U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/30/95 - 07/03/95 ** EVENT NUMBERS ** 28956 28997 28998 29006 29007 29008 29009 29010 29011 29012 29013 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28956 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 06/16/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 13:54 [ET]| |RX TYPE: [3] CE |EVENT DATE: 06/16/95 | +------------------------------------------------+EVENT TIME: 12:00[CDT]| |NRC NOTIFIED BY: PENDERGRASS |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH 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 +------------------------------------------------------------------------------+ | OUTSIDE DESIGN BASIS - SHUTDOWN COOLING VALVE FOUND TO BE INOPERABLE | | | | ON 06/11/95 AT 1311 (CDT), WHILE MAKING PREPARATIONS TO PLACE SHUTDOWN | | COOLING IN SERVICE, THE TRAIN "B" SUCTION VALVE (SI-405B) WOULD NOT FULLY | | OPEN. THE VALVE WAS DECLARED INOPERABLE. FURTHER INVESTIGATION REVEALED | | THAT THE HYDRAULIC OIL RESERVOIR LEVEL WAS LOW. THE LICENSEE DISCOVERED A | | SMALL OIL LEAK WHICH EXPLAINED THE LOW LEVEL. REPAIRS WERE MADE AND THE | | VALVE WAS RETURNED TO OPERABILITY. | | | | THE EXACT TIME AT WHICH THE VALVE BECAME INOPERABLE IS UNKNOWN. THEREFORE, | | THE LICENSEE CONCLUDED THAT THEY MAY HAVE OPERATED FOR SOME PROLONGED | | PERIOD OF TIME WITH THE VALVE (AND ONE TRAIN OF SHUTDOWN COOLING) | | INOPERABLE. THE LAST TIME OPERABILITY WAS VERIFIED WAS APRIL, 1994. | | THIS PLACED THE PLANT IN A CONDITION OUTSIDE OF DESIGN BASIS. THE | | ENGINEERING REVIEW WHICH LED TO THIS CONCLUSION WAS COMPLETED AT | | 1200 (CDT) ON 06/16/95. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE @ 1155 EDT ON 06/30/95 FROM LICENSEE: LITOLFF BY: McGINTY *** | | | | THE LICENSEE IS RETRACTING THIS EVENT WHICH ORIGINALLY REPORTED THE | | DISCOVERY THAT THE REACTOR COOLANT LOOP 1 SDC SUCTION LINE VALVE (SI-405B) | | WOULD ONLY OPEN 90% AND THEN CLOSE AFTER 15 MINUTES DUE TO NOT MAKING UP | | THE FULL LIMIT SWITCH. | | | | A ROOT CAUSE ANALYSIS HAS BEEN PERFORMED WHICH REVEALED THAT SDC TRAIN B | | WOULD HAVE BEEN ABLE TO PERFORM ITS INTENDED SAFETY FUNCTION DURING AN | | ACCIDENT. THIS WAS BASED ON TAKING CREDIT FOR OPERATOR ACTIONS TO DISABLE | | THE TIMING CIRCUIT WHICH CAUSES THE VALVE TO CLOSE. THIS IS SUPPORTED | | BY THE FACT THAT SDC IS A MANUALLY ACTUATED SYSTEM FOR WHICH A DELAY IN | | INITIATION WOULD NOT AFFECT THE SAFE SHUTDOWN CAPABILITY OF THE PLANT. | | WITH SI-405B 90% OPEN THERE IS VIRTUALLY NO AFFECT ON SYSTEM OPERATION. | | | | BASED ON THE ABOVE IT HAS BEEN DETERMINED THAT THE SDC SYSTEM CONTAINED | | SUITABLE REDUNDANCY TO PERFORM ITS INTENDED SAFETY FUNCTION. THEREFORE, | | THIS CONDITION DID NOT CAUSE WATERFORD 3 TO BE OUTSIDE THE DESIGN BASIS OF | | THE PLANT AND IS NOT REPORTABLE. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED THE R4DO (SANBORN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28997 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 06/28/95 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 14:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/28/95 | +------------------------------------------------+EVENT TIME: 13:50[EDT]| |NRC NOTIFIED BY: DENNIS MCCORKEL |LAST UPDATE DATE: 07/01/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BOB DENNIG EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOHN DAMICO FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT - ALL SITE EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE | | | | ALL SITE EMERGENCY DIESEL GENERATORS (EDG) WERE DECLARED INOPERABLE BASED | | ON A DESIGN FLAW IN THEIR TURBOCHARGERS. EACH UNIT HAS TWO EDGs. THE '2B' | | EDG IS TAGGED OUT AND UNAVAILABLE (THE TURBOCHARGER FAILED ON THIS EDG), | | THE OTHER THREE EDGs ARE AVAILABLE. ALL OTHER SAFETY SYSTEMS AND OFFSITE | | POWER SOURCES ARE OPERABLE. | | | | THE UNUSUAL EVENT WAS DECLARED AT 1350. THE LICENSEE ENTERED TECH SPEC | | 3.0.3 AT THE SAME TIME. BOTH UNITS MUST BE IN MODE 3 WITHIN 7 HOURS OF | | DECLARATION (2050) AND MODE 5 WITHIN AN ADDITIONAL 30 HOURS. | | | | THE EDGs WERE MANUFACTURED BY NORDBERG, AND THE TURBOCHARGERS WERE MADE BY | | ABB. THE INVESTIGATION IS FOCUSING ON A DESIGN FLAW THAT INCREASES THE | | TURBULENCE OF THE INTAKE AIR STREAM IN THE TURBOCHARGER. | | | | THE LICENSEE NOTIFIED APPROPRIATE STATE AND LOCAL OFFICIALS AS WELL AS THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1850 ON 6/28/95 BY MCCORKEL TAKEN BY WEAVER * * * | | | | UNIT 1 IS IN MODE 3. ENFORCEMENT DISCRETION HAS BEEN GRANTED FOR UNIT 2. | | THE LICENSEE HAS 34 HOURS TO COMPLETE THE REPAIRS ON THE '2B' EDG. UPON | | COMPLETION OF REPAIRS TO THE '2B' EDG, THE LICENSEE WILL BE IN A 72-HOUR | | LCO WITH ONLY THE '2A' EDG INOPERABLE ON UNIT 2. POWER DESCENT ON UNIT 2 | | WAS STOPPED AT 30%. POWER WILL BE INCREASED TO 45% ON UNIT 2 & HELD THERE. | | | | HOO NOTIFIED R2DO (URYC) AND NRR EO (SPESSARD). | | | | * * * UPDATE AT 0751 ON 06/29/95 BY SARRATT TAKEN BY KARSCH * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT FOR UNIT 2 AT 0740 EDT ON | | 06/29/95 BY RETURNING THE "2B" EDG TO OPERABILITY. A NEW DESIGN DIFFUSER | | PLATE WAS INSTALLED IN THE TURBOCHARGER TO BLANK OFF THE TURBULENCE. THE | | DISCRETIONARY ENFORCEMENT HAS BEEN TERMINATED. UNIT 2 IS IN A 72-HOUR LCO | | WHICH STARTED AT 1350 EDT ON 06/28/95 FOR THE "2A" EDG. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R2DO (URYC), NRR EO | | (DENNIG), AND FEMA (WITSBERGER). | | | | * * * UPDATE AT 0436 ON 07/01/95 BY McALLISTER TAKEN BY HOO JOLLIFFE * * * | | | | AT 0415 ON 07/01/95, LICENSEE TERMINATED THE UNUSUAL EVENT ON UNIT 1 | | AFTER RESTORING EDG #1A TO OPERABLE STATUS; EDG #1B IS STILL INOPERABLE. | | LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL OFFICIALS | | OF THE TERMINATION OF THE UNUSUAL EVENT ON UNIT 1. HOO NOTIFIED R2DO URYC, | | NRR EO SPESSARD, AND FEMA SIMMERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28998 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 06/28/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 15:28 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 06/28/95 | +------------------------------------------------+EVENT TIME: 12:15[CDT]| |NRC NOTIFIED BY: MARK ORTMEYER |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 Y 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - STEAM GENERATOR BLOWDOWN ISOLATION | | | | DURING THE PERFORMANCE OF A FUNCTIONAL TEST ON RADIATION MONITOR CHANNEL | | R-19, AN INADVERTENT BLOWDOWN ISOLATION OCCURRED. THE ACTUATION OCCURRED | | WHEN THE KEY SWITCH FOR THAT MONITOR WAS REPOSITIONED FROM ON TO THE KEY | | PAD POSITION. THE LICENSEE SUSPECTS THAT THE SWITCH CONTACTS ARE FAULTY. | | | | ALL OF THE EXPECTED ISOLATIONS DID NOT OCCUR. THE LICENSEE IS SPECULATING | | THAT THE FAULTY SWITCH CAUSED A MOMENTARY LOSS OF POWER TO THE ISOLATION | | RELAYS. THEREFORE, SOME RELAYS CHANGED POSITION, AND SOME DID NOT. THIS | | THEORY IS SUPPORTED BY A TEST THE LICENSEE CONDUCTED. POWER WAS REMOVED | | FROM ALL THE RELAYS, AND ALL OF THE EXPECTED ISOLATIONS OCCURRED. THE | | RADIATION MONITOR IS INOPERABLE. | | | | THE POINT BEACH RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT, THE KEWAUNEE | | RESIDENT INSPECTORS WERE UNAVAILABLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29006 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 06/30/95 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 00:31 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 20:16[CDT]| |NRC NOTIFIED BY: DOM LOGALBO |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 | 0 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 | 0 | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN EMERGENCY EQUIPMENT COOLING WATER (EECW) PUMP STARTED UNEXPECTEDLY | | DURING AN RHR SYSTEM SURVEILLANCE TEST. | | | | DURING PERFORMANCE OF 0-SI-4.2.B-67 (RHR SERVICE WATER INITIATION LOGIC), | | AN UNEXPECTED AUTO START OF B1 EECW PUMP OCCURRED. AS PART OF THE TEST, | | JUMPERS WERE PUT IN PLACE TO PREVENT EECW PUMPS A3, B1, C1, AND D3 FROM | | AUTO STARTING ON LOW RAW COOLING WATER (RCW) SYSTEM PRESSURE. WHEN RCW | | SYSTEM PRESSURE WAS LOWERED IN A SUBSEQUENT STEP TO TEST THE INITIATION | | LOGIC, PUMP B1 UNEXPECTEDLY AUTOMATICALLY STARTED. | | | | TESTING HAS BEEN SUSPENDED PENDING INVESTIGATION OF THE CAUSES OF THIS | | EVENT. THE JUMPERS SEEM TO BE CORRECTLY INSTALLED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29007 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 06/30/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 13:33 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 17:11[CDT]| |NRC NOTIFIED BY: PETER |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | TRAIN 'A' CONTROL ROOM ENVELOPE HVAC WAS INOPERABLE DUE TO A REG GUIDE 1.75 | | SEPARATION VIOLATION. | | | | THE TRAIN 'A' CONTROL ROOM ENVELOPE HVAC (HEATING VENTILATION AND AIR | | CONDITIONING) DAMPER 'A1HEFCV9584' WAS DETERMINED TO BE INOPERABLE ON | | 6/29/95 AT 1711 CDT DUE TO VIOLATION OF REGULATORY GUIDE (RG) 1.75 | | SEPARATION REQUIREMENTS. THE CONDITION EXISTED FOR A PERIOD GREATER THAN | | SEVEN DAYS, WHICH IS IN NONCOMPLIANCE WITH TECHNICAL SPECIFICATION 3.7.7, | | ACTION 'A'. THIS IS REPORTABLE PER STP UNIT 1 OPERATING LICENSE, ITEM 2.G. | | | | THE CONDITION WAS INITIALLY OBSERVED ON 6/28/95 AT 1530 CDT AND AN | | OPERABILITY/REPORTABILITY EVALUATION WAS REQUESTED IN ACCORDANCE WITH | | STATION PROCEDURES. THE RG 1.75 SEPARATION VIOLATION WAS CORRECTED ON | | 6/29/95 AT 1720 CDT. | | | | THE CONDITION INVOLVES THE WIRING FOR THE CONTROLLER FOR THE DAMPER, | | LOCATED BEHIND THE CONTROL BOARD. THE REQUIREMENT IS FOR 6 INCHES OF OPEN | | AIR GAP ON EXPOSED WIRING, AND THIS PARTICULAR WIRING ONLY HAD ABOUT 5 | | INCHES. THE LICENSEE IS INVESTIGATING THE POSSIBLE APPLICABILITY TO | | UNIT 2. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29008 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NATIONAL INSTITUTE OF HEALTH |NOTIFICATION DATE: 06/30/95 | | CITY: BETHESDA REGION: 1 |NOTIFICATION TIME: 15:04 [ET]| | COUNTY: MONTGOMERY STATE: MD |EVENT DATE: 06/28/95 | |LICENSE#: 19-00296-10 AGREEMENT: Y |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/30/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ROBERT BORES RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ZOON | | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INTERNAL CONTAMINATION OF AN INVESTIGATOR AT THE NATIONAL INSTITUTE OF | | HEALTH. | | | | MR. ZOON, OF THE NATIONAL INSTITUTE OF HEALTH IN BETHESDA, MD, REPORTED AN | | INCIDENT THAT OCCURRED ON 6/28/95. AN INVESTIGATOR AT THE NATIONAL CANCER | | INSTITUTE WAS REPORTED AS HAVING DETECTABLE RADIOACTIVITY BURDEN. THE | | EMERGENCY RESPONSE AND FOLLOWUP HAS CONFIRMED THE EXISTENCE OF THE BURDEN. | | THIS EVENT IS BEING REPORTED AS INFORMATION, BECAUSE IT DOES NOT APPEAR | | THAT AN ANNUAL LIMIT ON INTAKE WAS EXCEEDED. HOWEVER, THERE ARE SOME | | SUSPICIOUS CIRCUMSTANCES REGARDING THE OCCURRENCE. THE ISOTOPE THAT WAS | | INGESTED IS P-32. | | | | THE INCIDENT IS UNDER INVESTIGATION BY THE NIH SAFETY AND SECURITY | | PROGRAMS. THERE ARE NO ADVERSE HEALTH CONSEQUENCES EXPECTED FOR THE | | INVESTIGATOR. THE ESTIMATED INGESTION IS ABOUT 300 MICROCURIES OF P-32, | | BASED ON URINE AND BLOOD SAMPLES. P-32 EMITS A 1.7 Mev BETA. THE LICENSEE | | BELIEVES THAT THE EVENT PROBABLY OCCURRED AROUND 1200 ON 6/28/95. | | | | THE NRC CONDUCTED A COMMISSIONER'S ASSISTANT'S BRIEFING AT 1200 ON 6/30/95. | | REGION 1 WILL BE DISPATCHING AN AIT. | | | | COMMISSIONERS ASSISTANTS BRIEFING NOTIFICATIONS: AEOD(JORDAN), | | ERB(BROCKMAN), CHMN SELIN(McCONNELL), JACKSON(WINSBERG), ROGERS(SORENSEN), | | de PLANQUE(LUBENAU), EDO(STABLIEN), NMSS(CAMPER, KNAPP), PAO(BEECHER), | | CAO(KEELING), SECY(HART), STATE(BANGART), IP(CONGDON), BRIEFER(DWYER), | | OI(CAPUTO), REGION 1(MARTIN, SHANKMAN, HEHL, BELLAMY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29009 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 06/30/95 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 15:11 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 06/30/95 | +------------------------------------------------+EVENT TIME: 14:26[EDT]| |NRC NOTIFIED BY: BAUCOM |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP ON LO LO SG WATER LEVEL DUE TO SPURIOUS CLOSURE OF 'B' MSIV. | | | | ROBINSON UNIT 2 EXPERIENCED AN AUTOMATIC REACTOR TRIP ON LOW LOW WATER | | LEVEL IN THE 'B' STEAM GENERATOR DUE TO A SPURIOUS CLOSURE OF THE 'B' MAIN | | STEAM ISOLATION VALVE (MSIV). THE 'B' MSIV HAS BEEN VERIFIED TO BE CLOSED | | LOCALLY, BUT THERE IS CURRENTLY NO POSITION INDICATION ON THE CONTROL | | BOARD. THE LICENSEE HAS ALSO IDENTIFIED A GROUND ON THE 'B' BATTERY | | CHARGER, AND SUSPECTS THAT THE GROUND IS ASSOCIATED WITH THE SPURIOUS | | CLOSURE OF THE 'B' MSIV AND THE LOSS OF INDICATION ON THE CONTROL BOARD. | | THE MSIVs USE DC SOLENOIDS TO DIRECT AIR FOR THEIR OPERATION. | | | | ALL RODS FULLY INSERTED INTO THE CORE. THERE WERE NO PROBLEMS WITH | | TRANSFERS OF BUS POWER SUPPLIES. THE LICENSEE IS FEEDING WITH MAIN | | FEEDWATER VIA THE BYPASS VALVES, AS REQUIRED, AND IS STEAMING TO THE MAIN | | CONDENSER VIA THE 'A' AND 'C' MAIN STEAM LINES. THE ECCSs AND EDGs ARE | | OPERABLE AND AVAILABLE. NO PRIMARY RELIEF VALVES OPENED, AND THE SG PORVs | | MOMENTARILY OPENED AND CLOSED, AS DESIGNED. THE REACTOR TRIPPED ON LOW LOW | | SG LEVEL IN THE 'B' STEAM GENERATOR DUE TO SHRINK ASSOCIATED WITH THE | | CLOSURE OF THE 'B' MSIV. THE LICENSEE WILL BE INVESTIGATING THE CAUSE OF | | THE EVENT AND HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | NOTE: SEE EVENT #29011 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29010 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 06/30/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:54 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 06/30/95 | +------------------------------------------------+EVENT TIME: 15:28[EDT]| |NRC NOTIFIED BY: MOSTERT |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 Y 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF OFFSITE POWER VIA CIRCUIT #751 (DUE TO A LIGHTNING STRIKE) CAUSED A | | START OF THE 'A' EDG. | | | | AT 1528 EDT ON 6/30/95, GINNA STATION EXPERIENCED A LOSS OF OFFSITE POWER, | | CIRCUIT #751. THIS RESULTED IN MOMENTARY LOSS OF POWER TO ONE TRAIN OF 480 | | VAC SAFEGUARDS BUSES (14 & 18), AND INSTRUMENT BUS 'B'. THESE BUSES WERE | | REENERGIZED BY THE AUTOMATIC START AND LOAD OF EDG 'A'. | | | | THE LOSS OF CIRCUIT #751 WAS CAUSED BY A LIGHTNING STRIKE ON AN OFFSITE | | ELECTRIC POWER POLE (ABOUT 4 MILES FROM THE STATION). ALL SAFEGUARDS | | EQUIPMENT FUNCTIONED PROPERLY, AND THERE WAS NO CHANGE IN TURBINE LOAD. | | OPERATORS RESPONDED TO THE EVENT BY ENTERING ABNORMAL PROCEDURE, | | 'AP-ELEC.1' TO STABILIZE PLANT SYSTEMS. REACTOR COOLANT SYSTEM | | TEMPERATURES AND PRESSURES REMAINED STABLE AT NORMAL FULL POWER OPERATING | | VALUES THROUGHOUT THE EVENT. | | | | AT 1557 EDT, THE 4160 VAC BUS '12A' WAS ENERGIZED FROM OFFSITE CIRCUIT #767 | | (4160 VAC BUS '12B' WAS POWERED VIA CIRCUIT #767 AT THE TIME OF THE EVENT | | AND WAS NOT AFFECTED). SAFEGUARDS BUSES WERE RESTORED TO THE NORMAL POWER | | ALIGNMENT AND THE 'A' EDG WAS SECURED AND PLACED IN STANDBY STATUS AT 1708 | | EDT. REPAIRS HAVE BEEN COMPLETED ON CIRCUIT #751 AND IT IS NOW AVAILABLE | | (NORMALLY GINNA OPERATES WITH ONE TRAIN OF SAFEGUARDS BUSES SUPPLIED VIA | | CIRCUIT #767 AND THE OTHER TRAIN POWERED VIA CIRCUIT #751). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29011 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 06/30/95 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 21:10 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 06/30/95 | +------------------------------------------------+EVENT TIME: 18:39[EDT]| |NRC NOTIFIED BY: BILLINGS |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTO START OF AFW AND S/G BLOWDOWN ISOLATION DURING RECOVERY FROM Rx TRIP. | | | | DURING THE RECOVERY OF STEAM GENERATOR LEVELS FOLLOWING A REACTOR TRIP | | (SEE EVENT #29009), THE ONE RUNNING MAIN FEEDWATER PUMP TRIPPED ON HIGH | | STEAM GENERATOR WATER LEVEL. THIS CAUSED AN AUXILIARY FEEDWATER PUMP | | AUTOMATIC START DUE TO BOTH MAIN FEEDWATER PUMP BREAKERS BEING OPENED. | | THE AUTOMATIC START SIGNAL CAUSED THE STEAM GENERATOR BLOWDOWN VALVES | | TO CLOSE. THESE CONTAINMENT ISOLATION VALVES ARE ESF COMPONENTS. | | | | THE HIGH STEAM GENERATOR WATER LEVEL WAS DUE TO LEAKAGE PAST THE CLOSED | | FEEDWATER REGULATING VALVES. THE BLOCK VALVES WERE CLOSED TO ISOLATE THE | | FEEDWATER REGULATING VALVES. THE BLOWDOWN VALVES WERE REOPENED AND STEAM | | GENERATOR WATER LEVELS RESTORED TO WITHIN THEIR NORMAL OPERATING BAND. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29012 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 07/01/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 03:53 [ET]| |RX TYPE: [3] CE |EVENT DATE: 07/01/95 | +------------------------------------------------+EVENT TIME: 00:18[CDT]| |NRC NOTIFIED BY: STEVE WINN |LAST UPDATE DATE: 07/01/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTROL ROOM VENT SYSTEM ISOLATED DUE TO NEARBY CHEMICAL PLANT RELEASE - | | | | AT 0018 (CDT), THE CONTROL ROOM VENTILATION SYSTEM ISOLATED DUE TO | | READINGS OF 6 AND 5 PPM ON BROAD RANGE GAS MONITORS #1 AND #2 RESPECTIVELY. | | SHORTLY AFTER DETECTION, THE CHEMICAL FUMES DISSIPATED AND THE GAS MONITORS | | RETURNED TO NORMAL READINGS OF LESS THAN 1 PPM EACH. | | | | AT 0042 (CDT), CHEMISTRY TECHNICIANS CONFIRMED THAT THERE WAS NO LONGER ANY | | INDICATION OF TOXIC GAS ON SITE. | | | | AT 0053 (CDT), CONTROL ROOM PERSONNEL WERE NOTIFIED THAT THE WITCO CHEMICAL | | PLANT LOCATED APPROXIMATELY 1 MILE FROM THE PLANT HAD BRIEFLY RELEASED SOME | | XYLENE, A CHEMICAL CLASSIFIED AS A SMALL HAZARD. | | | | AT 0107 (CDT), LICENSEE RESTORED THE CONTROL ROOM VENTILATION SYSTEM TO | | NORMAL. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29013 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/01/95 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 04:00 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/01/95 | +------------------------------------------------+EVENT TIME: 01:20[CDT]| |NRC NOTIFIED BY: BYRAN HANSEN |LAST UPDATE DATE: 07/01/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -2 CONTAINMENT ISOLATION VALVES WERE INOPERABLE WHILE UNIT 3 WAS AT POWER- | | | | ON 01/16/95, DURING A ROUTING VALVE CLOSING TIME TEST WHILE UNIT 3 WAS | | STARTING UP, THE 2 INCH INBOARD MAIN STEAM LINE DRAIN VALVE (#220-1) | | SHOWED DUEL VALVE POSITION INDICATION. LICENSEE DECLARED THIS PRIMARY | | CONTAINMENT ISOLATION VALVE INOPERABLE AND CLOSED THE IN-SERIES 2 INCH | | OUTBOARD MAIN STEAM LINE DRAIN VALVE (#220-2) (ALSO A PRIMARY CONTAINMENT | | ISOLATION VALVE) TO COMPLY WITH TECH SPEC LCO A/S 3.7.D.2. | | | | ON 06/30/95, LICENSEE PERFORMED A LOCAL LEAK RATE TEST ON BOTH DRAIN | | VALVES WHILE UNIT 3 WAS SHUTDOWN. THE AS-FOUND LEAKAGE ON BOTH VALVES | | WAS INDETERMINATE (THE VALVES WERE LEAKING THROUGH INTERNALLY). | | LICENSEE REMOVED THE OUTBOARD DRAIN VALVE AND INSTALLED A PIPE PLUG. | | UPON DISASSEMBLING THE OUTBOARD DRAIN VALVE, LICENSEE DISCOVERED THAT | | PIECES OF THE VALVE SEAT AND BODY WERE MISSING. BOTH VALVES WERE INSTALLED | | AS NEW VALVES DURING THE LAST REFUELING OUTAGE WHICH ENDED IN 11/94. | | | | LICENSEE DETERMINED THAT BOTH THE INBOARD AND OUTBOARD VALVES HAD BEEN | | INOPERABLE WHILE UNIT 3 HAD BEEN AT POWER OPERATIONS. | | | | UNIT 3 HAS BEEN SHUTDOWN IN A MAINTENANCE OUTAGE SINCE 05/28/95. | | | | LICENSEE IS INVESTIGATING THE CAUSE AND PLANS TO REPLACE BOTH VALVES | | PRIOR TO PLANT RESTART SCHEDULED FOR 08/03/95. | | | | THIS SAME CONDITION DOES NOT EXIST ON UNIT 2. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+