U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/02/96 - 04/03/96 ** EVENT NUMBERS ** 30217 30218 30219 30220 30221 30222 30223 30224 30225 30226 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30217 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 04/02/96 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 02:58 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 04/01/96 | +------------------------------------------------+EVENT TIME: 22:36[MST]| |NRC NOTIFIED BY: BERT GRABO |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOSS OF SHUTDOWN COOLING FOR 45 SECONDS DUE TO PERSONNEL ERROR - | | | | UNIT 2 IS IN MODE 6 IN THE SIXTH REFUELING OUTAGE WITH THE CORE COMPLETELY | | OFFLOADED TO THE SPENT FUEL POOL WITH THE EXCEPTION OF FUEL ASSEMBLY #A-O7 | | WHICH IS LODGED IN PLACE. | | | | FOLLOWING MAINTENANCE ACTIVITIES, A CONTROL ROOM OPERATOR WAS RESTORING | | POWER TO THE NON-CLASS 1E 4160 VAC BUS #NBN-S02. THE CONTROL ROOM OPERATOR | | CLOSED THE ALTERNATE AC POWER SUPPLY BREAKER (#PBB-HS-SO4L) TO CLASS 1E | | 4160 VAC BUS #PBB-SO4 INSTEAD OF THE NORMAL AC POWER SUPPLY BREAKER | | (#NBN-HS-S02A) TO NON-CLASS 1E 4160 VAC BUS #NBN-S02. THIS CAUSED THE | | NORMAL AC POWER SUPPLY BREAKER (#PBB-HS-S04K) TO CLASS 1E 4160 VAC BUS | | #PBB-S04 TO OPEN SINCE BREAKERS #PBB-HS-SO4K & L ARE INTERLOCKED. THE | | CONTROL SWITCHES FOR BREAKERS #PBB-HS-SO4L AND #NBN-HS-SO2A ARE LOCATED | | ADJACENT TO EACH OTHER, APPROXIMATELY 4 INCHES APART. | | | | AT 2236 (MST), THE CONTROL ROOM OPERATOR REOPENED BREAKER #PBB-HS-S04L | | BASED ON INFORMATION RECEIVED FROM AN AUXILIARY OPERATOR IN THE FIELD. | | THIS DEENERGIZED BUS #PBB-SO4, CAUSING A LOSS OF POWER TO THE CLASS 1E | | 4160 VAC SYSTEM, TRAIN 'B'. THE TRAIN 'A' SYSTEM WAS INOPERABLE FOR | | MAINTENANCE ACTIVITIES DURING THE REFUELING OUTAGE. | | | | THE OPERATING SHUTDOWN COOLING PUMP TRIPPED DUE TO THE LOSS OF POWER TO BUS | | #PBB-S04. THE TRAIN 'B' EDG STARTED AND SUPPLIED 4160 VAC POWER TO BUS | | #PBB-S04. CONTROL ROOM OPERATORS MANUALLY RESTARTED THE SHUTDOWN COOLING | | PUMP APPROXIMATELY 45 SECONDS LATER, AFTER THE 'B' EDG STARTED. | | | | AT 2254 (MST), CONTROL ROOM OPERATORS RESTORED ALL SYSTEMS TO NORMAL. | | THERE WAS NO DETECTABLE REACTOR COOLANT SYSTEM TEMPERATURE INCREASE DURING | | THIS SHORT PERIOD OF TIME SINCE DECAY HEAT FROM THE SOLE FUEL BUNDLE IN THE | | CORE IS MINIMAL. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THIS PERSONNEL ERROR. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30218 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GOOD SAMARITAN HOSPITAL |NOTIFICATION DATE: 04/02/96 | | CITY: CINCINNATI REGION: 3 |NOTIFICATION TIME: 10:04 [ET]| | COUNTY: STATE: OH |EVENT DATE: 12/21/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 12:00[EST]| | DOCKET: |LAST UPDATE DATE: 04/02/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GARY SHEAR RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DR CHARLES McCARTHY, RSO | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PATIENT RECEIVED AN UNDERDOSE OF LIQUID SR-89 DURING A CANCER TREATMENT | | | | ON 12/21/95, A PATIENT WITH PROSTATE CANCER WAS GIVEN AN INTRAVENOUS | | INJECTION OF LIQUID SR-89 AT GOOD SAMARITAN HOSPITAL IN CINCINNATI, OHIO. | | THE PRESCRIBED DOSE WAS 4.9 MILLICURIES OF LIQUID SR-89. HOWEVER, DUE TO A | | LEAK IN THE INTRAVENOUS TUBING, THE PATIENT RECEIVED LESS THAN 4.9 | | MILLICURIES. THE PATIENT AND HIS PHYSICIAN WERE NOTIFIED OF THE UNDERDOSE. | | | | ON 01/09/96, DR CHARLES McCARTHY, RADIATION SAFETY OFFICER, SUBMITTED A | | WRITTEN REPORT OF THIS INCIDENT TO REGION 3 (B. J. HOLT) AS A POTENTIAL | | MEDICAL MISADMINISTRATION EVENT. | | | | AT THE REQUEST OF REGION 3, A TEST EXPERIMENT WAS CONDUCTED TO DETERMINE | | THE ACTUAL DOSE THE PATIENT HAD RECEIVED. | | | | ON 03/27/96, DR McCARTHY RECEIVED THE RESULTS OF THE TEST. THE | | CALCULATIONS ASSOCIATED WITH THE TEST INDICATED THAT THE PATIENT HAD | | RECEIVED A DOSE OF 2.2 MILLICURIES OF LIQUID SR-89. | | | | SEE HOO LOG FOR DR McCARTHY'S TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30219 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/02/96 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 12:20 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/02/96 | +------------------------------------------------+EVENT TIME: 10:00[CST]| |NRC NOTIFIED BY: GEORGE RUITER |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 98 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP/TURBINE TRIP ON POSITIVE FLUX RATE SIGNALS DURING | | NUCLEAR POWER RANGE CHANNEL TESTING DUE TO A POSITIVE RATE RELAY FAILURE | | | | WHILE I&C WAS PERFORMING PROCEDURE SP48-0003F, NUCLEAR POWER RANGE CHANNEL | | 2, N-42, MONTHLY TEST, A REACTOR TRIP OCCURRED WHILE THE FLUX CURRENT WAS | | BEING RAISED FOR N-42 PER THE TEST PROCEDURE. FOLLOWING THE TRIP, ALL | | CONTROL RODS FULLY INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. IN | | ADDITION, AN AUTOMATIC LETDOWN ISOLATION OCCURRED WHEN PRESSURIZER LEVEL | | DECREASED TO LESS THAN 18%, AND AUXILIARY FEEDWATER AUTOMATICALLY STARTED | | AS EXPECTED DUE TO LOW STEAM GENERATOR WATER LEVELS. | | | | THE LICENSEE'S INVESTIGATION DISCOVERED A STUCK OPEN CONTACT ON THE | | POSITIVE RATE RELAY FOR CHANNEL N-41, WHICH HAD BEEN TESTED PRIOR TO | | STARTING THE N-42 TEST. WITH THIS CONDITION, A REACTOR TRIP SIGNAL WAS | | GENERATED WHEN THE N-42 FLUX CURRENT WAS RAISED FOR TESTING RESULTING IN | | TWO OUT OF FOUR POSITIVE RATE TRIP SIGNALS. | | | | THE UNIT IS CURRENTLY IN HOT SHUTDOWN. OPERATORS ARE UTILIZING NORMAL | | CHARGING AND MAKEUP, PRESSURIZER HEATERS AND SPRAYS, AND THE REACTOR | | COOLANT PUMPS FOR PRIMARY INVENTORY, PRESSURE, AND TRANSPORT CONTROL. | | AUXILIARY FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS, AND THE | | CONDENSER IS AVAILABLE AS A HEAT SINK. THE LICENSEE CURRENTLY PLANS TO | | REPLACE THE FAILED RELAY AND TO RESTART THE UNIT LATER TODAY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 30220 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NUCLEAR FUEL SERVICES INC. |NOTIFICATION DATE: 04/02/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 12:52 [ET]| |COMMENTS: HEU CONVERSION & SCRAP RECOVERY |EVENT DATE: 04/02/96 | | NAVAL REACTOR FUEL CYCLE |EVENT TIME: 12:26[EST]| | LEU SCRAP RECOVERY |LAST UPDATE DATE: 04/02/96 | | CITY: ERWIN REGION: 2 +-----------------------------+ | COUNTY: UNICOI STATE: TN |PERSON ORGANIZATION| |LICENSE#: SNM-124 AGREEMENT: Y |BRUNO URYC RDO | | DOCKET: 07000143 |JOHN LINEHAN, NMSS EO | +------------------------------------------------+HOWARD EARL FEMA | |NRC NOTIFIED BY: WAYNE PHILLIPS |KEVIN MOORE DOE | |HQ OPS OFFICER: LEIGH TROCINE |CHECKAN EPA | +------------------------------------------------+JIM RAAB HHS | |EMERGENCY CLASS: SITE AREA EMERGENCY | | |10 CFR SECTION: | | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED | | |KBAD 70.50(b)(1)(ii) MATL >5X LOWEST LIMIT | | |KBDA 70.50(b)(4)(i) FIRE/EXP INVOLV LNM | | |NOCM COMM ASST BRIEF | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DECLARATION OF A SITE AREA EMERGENCY DUE TO A FIRE EXCEEDING 15 MINUTES, A | | BREECH OF CONTAINMENT, AND THE POTENTIAL FOR A RADIOACTIVE RELEASE | | | | AT 1226, THE LICENSEE DECLARED A SITE AREA EMERGENCY DUE TO A FIRE THAT WAS | | NOT EXTINGUISHED WITHIN 15 MINUTES, A BREECH IN CONTAINMENT, AND THE | | POTENTIAL FOR A RADIOACTIVE RELEASE. THE FIRE WAS DETECTED IN THE #302 | | INCINERATOR ROOM. IT SPREAD TO THE DUCT WORK ON THE ROOF AND BREECHED THE | | DUCT WORK. AT THE TIME OF THIS NOTIFICATION, THE FIRE WAS UNDER CONTROL, | | AND IT WAS EXTINGUISHED BY 1255 (DURING THIS NOTIFICATION). THE | | INCINERATOR WAS BURNING RADIOACTIVE MATERIAL AT THE TIME SO THE POTENTIAL | | EXISTED FOR A RADIOLOGICAL RELEASE. THE LICENSEE DETERMINED THAT THERE WAS | | A MAXIMUM OF 800 GRAMS OF HIGH ENRICHED URANIUM AVAILABLE FOR RELEASE AND | | IS CURRENTLY PERFORMING EVALUATIONS TO DETERMINE A MORE ACCURATE QUANTITY. | | (IT WAS LATER DETERMINED THAT THERE WAS APPROXIMATELY 200 GRAMS OF 90% | | ENRICHED URANIUM AVAILABLE FOR POSSIBLE RELEASE.) AT THE TIME OF THIS | | NOTIFICATION, THE WIND WAS BLOWING OUT OF THE SOUTH (AWAY FROM THE LOCAL | | POPULATION CENTER) AT A SPEED OF THREE TO FIVE MILES PER HOUR. OFFSITE | | EVACUATION WAS NOT RECOMMENDED. THE LOCAL FIRE DEPARTMENT AND LOCAL LAW | | ENFORCEMENT REPRESENTATIVES RESPONDED TO THE SITE TO ASSIST ONSITE | | EMERGENCY RESPONSE PERSONNEL. | | | | IN ADDITION TO THE NOTIFICATIONS REFERENCED AT THE TOP OF THIS FORM, THE | | NRC OPERATIONS CENTER NOTIFIED THE USDA (KECIA COOPER). | | | | * * * 1345 APRIL 2, 1996, NRC UPDATE TAKEN BY BAILEY * * * | | | | AT 1345 ON APRIL 2, 1996, THE NRC ENTERED THE MONITORING PHASE OF NORMAL | | OPERATIONS. | | | | * * * 1445 APRIL 2, 1996, COMMISSIONERS' ASSISTANTS BRIEFING * * * | | | | A COMMISSIONERS' ASSISTANTS BRIEFING WAS CONDUCTED IN ORDER TO DISCUSS THE | | ONGOING SITE AREA EMERGENCY. THE FOLLOWING BRIEFING NOTIFICATIONS WERE | | MADE (*INDICATES OFFICE DID NOT PARTICIPATE): AEOD (JORDAN, ROSS, AND | | CONGEL), ERB (BARRETT AND BAILEY), CHAIRMAN JACKSON (BOYLE AND JOHNSON), | | COMMISSIONER ROGERS (COPLAN), COMMISSIONER DICUS (LUBENAU), EDO (THOMPSON), | | NMSS EO (COOL), PAO (BEECHER), CAO (KEELING), SECY (HART), STATE PROGRAMS | | (BANGART), IP (*UPSHAW), BRIEFER (REYES), AND OTHERS (PAPERIELLO, BRACH, | | TENECK, GREEVES, TROSKOWSKI, AND THE PROTECTIVE MEASURES TEAM) | | | | THE FOLLOWING IS A SUMMARY OF COMMISSIONER'S ASSISTANTS BRIEFING: THE FIRE | | IN THE INCINERATOR BUILDING WAS DETECTED AT 1158. THE LICENSEE DECLARED | | THE SITE AREA EMERGENCY AT 1226, AND THE FIRE WAS EXTINGUISHED AT | | APPROXIMATELY 1230. THE FIRE DAMAGE TO THE ROOF VENTILATION DUCT WORK WAS | | IN AN AREA APPROXIMATELY 40 FEET LONG. THE LICENSEE NOTIFIED THE STATE OF | | TENNESSEE, AND THE STATE'S INDEPENDENT AIR SAMPLING SYSTEM WAS ACTIVATED AT | | APPROXIMATELY 1340. THE STATE ALSO DISPATCHED FOUR REPRESENTATIVES TO | | PERFORM RELEASE ASSESSMENTS. THE NRC DISPATCHED A REGIONAL MANAGER, TWO | | REGIONAL RADIATION SPECIALISTS, AND A HEADQUARTERS PROJECT MANAGER TO THE | | SITE. THE NRC ALSO ENTERED THE MONITORING PHASE OF NORMAL OPERATIONS AT | | 1345. THE LICENSEE HAS ESTIMATED THAT THE WORST CASE POTENTIAL RELEASE | | COULD HAVE BEEN UP TO 200 GRAMS OF URANIUM-235, AND THE LICENSEE'S | | ANALYTICAL CALCULATIONS SHOW THAT THERE COULD BE UP TO A 3 MILLIREM | | EXPOSURE AT A DISTANCE OF 1 MILE DOWN WIND. THE LICENSEE HAS LOCKED DOWN | | ITS FACILITY AND HAS PERFORMED NASAL SWIPES FOR THE RESPONDERS TO THE FIRE. | | THE RESULTS ARE CURRENTLY PENDING. THE LICENSEE DOWNGRADED ITS EMERGENCY | | CLASSIFICATION TO UNUSUAL EVENT AT 1450 BECAUSE THE FIRE WAS EXTINGUISHED | | AND UNDER CONTROL AND BECAUSE THE SITUATION DOES NOT APPEAR TO BE AS | | SEVERE. | | | | * * * 1518 APRIL 2, 1996, UPDATE FROM PHILLIPS RECEIVED BY BAILEY * * * | | | | THE LICENSEE DOWNGRADED ITS EMERGENCY CLASSIFICATION TO UNUSUAL EVENT AT | | 1450. THE LICENSEE ALSO NOTIFIED FEMA, ANI, AND THE STATE OF TENNESSEE OF | | THIS CHANGE IN CLASSIFICATION. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO | | (URYC), NMSS EO (COOL), FEMA (EARL), DOE (MOORE AND SCHMIT), EPA (CHECKAN), | | HHS (RAAB), USDA (COOPER), AND ARAC. | | | | * * * 1700 APRIL 2, 1996, NRC UPDATE TAKEN BY TROCINE * * * | | | | THE NRC TERMINATED THE MONITORING PHASE OF NORMAL OPERATIONS AT 1700 ON | | APRIL 2, 1996. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30221 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 04/02/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 13:55 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/02/96 | +------------------------------------------------+EVENT TIME: 10:45[CST]| |NRC NOTIFIED BY: NETERER |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE MANUALLY TRIPPED THE REACTOR FROM 100% POWER DUE TO ISOLATION | | OF THE "B" FEEDWATER ISOLATION VALVE. | | | | THIS OCCURRED WHEN THEY RECEIVED A NOT FULL OPEN ANNUNCIATOR SIGNAL ON THE | | MAIN FEED/MAIN STEAM WATER ISOLATION VALVE AND FOUND THAT THE "B" STEAM | | GENERATOR FEEDWATER ISOLATION VALVE (AEFVOO4O) WAS GOING FAST CLOSE AT | | WHICH TIME THEY MANUALLY TRIPPED THE REACTOR. PRESENTLY IT IS APPARENT | | THAT IT WAS EQUIPMENT MALFUNCTION IN THEIR MAIN FEED/MAIN STEAM ISOLATION | | CABINET, AND I&C AND ENGINEERS ARE CONTINUING TO INVESTIGATE. ALL RODS | | FULLY INSERTED DURING THE TRIP AND NO PRIMARY SAFETY RELIEF VALVES LIFTED, | | HOWEVER ONE SECONDARY RELIEF VALVE(SG ATMOSPHERIC PORV) LIFTED FOR 3 | | SECONDS AND THAN FULLY RESEATED. ALONG WITH THE FW ISOLATION THEY HAD AUX | | FEEDWATER ACTUATION. THEY MANUALLY ISOLATED "A" L.P. HEATER STRING DUE TO | | LEAKAGE REPORTS. L.P. HEATER STRING "C" AUTO ISOLATES ON HIGH LEVEL. SOURCE | | RANGE ENERGIZED, N32 PEGGED HIGH AND THEY RECEIVED A SOURCE RANGE HIGH FLUX | | TRIP ALARM. THEY THEN ENTERED TS 3.3.1. THE N32 FUSES WERE PULLED TO | | REMOVE HIGH FLUX ALARM. AT THIS POINT THEY THEN RECEIVED A FLUX DOUBLING | | SWAPOVER OF CHARGING PUMP SUCTION TO THE RWST. THEY ATTEMPTED TO RESET THE | | SOURCE RANGE FLUX DOUBLE, BUT IT WOULD NOT RESET. THE CVCS LETDOWN RELIEF | | LIFTED. THE SOURCE RANGE FLUX DOUBLE WAS BLOCKED AND CHARGING PUMP SUCTION | | WAS SWAPPED TO THE VCT. THE SOURCE RANGE FLUX DOUBLE WAS RESET AND I&C | | REINSTALLED THE N32 FUSES AND THE ANNUNCIATOR CLEARED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30222 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/02/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 13:58 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/02/96 | +------------------------------------------------+EVENT TIME: 13:49[EST]| |NRC NOTIFIED BY: JIM RUMBIN |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO PLANNED MAINTENANCE | | | | AS PART OF A PLANNED EVOLUTION, THE LICENSEE INTERRUPTED A POWER SUPPLY TO | | THE REACTOR BUILDING TO SUPPRESSION CHAMBER VACUUM BREAKERS IN ORDER TO | | REWIRE THE POWER SUPPLY. THE FUSE WAS PULLED TO INTERRUPT POWER AT 1349, | | AND THE UNIT ENTERED THE ACTION STATEMENT FOR TECHNICAL SPECIFICATION | | 3.5.A.7. THIS TECHNICAL SPECIFICATION REQUIRES THE UNIT TO BE IN COLD | | SHUTDOWN WITHIN 24 HOURS WITHOUT THE CORRECT NUMBER OF REACTOR BUILDING TO | | TORUS VACUUM BREAKERS BEING OPERABLE. DURING THIS EVENT NOTIFICATION, | | POWER WAS RESTORED AT 1404, AND THE ACTION STATEMENT WAS EXITED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30223 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/02/96 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 14:13 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/02/96 | +------------------------------------------------+EVENT TIME: 14:10[EST]| |NRC NOTIFIED BY: BAILEY |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 N 0 REFUELING | 0 REFUELING | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE ENTERED TS 3.15.1 12-HOUR LCO ACTION STATEMENT TO BE SHUT DOWN | | FOR UNITS 1 AND 3 DUE TO THE PENETRATION ROOM VENTILATION SYSTEM FILTER | | BEING DECLARED INOPERABLE. | | | | THIS CONDITION WAS REVEALED WHEN ENGINEERING DISCOVERED THAT TESTS | | PERFORMED ON THE CARBON FILTERS FOR THE PENETRATION ROOM VENT SYSTEM, THE | | REACTOR BUILDING PURGE SYSTEM AND THE SPENT FUEL POOL VENT SYSTEM ARE BEING | | CONDUCTED USING A MORE CURRENT AND CONSERVATIVE STANDARD(ASTM D3803-1989) | | WHICH USES A TEST TEMPERATURE OF 30 DEGREES C. HOWEVER, TS 4.5.4 FOR THE | | PENETRATION ROOM VENT SYSTEM AND TS 4.14 FOR THE REACTOR BUILDING PURGE AND | | SPENT FUEL POOL VENT SYSTEMS REQUIRE TESTING BE PERFORMED IN ACCORDANCE | | WITH ANSI N510-1975 AT 130 DEGREES C. WHILE THE CURRENT TESTING IS MORE | | CONSERVATIVE THAN THE TS REQUIREMENT, THE TESTING METHODOLOGY IS NOT IN | | ACCORDANCE WITH THE LITERAL WORDING OF THE TS. | | | | TS 4.5.4 REQUIRES THAT THE PENETRATION ROOM VENT SYSTEM BE DECLARED | | INOPERABLE IF TESTING IS NOT PERFORMED PER ANSI N510-1975. DECLARING THIS | | SYSTEM INOPERABLE WOULD REQUIRE THE A PLANT S/D AS PER TS 3.15.1. | | | | ADDITIONALLY TS 4.14 HAS SIMILAR TESTING REQUIREMENTS FOR THE REACTOR | | BUILDING PURGE AND SPENT FUEL POOL VENT SYSTEM CARBON FILTERS. WHILE | | DECLARING THESE SYSTEMS INOPERABLE WOULD NOT REQUIRE THE SHUTDOWN OF ANY | | UNIT, DECLARING THE SPENT FUEL POOL VENT SYSTEM INOPERABLE WOULD PREVENT | | FUEL MOVEMENT WITHIN THE SPENT FUEL POOL. | | | | AN EMERGENCY TS AMENDMENT IS BEING DEVELOPED TO CHANGE THE TS CARBON FILTER | | TESTING REQUIREMENTS TO MATCH THE MORE CONSERVATIVE TEST METHOD THAT IS | | BEING USED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30224 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 04/02/96 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 17:46 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 04/02/96 | +------------------------------------------------+EVENT TIME: 15:30[MST]| |NRC NOTIFIED BY: KATHLEEN ROBERSON |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM STETKA RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | |BRECK HENDERSON, R4 PAO | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANNED PRESS CONFERENCE TO DISCUSS THE REMOVAL OF A FUEL ASSEMBLY WHICH IS | | CURRENTLY LOCATED IN THE UNIT 2 CORE AND MEDIA CONTAINMENT TOUR | | | | AT APPROXIMATELY 1600 MST, THE LICENSEE PLANS TO HOLD A PRESS CONFERENCE | | FOR LOCAL MEDIA PERSONNEL TO DISCUSS THE REMOVAL OF THE REMAINING FUEL | | ASSEMBLY WHICH IS CURRENTLY LOCATED IN THE UNIT 2 REACTOR CORE. MEMBERS OF | | THE MEDIA WILL ALSO BE INVITED TO TOUR THE UNIT 2 CONTAINMENT. | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTORS, NRC REGION 4 OFFICE, | | AND NRC WALNUT CREEK FIELD OFFICE. REPRESENTATIVES FROM THE REGION 4 | | OFFICE AND FROM THE NRC RESIDENT INSPECTOR STAFF ARE CURRENTLY ON SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30225 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 04/02/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 18:24 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 04/02/96 | +------------------------------------------------+EVENT TIME: 16:12[EST]| |NRC NOTIFIED BY: STEVEN M. SMITH |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | M/R Y 13 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP/TURBINE TRIP FROM 13% REACTOR POWER DUE TO HIGH MAIN | | GENERATOR STATOR DIFFERENTIAL TEMPERATURE | | | | AT 1612, A REACTOR/TURBINE TRIP WAS MANUALLY INITIATED FROM 13% REACTOR | | POWER AS A RESULT OF MAIN ELECTRICAL GENERATOR STATOR RTDs INDICATING A | | DIFFERENTIAL TEMPERATURE IN EXCESS OF THE LICENSEE'S OPERATIONAL LIMITS. | | ALL CONTROL RODS FULLY INSERTED FOLLOWING THE REACTOR TRIP, AND ALL SAFETY | | SYSTEMS FUNCTIONED AS REQUIRED. THE LICENSEE MANUALLY TRIPPED THE | | FEEDWATER PUMPS PER THE EMERGENCY OPERATING PROCEDURES, AND THIS CAUSED AN | | AUTOMATIC START OF AUXILIARY FEEDWATER. THE LICENSEE DOES NOT CONSIDER | | THIS TO BE AN ENGINEERED SAFEGUARDS FEATURE ACTUATION. THE CAUSE OF THE | | HIGH MAIN GENERATOR STATOR DIFFERENTIAL TEMPERATURE IS UNDER INVESTIGATION. | | | | THE UNIT IS CURRENTLY STABLE IN A HOT SHUTDOWN CONDITION. OPERATORS ARE | | CURRENTLY UTILIZING NORMAL CHARGING AND MAKEUP, PRESSURIZER HEATERS AND | | SPRAYS, AND THE REACTOR COOLANT PUMPS FOR PRIMARY INVENTORY, PRESSURE, AND | | TRANSPORT CONTROL. AUXILIARY FEEDWATER IS BEING UTILIZED TO SUPPLY WATER | | TO THE STEAM GENERATORS, AND SECONDARY STEAM IS BEING DUMPED TO THE | | ATMOSPHERE. THERE HAS BEEN NO EVIDENCE OF STEAM GENERATOR TUBE LEAKAGE. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND CURRENTLY PLANS TO | | ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30226 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/02/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 18:34 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/02/96 | +------------------------------------------------+EVENT TIME: 16:45[EST]| |NRC NOTIFIED BY: DAVID COSEO |LAST UPDATE DATE: 04/02/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SHEAR 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR FREEZING OF THE COOLING TOWER INLET LINES DUE TO BLOCKAGE OF | | THE DRAIN LINES THAT COME OFF OF THE COOLING TOWER INLET LINES | | | | DURING A WALKDOWN OF THE RESIDUAL HEAT REMOVAL (RHR) COMPLEX, IT WAS NOTED | | THAT THE DRAIN LINES FOR THE RHR SERVICE WATER COOLING WATER TOWERS WERE | | COMPLETELY OR PARTIALLY BLOCKED. THE DRAIN LINES FUNCTION TO DRAIN THE | | 18-INCH COOLING TOWER INLET LINES UPON COOLING TOWER SHUTDOWN AND | | ISOLATION. | | | | IN THE EVENT OF EXTREMELY COLD WEATHER, THERE IS A POTENTIAL THAT INLET | | LINES, WHICH ARE PARTIALLY EXPOSED TO OUTSIDE TEMPERATURES, COULD FREEZE IF | | THE DRAIN PATH IS BLOCKED. COMPLETE FREEZING OF THESE LINES WOULD RENDER | | THE COOLING TOWERS INOPERABLE AND INCAPABLE OF COOLING THE RHR COMPLEX | | RESERVOIR (THE ULTIMATE HEAT SINK) IF NEEDED IN THE EVENT OF AN ACCIDENT. | | THERE HAS BEEN NO EVIDENCE OF THE COOLING TOWER INLET VALVES FREEZING | | DURING PAST OPERATION OF THE COOLING TOWERS IN COLD WEATHER. | | | | THE LICENSEE CONSIDERS THE COOLING TOWERS TO BE OPERABLE AT THIS TIME DUE | | TO THE PRESENT TEMPERATURES BEING NEAR OR ABOVE FREEZING. THE LICENSEE IS | | CURRENTLY EVALUATING WHAT ACTIONS ARE NECESSARY PRIOR TO PLANT STARTUP. | | FURTHER EVALUATION OF THE POTENTIAL FOR FREEZING THE COOLING TOWER INLET | | LINES IS ALSO IN PROGRESS. | | | | THE LICENSEE IS REPORTING THIS ISSUE AS A CONDITION FOUND WHILE THE REACTOR | | IS SHUTDOWN THAT HAD IT BEEN FOUND WHILE THE REACTOR WAS IN OPERATION WOULD | | HAVE RESULTED IN THE NUCLEAR PLANT BEING SERIOUSLY DEGRADED OR BEING IN AN | | UNANALYZED CONDITION THAT SIGNIFICANTLY COMPROMISES PLANT SAFETY. THE | | LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+