIFY THAT IT IS NOT A | | FEEDBACK SENSOR PROBLEM. UPON FIELD INVESTIGATION ON JANUARY 10 AND 11, | | 1996, IT WAS DISCOVERED THAT THERMAL OVERLOADS HAD TRIPPED WHICH RENDERED | | THE 5 ADDITIONAL SIRENS INOPERABLE UNTIL RESET BY THE TECHNICIANS. THIS | | INFORMATION CONFIRMED THAT GREATER THAN 8 SIRENS WERE NOT FUNCTIONAL FOR | | GREATER THAN 1 HOUR. DUE TO THE WEATHER CONDITIONS, ALL SIRENS COULD NOT | | BE SERVICED ON JANUARY 10, 1996. FEEDBACK FROM THE TECHNICIANS INDICATED | | THAT THE SUSPECTED REASON FOR THE OVERLOAD TRIPS WAS DUE TO SNOW PACKING IN | | THE SIREN HORN FROM THE BLIZZARD OF 1996. TECHNICIANS HAVE RESET OVERLOADS | | AND TESTED FAILED SIRENS, AND THE CURRENT STATUS INDICATES THAT A TOTAL OF | | 5 SIRENS ARE STILL NOT FUNCTIONAL. TROUBLESHOOTING AND REPAIRS ARE | | CONTINUING AS WEATHER CONDITIONS ALLOW ACCESS TO THE SIRENS. THIS REPORT | | IS BEING MADE AFTER-THE-FACT BECAUSE SIREN TEST INFORMATION WAS NOT | | INTERPRETED CORRECTLY UNTIL FURTHER DISCUSSIONS WITH THE SIREN TECHNICIANS | | WERE HELD ON JANUARY 12, 1996. THIS IS THE FIRST TIME THAT SNOW PACKING | | HAS BEEN RECOGNIZED AS THE CAUSE FOR SIRENS TO BE NOT FUNCTIONAL. | | | | (ALSO SEE SIMILAR EVENT #29831.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND THE LOWER | | ALLOWAYS CREEK TOWNSHIP. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29831 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 01/12/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 19:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/12/96 | +------------------------------------------------+EVENT TIME: 19:00[EST]| |NRC NOTIFIED BY: JOHN KONOVALCHICK |LAST UPDATE DATE: 01/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 REFUELING | 0 REFUELING | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF GREATER THAN 10% OF THE 71 EMERGENCY SIRENS DUE TO SNOW PACKING | | | | A SCHEDULED SIREN ACTIVATION TEST WAS CONDUCTED ON JANUARY 10, 1996, WITH | | PRELIMINARY RESULTS INDICATING THAT 6 SIRENS HAD FAILED TO SOUND. THIS | | NUMBER OF FAILURES IS BELOW THE 1-HOUR REPORTING CRITERIA WHICH IS 8 SIREN | | FAILURES (GREATER THAN 10% OF THE 71 SIRENS WITHIN THE 10-MILE EMERGENCY | | PROTECTION ZONE). IN ADDITION TO THE 6 SIRENS THAT HAD FAILED TO SOUND, 5 | | SIRENS INDICATED NO FEEDBACK ON THE ROTATIONAL SENSORS. THIS IS NOT | | CONSIDERED TO BE A SIREN FAILURE UNTIL TECHNICIANS VERIFY THAT IT IS NOT A | | FEEDBACK SENSOR PROBLEM. UPON FIELD INVESTIGATION ON JANUARY 10 AND 11, | | 1996, IT WAS DISCOVERED THAT THERMAL OVERLOADS HAD TRIPPED WHICH RENDERED | | THE 5 ADDITIONAL SIRENS INOPERABLE UNTIL RESET BY THE TECHNICIANS. THIS | | INFORMATION CONFIRMED THAT GREATER THAN 8 SIRENS WERE NOT FUNCTIONAL FOR | | GREATER THAN 1 HOUR. DUE TO THE WEATHER CONDITIONS, ALL SIRENS COULD NOT | | BE SERVICED ON JANUARY 10, 1996. FEEDBACK FROM THE TECHNICIANS INDICATED | | THAT THE SUSPECTED REASON FOR THE OVERLOAD TRIPS WAS DUE TO SNOW PACKING IN | | THE SIREN HORN FROM THE BLIZZARD OF 1996. TECHNICIANS HAVE RESET OVERLOADS | | AND TESTED FAILED SIRENS, AND THE CURRENT STATUS INDICATES THAT A TOTAL OF | | 5 SIRENS ARE STILL NOT FUNCTIONAL. TROUBLESHOOTING AND REPAIRS ARE | | CONTINUING AS WEATHER CONDITIONS ALLOW ACCESS TO THE SIRENS. THIS REPORT | | IS BEING MADE AFTER-THE-FACT BECAUSE SIREN TEST INFORMATION WAS NOT | | INTERPRETED CORRECTLY UNTIL FURTHER DISCUSSIONS WITH THE SIREN TECHNICIANS | | WERE HELD ON JANUARY 12, 1996. THIS IS THE FIRST TIME THAT SNOW PACKING | | HAS BEEN RECOGNIZED AS THE CAUSE FOR SIRENS TO BE NOT FUNCTIONAL. | | | | (ALSO SEE SIMILAR EVENT #29830.) | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29832 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 01/13/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 02:24 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 01/13/06 | +------------------------------------------------+EVENT TIME: 01:33[EST]| |NRC NOTIFIED BY: MOFFATT |LAST UPDATE DATE: 01/13/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK 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 +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT SAFETY-RELATED CONTAINMENT MINI-PURGE VALVES | | CLOSING CIRCUITRY IS ROUTED THROUGH A NON SAFETY-RELATED SYSTEM. | | | | DURING AN INVESTIGATION OF A 1995 PROBLEM REPORT CONCERNING THE CONTAINMENT | | PURGE VALVES, A DISCREPANCY WAS NOTED WITH THE CONTAINMENT MINI-PURGE | | VALVES (LRV-70, 71, 72, AND 73). THESE VALVES ARE SAFETY-RELATED AND | | RECEIVE A SIGNAL TO CLOSE ON CERTAIN ENGINEERED SAFETY FEATURES (ESF) | | ACTUATIONS. IT WAS DISCOVERED THAT THE CIRCUITRY TO CLOSE THESE VALVES IS | | ROUTED THROUGH THE CONTAINMENT PURGE DUCT RADIATION MONITOR (RM-A1) CABINET | | WHICH IS NON SAFETY-RELATED. | | | | AN OPEN CIRCUIT IN THE RM-A1 PORTION OF THE CIRCUITRY WOULD NORMALLY CAUSE | | THE VALVES TO CLOSE (i.e. MOVE TO THEIR ESF REQUIRED POSITION). A SHORT | | CIRCUIT IN THE RM-A1 PORTION OF THE CIRCUITRY COULD CAUSE THE VALVES TO | | REMAIN IN THEIR PRIOR POSITION AND WOULD LEAVE THE CAPABILITY OF THE VALVES | | TO CLOSE ON AN ESF ACTUATION INTACT. A "HOT" SHORT IN THE RM-A1 PORTION OF | | THE CIRCUITRY, HOWEVER, COULD CAUSE THE VALVES TO REMAIN OPEN DESPITE AN | | ESF ACTUATION TO CLOSE THE VALVES. BASED ON CIRCUIT DESIGN, THIS | | POSTULATED FAILURE WOULD NOT CAUSE THE VALVES TO OPEN SPURIOUSLY, AND THE | | CONTROL BOARD SWITCH FOR THESE VALVES WOULD NOT BE DISABLED BY THE | | POSTULATED FAILURE. | | | | THE PLANT IS PRESENTLY IN COLD SHUTDOWN, AND THERE ARE NO TECHNICAL | | SPECIFICATION REQUIREMENTS FOR THE CONTAINMENT MINI-PURGE VALVES IN THIS | | MODE. THESE VALVES HAVE BEEN OPENED SEVERAL TIMES WITH THE PLANT IN MODE 1 | | DURING THE LAST FEW YEARS. IF THE POSTULATED FAILURE HAD OCCURRED (i.e. | | THE PLANT IN MODE 1 AND THE CONTAINMENT MINI-PURGE VALVES OPEN WITH A | | COINCIDENT ESF ACTUATION), EXITING THE EMERGENCY OPERATING PROCEDURE WOULD | | HAVE LED THE CONTROL BOARD OPERATOR TO NOTE THE FAILURE AND TO USE THE | | CONTROL SWITCH TO CLOSE THE VALVES. THE LICENSEE IS STILL INVESTIGATING A | | METHOD TO CORRECT THIS CONDITION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29833 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/13/96 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 05:43 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/13/96 | +------------------------------------------------+EVENT TIME: 02:45[CST]| |NRC NOTIFIED BY: WELCH |LAST UPDATE DATE: 01/13/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE WILL NOTIFY THE ILLINOIS ENVIRONMENTAL PROTECTION AGENCY (EPA) | | THAT THE PLANT VIOLATED ITS NPDES PERMIT. | | | | THIS OCCURRED WHEN THE LICENSEE RECEIVED A REPORT OF AN ARCING INSULATOR ON | | THE 138-KV LINE LEADING TO THE STATION COOLING LAKE. A FAILURE OR TRIP OF | | THE TRANSMISSION LINE APPEARED TO BE IMMINENT. THE ONLY WAY TO ISOLATE THE | | LINE IS TO DEENERGIZE THE COOLING LAKE PUMPS, BYPASS THE COOLING LAKE, AND | | DISCHARGE DIRECTLY TO THE DES PLANES RIVER. THIS IS IN VIOLATION OF THE | | STATION'S NPDES PERMIT WHICH PROHIBITS DIRECT OPEN CYCLE AND REQUIRES | | NOTIFICATION OF THE ILLINOIS EPA WITHIN 24 HOURS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29834 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 01/13/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:39 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/13/96 | +------------------------------------------------+EVENT TIME: 15:30[EST]| |NRC NOTIFIED BY: ARCHIE FAULKNER |LAST UPDATE DATE: 01/13/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP |JOHN HANNON (NRR) EO | | | | | |HENRY BAILEY ERB | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL FOULING OF BOTH TRAINS OF THE SAFETY AUXILIARY COOLING SYSTEM | | HEAT EXCHANGERS DUE TO A STRAINER FAILURE | | | | DURING A PLANNED STATION SERVICE WATER LOOP 'A' OUTAGE, THE LICENSEE | | DISCOVERED THAT BOTH LOOP 'A' SAFETY AUXILIARY COOLING SYSTEM HEAT | | EXCHANGERS WERE HEAVILY FOULED WITH GRASS FROM AN APPARENT FAILURE OF THE | | 'C' STATION SERVICE WATER PUMP OUTLET STRAINER. DURING NORMAL OPERATION OF | | THE STATION SERVICE WATER SYSTEM, BOTH THE 'A' AND 'B' LOOPS ARE | | CROSS-TIED, AND THE DEBRIS FLOWING THROUGH THE FAILED STRAINER COULD HAVE | | FOULED THE 'B' STATION SERVICE WATER LOOP SAFETY AUXILIARY COOLING SYSTEM | | HEAT EXCHANGERS WHILE THE CROSS-TIE VALVES WERE OPEN. THE LENGTH OF TIME | | THAT THE 'C' STRAINER WAS FAILED IS UNKNOWN AT THIS TIME. | | | | THE UNIT IS CURRENTLY IN COLD SHUTDOWN, AND THE LICENSEE HAS COMPLETED ITS | | FUEL MOVES. THE REFUELING CAVITY IS FLOODED, AND THE GATES BETWEEN THE | | FUEL POOL AND CAVITY ARE REMOVED. IN THIS MODE OF OPERATION (MODE 5), THE | | UNIT IS REQUIRED TO HAVE ONE OPERABLE SERVICE WATER LOOP. AT THIS TIME, | | THE LICENSEE CONSIDERS THE 'B' SERVICE WATER LOOP TO BE OPERABLE BECAUSE IT | | IS CURRENTLY IN SERVICE (USING A DIFFERENT STRAINER) WITH NORMAL FLOW | | INDICATIONS. THE LICENSEE DOES NOT KNOW THE EXTENT OF THE FOULING IN THE | | 'B' LOOP. THE STATION SERVICE WATER SYSTEM IS A SAFETY-RELATED COOLING | | SYSTEM THAT INDIRECTLY COOLS THE RESIDUAL HEAT REMOVAL SYSTEM. | | | | THE LICENSEE NOTIFIED THE LOWER ALLOWAYS CREEK TOWNSHIP AND PLANS TO NOTIFY | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29835 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/13/96 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 20:14 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/13/96 | +------------------------------------------------+EVENT TIME: 17:15[CST]| |NRC NOTIFIED BY: JIM BOYLE |LAST UPDATE DATE: 01/13/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF RESIDUAL HEAT REMOVAL FOR 19 MINUTES DURING A REFUELING OUTAGE DUE | | TO THE LOSS OF THE NORMAL POWER SUPPLY TO A REACTOR PROTECTION SYSTEM BUS | | | | AT 1715 CST, A LOSS OF THE 'B' 120-VOLT REACTOR PROTECTION SYSTEM (RPS) BUS | | OCCURRED, AND THIS FORCED OPERATORS TO SECURE THE 'B' RESIDUAL HEAT REMOVAL | | (RHR) PUMP WITH THE 'A' RHR TRAIN OUT OF SERVICE FOR MAINTENANCE. PRIOR TO | | THE LOSS OF RPS BUS 'B', THE SHUTDOWN COOLING SYSTEM WAS LINED UP TO THE | | UPPER POOL IN THE FUEL POOL COOLING ASSIST MODE. UPON THE LOSS OF RPS BUS | | 'B', VALVE SSC-MOV-139 (LOCATED IN THE FUEL POOL COOLING ASSIST RETURN | | LINE) RECEIVED AN ISOLATION SIGNAL AND CLOSED, AND FOUR 480-VOLT LOAD SHED | | FEED BREAKERS (EJS-ACB-49, 50, 66, AND 77) OPENED. IN ADDITION, TWO | | CONTAINMENT ISOLATION DRAIN VALVES (DFR-AW-101 AND DER-AOE-126), THREE | | CHILLED WATER VALVES (HVN-MOV-129, 102, AND 130), AND TWO AIR LOCK SUPPLY | | VALVES (JRB-SOV-15 AND 25) CLOSED. REACTOR WATER CLEANUP ALSO ISOLATED. | | ALL SYSTEMS ISOLATED AS DESIGNED WITH THE EXCEPTION OF REACTOR PLANT | | COOLING SYSTEM RETURN ISOLATION VALVE CCP-MOV-144. THIS VALVE ACTUATED BUT | | DID NOT GO FULLY CLOSED. | | | | THE RPS BUS 'B' WAS SUBSEQUENTLY TRANSFERRED FROM ITS NORMAL POWER SUPPLY | | TO AN ALTERNATE POWER SUPPLY, AND THE ISOLATIONS RECEIVED WERE RESET PER | | ABNORMAL OPERATING PROCEDURES. THE TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION FOR LOSS OF RHR COOLING WAS EXITED AFTER 19 MINUTES | | WHEN THE RHR PUMP WAS RESTORED IN THE FUEL POOL COOLING ASSIST MODE AT 1734 | | CST. THERE WAS NO INDICATED CHANGE IN REACTOR COOLANT TEMPERATURE. | | | | THE LICENSEE'S INVESTIGATION OF THE CAUSE OF THE LOSS OF THE NORMAL POWER | | SUPPLY FOR THE 'B' RPS BUS IS CURRENTLY ONGOING. BOTH ELECTRICAL | | PROTECTION ASSEMBLY BREAKERS WHICH PROTECT THE RPS SYSTEM FROM UNDER | | VOLTAGE, OVER CURRENT, OR UNDER FREQUENCY DID TRIP. THERE WERE NO | | MAINTENANCE OR SURVEILLANCE ACTIVITIES OCCURRING ON THE 'B' TRAIN OF RPS AT | | THE TIME OF THE EVENT. THE LICENSEE IS CURRENTLY PERFORMING A MODIFICATION | | TO THE SAME BREAKERS ON THE 'A' TRAIN AND PLANS TO PERFORM THE SAME | | MODIFICATION TO THE 'B' TRAIN BREAKERS DURING THE CURRENT REFUELING OUTAGE. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29836 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/14/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 19:33 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/14/96 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: JIM CROSSMAN |LAST UPDATE DATE: 01/14/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK CRLENJAK RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 +------------------------------------------------------------------------------+ | POTENTIAL FOR THE UNIT 1 SAFEGUARDS FANS TO TAKE A SUCTION FROM THE UNIT 2 | | SAFEGUARDS BUILDING DURING A UNIT 2 CONTAINMENT DEPRESSURIZATION ACTUATION | | AND THEN DISCHARGE TO ATMOSPHERE WITHOUT CHARCOAL FILTER FILTRATION | | | | AT APPROXIMATELY 1700, THE LICENSEE DETERMINED THAT THE UNIT 1 SAFEGUARDS | | VENTILATION DAMPERS DID NOT GO TO THE CLOSED POSITION AFTER REMOVING THE | | SYSTEM FROM THE CHARCOAL FILTERS. BECAUSE UNITS 1 AND 2 ARE TIED TOGETHER | | THROUGH COMMON DUCT WORK AND BECAUSE THEY BOTH INTERFACE AT THE IODINE | | CHARCOAL FILTERS, THE FAILURE OF THE UNIT 1 SAFEGUARDS VENTILATION DAMPERS | | TO CLOSE PROVIDED A POTENTIAL FOR THE UNIT 1 SAFEGUARDS FANS TO TAKE A | | SUCTION FROM THE UNIT 2 SAFEGUARDS BUILDING (DURING A UNIT 2 CONTAINMENT | | DEPRESSURIZATION ACTUATION) AND THEN DISCHARGE TO ATMOSPHERE WITHOUT | | CHARCOAL FILTER FILTRATION. (THE SAFEGUARDS BUILDING HOUSES THE LOW HEAD | | SAFETY INJECTION PUMPS AND THE CONTAINMENT RECIRCULATION SPRAY PUMPS.) THE | | LICENSEE SUSPECTS THAT A CONTROL AIR LEAK ON A SAFEGUARDS DAMPER WAS NOT | | ALLOWING ENOUGH AIR TO THE OTHER SAFEGUARDS DAMPERS ON UNIT 1 TO PERMIT | | PROPER OPERATION. | | | | THIS SYSTEM IS INTENDED TO AUTOMATICALLY ALIGN TO CHARCOAL FILTERS TO LIMIT | | THE RADIATION RELEASE TO THE ENVIRONMENT DURING A CONTAINMENT | | DEPRESSURIZATION ACTUATION WHEN CONTAINMENT SUMP WATER IS BEING PUMPED BY | | THE PUMPS IN THAT ROOM. ACCORDINGLY, TECHNICAL SPECIFICATION 3.7.8.1 | | REQUIRES THE LICENSEE TO HAVE AN OPERABLE CHARCOAL FILTERING SYSTEM | | AVAILABLE FOR EACH TRAIN. PER TECHNICAL SPECIFICATION 3.7.8.1, NO CHARCOAL | | FILTERS WOULD HAVE BEEN OPERABLE ON UNIT 2. THEREFORE, UNIT 2 WAS IN | | TECHNICAL SPECIFICATION 3.0.3 FOR 10 MINUTES UNTIL THE UNIT 1 SYSTEM WAS | | ALIGNED THROUGH THE CHARCOAL FILTERS. THE LICENSEE WILL NOTIFY THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 29837 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CHAMPION TARGET |NOTIFICATION DATE: 01/15/96 | | CITY: RICHMOND REGION: 3 |NOTIFICATION TIME: 09:11 [ET]| | COUNTY: STATE: IN |EVENT DATE: 01/14/96 | |LICENSE#: 13-16598-01 AGREEMENT: N |EVENT TIME: 10:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/15/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM MCCORMICKBARGER RDO | | |MICHAEL WEBER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MCDIVITT | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CHAMPION TARGET REPORTED A SMALL FIRE AT THEIR FACILITY ON 1/14/96. | | | | THE LICENSEE HAD A FIRE AT THEIR FACILITY WHILE NO ONE WAS PRESENT(BETWEEN | | 10:00 - 15:00). THE FIRE INVOLVED A PIECE OF EQUIPMENT WITH A SOURCE HOLDER | | CONTAINING 50 MILLICURIES OF CESIUM 137. THE FIRE WAS DISCOVERED WHEN A | | WORKER RETURNED TO THE SMOKE FILLED FACILITY. THE ACTUAL FIRE WAS NOT | | FOUND, BUT THE FIRE DEPARTMENT WAS CALLED TO THE SITE. THE FIRE EVIDENTLY | | HAD EXTINGUISHED ITSELF. THE LICENSEE DETERMINED THAT THE SOURCE HOLDER | | LEAD SHIELDING HAD MELTED. THEY CALLED THE WAYNE COUNTY EMERGENCY | | MANAGEMENT AGENCY WHO RESPONDED TO MEASURE THE RADIATION AND FOUND THAT | | THEIR DETECTOR MEASURED >0.5 MR/R. THE AREA WAS ROPED OFF. THE LICENSEE | | CONTACTED THE SUPPLIER OF THE SOURCE HOLDER, WHO CONTACTED THE ROSEMONT | | COMPANY TO RESPOND TO THE PROBLEM. ALL PERSONNEL THAT WERE NEAR THE SOURCE | | AT THE TIME OF THE FIRE, WERE NOT CONTAMINATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29838 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 01/15/96 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 11:39 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/15/96 | +------------------------------------------------+EVENT TIME: 09:08[CST]| |NRC NOTIFIED BY: BUSH |LAST UPDATE DATE: 01/15/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG 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 +------------------------------------------------------------------------------+ | FULL BALANCE OF PLANT ISOLATION OCCURRED DUE TO PERSONNEL ERROR. | | | | THIS OCCURRED DURING THE PERFORMANCE OF STP #O584201, 18 MONTH CONTAINMENT | | AND DRYWELL MANUAL ISOLATION ACTUATION LOGIC SYSTEM FUNCTIONAL AND CHANNEL | | FUNCTIONAL TEST. AN I&C TECHNICIAN MISTAKENLY PLACED LOGIC TEST SWITCHES | | IN THE TEST POSITION INSTEAD OF THE NORMAL POSITION. OPERATIONS DEPARTMENT | | PERFORMED ABNORMAL OPERATING PROCEDURE #0003, AUTOMATIC ISOLATIONS. | | THREE BREAKERS TRIPPED, 10 MOVs CHANGED POSITIONS AND 4 DAMPERS CHANGED | | POSITIONS, AS DESIGNED. RHR PUMP "B" WAS IN THE UPPER FUEL POOL COOLING | | ASSIST MODE FOR SHUTDOWN COOLING AND WAS UNAFFECTED. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 29839 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CHILDRENS MERCY HOSPITAL |NOTIFICATION DATE: 01/15/96 | | CITY: KANSAS CITY REGION: 3 |NOTIFICATION TIME: 15:55 [ET]| | COUNTY: STATE: MO |EVENT DATE: 01/15/96 | |LICENSE#: 24-15513-01 AGREEMENT: N |EVENT TIME: 08:00[CST]| | DOCKET: |LAST UPDATE DATE: 01/15/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JIM MCCORMICKBARGER RDO | | |MICHAEL WEBER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: NANCI BURCHELL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 50 æCi Co-57 SPOT MARKER SEALED SOURCE MISSING FROM HOSPITAL - | | | | AT 0800 (CST) ON 01/15/96, LICENSEE DISCOVERED THAT A 3 mm DIAMETER 50 æCi | | Co-57 SPOT MARKER SOURCE SEALED IN A 25 mm DIAMETER X 6 mm THICK CLEAR | | LUCITE DISK WAS MISSING FROM ITS LEAD SHIELD. THE DISK IS NORMALLY STORED | | IN A LOCKED ROOM IN THE NUCLEAR MEDICINE DEPARTMENT AT THE HOSPITAL. | | LICENSEE IS SEARCHING FOR THE MISSING DISK. | | | | THE HOSPITAL RADIATION SAFETY OFFICER HAS BEEN NOTIFIED. | | | | LICENSEE WILL SUBMIT A WRITTEN REPORT TO THE NRC. | | | | NOTE: SEE HOO LOG FOR HOSPITAL TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29840 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/15/96 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 18:33 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/15/96 | +------------------------------------------------+EVENT TIME: 14:30[CST]| |NRC NOTIFIED BY: KEITH POLSON |LAST UPDATE DATE: 01/15/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 4100 POUNDS OF LIQUID SODIUM HYPOCHLORITE LEAKED INTO CIRC WATER SYSTEM - | | | | LICENSEE NOTIFIED THE ILLINOIS EMERGENCY MANAGEMENT AGENCY AND THE DOT | | NATIONAL RESPONSE CENTER THAT 4100 POUNDS OF LIQUID SODIUM HYPOCHLORITE | | HAD LEAKED INTO THE CIRCULATING WATER SYSTEM. THE AMOUNT OF THIS LEAK | | EXCEEDS THE SUPERFUND AMENDMENT AND REAUTHORIZATION ACT LIMITS. | | | | LICENSEE STOPPED THE LEAK AND IS INVESTIGATING THE CAUSE. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29841 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 01/16/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 00:18 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 01/15/96 | +------------------------------------------------+EVENT TIME: 23:50[EST]| |NRC NOTIFIED BY: TURNER |LAST UPDATE DATE: 01/16/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT ONE OF FOUR REACTOR DEPRESSURIZATION SYSTEM | | (RDS) VALVES FAILED TO OPERATE DURING A VALVE TEST. | | | | THE LICENSEE WAS PERFORMING A REFUELING SURVEILLANCE TEST PROCEDURE ON THE | | "B" TRAIN RDS VALVE. THEY DISCOVERED THAT THE 125VDC SOLENOID PILOT VALVE | | FAILED TO OPERATE, WHILE ON THE TEST STAND, WHEN THE SOLENOID WAS | | ENERGIZED. HAD THIS VALVE BEEN CALLED UPON TO OPERATED WHILE THEY WERE AT | | POWER IT MAY NOT HAVE OPERATED. A SECOND RDS VALVE DID OPERATE WHEN TESTED | | AND THE OTHER TWO VALVES HAVE NOT YET BEEN TESTED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+