U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/14/95 - dr.der ~07/17/95 ** EVENT NUMBERS ** 28945 29008 29011 29063 29064 29065 29066 29067 29068 29069 29070 29071 29072 29073 29074 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28945 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 06/14/95 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 06/14/95 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: D AKERS |LAST UPDATE DATE: 07/17/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVE VERRELLI 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROCEDURAL ERROR CAUSED AUXILIARY FEEDWATER TO ACTUATE AND STEAM GENERATOR | | BLOWDOWN ISOLATION VALVES TO ISOLATE. | | | | PRIOR TO DRAINING THE STEAM GENERATORS IN PREPARATION FOR PLANT HEATUP PER | | THE STEAM GENERATOR DRAIN DOWN PROCEDURE THE AUTOMATIC START OF THE | | AUXILIARY FEEDWATER PUMPS ON LOW LOW STEAM GENERATOR WATER LEVEL DEFEAT | | SWITCH IS CHECKED TO MAKE SURE IT IS IN ITS DEFEATED POSITION. AUXILIARY | | OPERATOR CALLED CONTROL ROOM AND ASKED IF THE LEVEL SIGNAL FOR LOW LOW | | STEAM GENERATOR WATER LEVEL WAS DEFEATED (PREVENT AUXILIARY FEEDWATER PUMPS | | FROM AUTOMATICALLY STARTING ON LOW LOW STEAM GENERATOR WATER LEVEL WHICH IS | | 16% NARROW RANGE WHICH CORRESPONDS TO 80% STEAM GENERATOR WATER LEVEL WIDE | | RANGE). CONTROL ROOM SAID THAT THEY WERE DEFEATED (THEY WERE NOT DEFEATED, | | SENIOR REACTOR OPERATOR DID NOT LOOK AT THE SWITCH BUT LOOKED AT THE LIGHT | | INDICATION). WHEN STEAM GENERATOR WATER LEVEL DECREASED TO 80% WIDE LEVEL | | INDICATION BOTH MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS AUTOSTARTED AND | | INJECTED WATER INTO ALL THREE STEAM GENERATORS FOR ABOUT ONE MINUTE BEFORE | | THEY WERE SECURED (DID NOT OVER FILL THE STEAM GENERATORS). REACTOR COOLANT | | TEMPERATURE DID NOT CHANGE DURING THE TIME PERIOD AUXILIARY FEEDWATER | | INJECTED INTO THE STEAM GENERATORS (REACTOR COOLANT TEMPERATURE REMAINED AT | | 113 DEGREES F). LICENSEE ALSO HAD AUTO CLOSURE OF THE STEAM GENERATOR | | BLOWDOWN ISOLATION VALVES (CONTAINMENT ISOLATION). ALL SYSTEMS HAVE BEEN | | RETURNED TO THEIR PROPER LINEUP AND THEY ARE CONTINUING TO DRAIN THEIR | | STEAM GENERATORS. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE 7/14/95 AT 11:30 FROM CROOKE TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS RETRACTED THE NOTIFICATION OF THIS EVENT. THE FOLLOWING | | IS TEXT OF A LICENSEE FACSIMILE: | | | | "THIS IS A RETRACTION OF TWO EVENT NOTIFICATIONS MADE ON JUNE 14, 1995, AND | | ON JUNE 30, 1995. THESE NOTIFICATIONS CONCERNED APPARENT UNEXPECTED ESF | | ACTUATIONS (I.E., AUTOMATIC CLOSURE OF STEAM GENERATOR BLOWDOWN CONTAINMENT | | ISOLATION VALVES). SUBSEQUENT REVIEW OF EACH EVENT HAS CONCLUDED THAT | | THESE AUTOMATIC VALVE CLOSURES DO NOT CONSTITUTE ESF ACTUATIONS BECAUSE | | NEITHER VALVE CLOSURE SIGNAL WAS GENERATED BY AN ESF SIGNAL. THE ESF | | ACTUATION SIGNAL THAT CLOSES THIS VALVE IS A CONTAINMENT ISOLATION SIGNAL, | | AND NO CONTAINMENT ISOLATION SIGNAL WAS PRESENT FOR EITHER EVENT. THE | | CLOSURE OF THE STEAM GENERATOR BLOWDOWN VALVES IS ONLY CONSIDERED A PORTION | | OF THE CONTAINMENT ISOLATION FUNCTION. THEREFORE, THIS WAS NOT AN | | ACTUATION OF A SYSTEM TRAIN. BASED ON REVIEW OF 10 CFR 50.72, WE HAVE | | DETERMINED THAT THESE EVENTS ARE NOT REPORTABLE." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. NOTIFIED | | R2DO (RANKIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 07/14/95 | | +-----------------------------+ | |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). | | | | NOTE: SEE NRC PRELIMINARY NOTIFICATION #PNO-I-95-025. | | | | ***UPDATE AT 17:00 7/14/95 BY SEBROSKY*** | | COMMISSIONERS ASSISTANTS BRIEFING NOTIFICATIONS (*INDICATES OFFICE DID NOT | | PARTICIPATE): AEOD(JORDAN), IRB(BARRETT), CHMN JACKSON(BOYLE), | | ROGERS(COPLAN), EDO(STABLEIN), RDO(KINNEMAN), PAO(BEECHER), CAO(GERKE), | | SECY(*), STATE(BANGART), IP(UPSHAW), BRIEFER(SHANKMAN), NMSS(COMBS, COOL, | | PAPERIELLO), REGION I(KANE, JOHANSEN), AND REGION II(MALLETT). DURING THE | | INVESTIGATION OF THE ORIGINAL CONTAMINATION, THE LICENSEE IDENTIFIED A | | CONTAMINATED WATER COOLER. WHEN THE LICENSEE REMOVED THE WATER BOTTLE FROM | | THE COOLER, THE COOLER SHOWED INTERNAL CONTAMINATION. THE LICENSEE HAS | | ALSO IDENTIFIED 24 ADDITIONAL PERSONS WITH ELEVATED P-32 IN THEIR URINE. | | THE LICENSEE AND THE AIT ARE CONTINUING THEIR RESPECTIVE INVESTIGATIONS. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |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: 07/17/95 | |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. | | | | * * * UPDATE 7/14/95 AT 1130 FROM CROOK TAKEN BY STRANSKY: | | | | THE LICENSEE HAS RETRACTED A PORTION OF THIS EVENT NOTIFICATION. THE | | FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "THIS IS A RETRACTION OF TWO EVENT NOTIFICATIONS MADE ON JUNE 14, 1995 AND | | ON JUNE 30, 1995. THESE NOTIFICATIONS CONCERNED APPARENT UNEXPECTED ESF | | ACTUATIONS (I.E., AUTOMATIC CLOSURE OF STEAM GENERATOR BLOWDOWN CONTAINMENT | | ISOLATION VALVES). SUBSEQUENT REVIEW OF EACH EVENT HAS CONCLUDED THAT | | THESE AUTOMATIC VALVE CLOSURES DO NOT CONSTITUTE ESF ACTUATIONS BECAUSE | | NEITHER VALVE CLOSURE SIGNAL WAS GENERATED BY AN ESF SIGNAL. THE ESF | | ACTUATION SIGNAL THAT CLOSES THIS VALVE IS A CONTAINMENT ISOLATION SIGNAL, | | AND NO CONTAINMENT ISOLATION SIGNAL WAS PRESENT FOR EITHER EVENT. THE | | CLOSURE OF THE STEAM GENERATOR BLOWDOWN VALVES IS ONLY CONSIDERED A PORTION | | OF THE CONTAINMENT ISOLATION FUNCTION. THEREFORE, THIS WAS NOT AN | | ACTUATION OF A SYSTEM TRAIN. BASED ON REVIEW OF 10 CFR 50.72, WE HAVE | | DETERMINED THAT THESE EVENTS ARE NOT REPORTABLE." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. NOTIFIED | | R2DO (RANKIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 07/14/95 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 07:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/14/95 | +------------------------------------------------+EVENT TIME: 04:26[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 07/14/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARTIN FARBER 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 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP DUE TO A TURBINE TRIP ON A LOSS OF CONDENSER VACUUM. | | | | UNIT 1 RECEIVED AN AUTOMATIC REACTOR TRIP FROM A TURBINE TRIP WHICH | | RESULTED FROM A LOSS OF MAIN CONDENSER VACUUM. VACUUM WAS RESTORED TO | | NORMAL SHORTLY AFTER THE EVENT (WITHIN APPROXIMATELY 10 MINUTES) AND HAS | | REMAINED NORMAL. THE CAUSE FOR THE LOSS OF CONDENSER VACUUM IS UNDER | | INVESTIGATION AT THIS TIME. (APPROXIMATELY EIGHT MINUTES PRIOR TO THE | | TRIP, MAIN CONDENSER VACUUM BEGAN TO DECREASE. IT WAS RECOVERED FOR A | | SHORT PERIOD OF TIME, AND THEN IT WAS COMPLETELY LOST.) | | | | ALL CONTROL RODS FULLY INSERTED. BOTH MOTOR DRIVEN AUXILIARY FEEDWATER | | PUMPS AND THE TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS STARTED, AND A | | FEEDWATER ISOLATION OCCURRED AS DESIGNED. NO PRIMARY OR SECONDARY SAFETY | | VALVES LIFTED. OFFSITE POWER IS AVAILABLE, AND THE EMERGENCY DIESEL | | GENERATORS ARE IN STANDBY. AT THE TIME OF THE REACTOR TRIP, THE LICENSEE | | WAS IS THE PROCESS OF RESTORING ONE TRAIN OF CONTAINMENT SPRAY TO SERVICE | | FOLLOWING PLANNED MAINTENANCE. (THIS WAS NOT RELATED TO THE LOSS OF | | CONDENSER VACUUM.) ALL OTHER SAFETY SYSTEMS WERE AVAILABLE AND FUNCTIONED | | AS REQUIRED. DECAY HEAT IS BEING REMOVED BY THE USE STEAM DUMPS TO THE | | MAIN CONDENSER AND THE USE OF AUXILIARY FEEDWATER. THE UNIT IS CURRENTLY | | STABLE AT NO LOAD TEMPERATURE (547øF) AND PRESSURE (2080 PSIG). THE | | POST-TRIP REVIEW IS ONGOING, AND THE LICENSEE DOES NOT HAVE AN ESTIMATED | | RESTART SCHEDULE AT THIS TIME. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29064 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 07/14/95 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 12:00 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 07/14/95 | +------------------------------------------------+EVENT TIME: 10:10[CDT]| |NRC NOTIFIED BY: KEVIN GROTE |LAST UPDATE DATE: 07/14/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARTIN FARBER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |AL CHAFFEE EO | | | | | |FRANK INGRAM PA | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP DUE TO A TURBINE TRIP CAUSED BY A MAIN TRANSFORMER | | LOCKOUT. | | | | AT 10:10 A TURBINE TRIP/REACTOR TRIP OCCURRED. THE CAUSE OF THE TURBINE | | TRIP WAS A UNIT LOCKOUT ON THE MAIN TRANSFORMER. AT THIS TIME, THE | | LICENSEE DOES NOT KNOW THE CAUSE OF THE LOCKOUT. | | | | THE POST TRIP RESPONSE WAS NORMAL. NO PRIMARY RELIEF OR PORV VALVES | | LIFTED. ALL RODS INSERTED, AND ALL ECCS SYSTEMS AND EDGS SYSTEMS ARE | | OPERABLE. AUXILIARY FEEDWATER (AFW) AUTOMATICALLY STARTED DUE TO LOW LEVEL | | IN THE STEAM GENERATORS. STEAM GENERATOR WATER LEVEL WAS RESTORED BY THE | | AFW SYSTEM AND IS CURRENTLY BEING MAINTAINED BY THE MAIN FEEDWATER SYSTEM. | | | | THE MAIN CONDENSER IS UNAVAILABLE AS A HEAT SINK BECAUSE A RUPTURE DISK | | BLEW ON THE LOW PRESSURE TURBINE DURING THE TRANSIENT. THE LICENSEE IS | | UNABLE TO MAINTAIN CONDENSER VACUUM BECAUSE OF THIS PROBLEM. THE LICENSEE | | IS USING THE ATMOSPHERIC STEAM DUMPS TO CONTROL TEMPERATURE. | | | | THERE WERE NO PROBLEMS WITH ELECTRICAL BUS TRANSFERS DURING THE POST-TRIP | | RESPONSE, AND THE GRID APPEARS TO BE STABLE. UNIT 2 AT POINT BEACH REMAINS | | AT 100% POWER. | | | | THE LICENSEE PLANS TO ISSUE A PRESS RELEASE AND HAS INFORMED THE RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29065 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FRANK BARKER ASSOCIATES |NOTIFICATION DATE: 07/14/95 | | CITY: REGION: 1 |NOTIFICATION TIME: 16:42 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 07/13/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 23:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/14/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN KINNEMAN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JEFF STICKLER | | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FRANK BARKER ASSOCIATES CALLED TO REPORT AN APPARENT PROBLEM WITH A | | BRACHYTHERAPY HIGH DOSE RATE AFTER LOADER MACHINE. | | | | FRANK BARKER ASSOCIATES IS A DISTRIBUTOR FOR BRACHYTHERAPY HIGH DOSE RATE | | AFTER LOADER MACHINES. WHILE TECHNICIANS WERE IN THE PROCESS OF SETTING UP | | A NEW MACHINE AT APPLE HILL MEDICAL CENTER (YORK CANCER CENTER) IN YORK, | | PENNSYLVANIA, THEY RAN INTO A PROBLEM WITH THE SOURCE NOT FULLY RETRACTING | | BACK INTO THE MACHINE. THE HIGH DOSE RATE AFTER LOADER BRACHYTHERAPY | | MACHINE INVOLVED WAS A GAMMA MED MODEL 12I. NO PATIENT WAS INVOLVED IN THE | | PROCEDURE. | | | | THE TECHNICIANS HAD PERFORMED ACCEPTANCE TESTING ON THE MACHINE AND WERE IN | | THE PROCESS OF CHECKING OUT THE WELL CHAMBER. (THE WELL CHAMBER IS WHERE | | THE 10 CURIE IRIDIUM 192 SOURCE IS CHECKED BY INSTRUMENTS FOR CALIBRATION | | PRIOR TO ITS USE IN A PATIENT.) WHEN THE SOURCE WAS BEING RETRACTED BACK | | FROM THE WELL CHAMBER, IT DID NOT FULLY RETRACT INTO ITS SHIELDED POSITION. | | THE TECHNICIANS WERE INFORMED OF THE PROBLEM BY THE RADIATION LIGHTS NOT | | GOING OUT ON THE MACHINE AND THE COMPUTER SOFTWARE PROGRAM TELLING THEM | | THAT THE SOURCE WAS NOT FULLY RETRACTED. THE TECHNICIANS WERE ABLE TO | | FULLY RETRACT THE SOURCE BACK TO ITS SHIELDED POSITION. HOW THIS WAS DONE | | IS STILL BEING INVESTIGATED. THE TECHNICIANS INVOLVED WERE IN TRANSIT AT | | THE TIME OF THIS REPORT. | | | | THE PROBLEM APPEARS TO BE CAUSED BY A CLAMPING ADAPTER NOT BEING PROPERLY | | INSTALLED BY THE TECHNICIAN. THE CLAMPING ADAPTER IS USED TO CONNECT A | | TUBE ON THE MACHINE TO A CATHETER. THE CATHETER THEN DIRECTS THE SOURCE | | WIRE TO THE PROPER LOCATION. THERE HAVE BEEN PROBLEMS IN THE PAST WITH THE | | CLAMPING ADAPTER NOT BEING PROPERLY INSTALLED BY TECHNICIANS LEADING TO THE | | SOURCE BEING STUCK. PROCEDURES HAVE BEEN DEVELOPED TO PREVENT THIS PROBLEM | | AND IT IS NOT CLEAR AT THIS TIME IF THOSE PROCEDURES WERE FOLLOWED. THE | | MANUFACTURER HAS DESIGNED A NEW CLAMPING ADAPTER WHICH IS NOT SUSCEPTIBLE | | TO THIS PROBLEM. | | | | OFFICIALS FROM FRANK BARKER ASSOCIATES ARE STILL INVESTIGATING THE PROBLEM | | AND HAVE DISCUSSED THIS EVENT WITH REGION I (KIRKWOOD). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ANDERSON, GREENWOOD & CO (AGCO) |NOTIFICATION DATE: 07/14/95 | | CITY: STAFFORD REGION: 4 |NOTIFICATION TIME: 15:24 [ET]| | COUNTY: STATE: TX |EVENT DATE: 07/14/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 07/14/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: J. ALAN WEST |VERN HODGE NRR | |HQ OPS OFFICER: JOSEPH SEBROSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ANDERSON, GREENWOOD & CO (AGCO) OF STAFFORD, TEXAS, CALLED TO REPORT A | | PROBLEM WITH RELIEF VALVES IN ACCORDANCE WITH 10 CFR PART 21. | | | | AGCO HAS INFORMATION INDICATING THAT AGCO MODEL 81P RELIEF VALVES, IF | | ADJUSTED IN THE FIELD USING AIR AS THE TEST MEDIA, MAY NOT EXHIBIT A SET | | PRESSURE WITHIN THE SPECIFICATION TOLERANCE. THESE RELIEF VALVES ARE | | DESIGNED FOR LIQUID THERMAL RELIEF APPLICATIONS AND ARE FACTORY SET AND | | SEALED TO THE SPECIFIED SET PRESSURE USING WATER AS THE TEST MEDIA. | | | | AGCO RECOMMENDS USING WATER AS A TEST MEDIA WHEN ADJUSTMENTS ARE MADE IN | | THE FIELD; HOWEVER, THEY DO SUPPLY THEIR BUYERS WITH A PROCEDURE TO ADJUST | | THE SETPOINT OF THE VALVES WITH AIR. PRELIMINARY TESTS DONE BY AGCO SHOW | | THAT VALVES MAY EXHIBIT UP TO A 40% SET PRESSURE DEVIATION WHEN THE AIR | | METHOD IS USED. THESE TESTS ALSO INDICATE THE DEVIATION WILL BE LARGEST | | FOR LOW SET PRESSURES (100 PSI). | | | | AGCO HAS SUPPLIED MODEL 81P RELIEF VALVES TO THE FOLLOWING UTILITIES: DUKE | | POWER COMPANY, NORTHEAST UTILITIES, VIRGINIA POWER, PENNSYLVANIA POWER AND | | LIGHT, BOSTON EDISON, CENTERIOR SERVICE, NEBRASKA PUBLIC POWER DISTRICT, | | VERMONT YANKEE, OMAHA PUBLIC POWER DISTRICT, GPU NUCLEAR CORPORATION, | | GEORGIA POWER, PUBLIC SERVICE ELECTRIC AND GAS, AND ENTERGY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 07/14/95 | |UNIT: [1] [2] [ ] STATE: AR |NOTIFICATION TIME: 23:22 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 07/14/95 | +------------------------------------------------+EVENT TIME: 19:05[CDT]| |NRC NOTIFIED BY: DAN CHURCHMAN |LAST UPDATE DATE: 07/14/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO A FUNNEL CLOUD BEING SPOTTED APPROXIMATELY 2 | | MILES FROM THE SITE AND MOVING AWAY FROM THE SITE. THE NOTIFICATION WAS | | MADE TO LOCAL AGENCIES TO ALERT THEM TO THE PRESENCE OF THE FUNNEL CLOUD. | | | | THE SITE HAD SEVERE WEATHER PASS THROUGH IT EARLIER THIS EVENING. DURING | | THIS TIME, AN OPERATOR NOTICED A FUNNEL CLOUD APPROXIMATELY 2 MILE SOUTH OF | | THE PLANT. THE FUNNEL CLOUD WAS NOTED TO BE TRAVELING IN THE SOUTHWEST | | DIRECTION AWAY FROM THE PLANT. THE LICENSEE NOTIFIED POPE AND YELL COUNTY | | OFFICIALS OF THE FUNNEL CLOUD SO THAT THEY COULD TAKE ACTIONS TO PROTECT | | THE PUBLIC. THE LICENSEE ALSO NOTIFIED THE ARKANSAS STATE DEPARTMENT OF | | HEALTH. | | | | THE SEVERE WEATHER THAT PASSED THROUGH THE AREA DID CAUSE SOME MINOR WIND | | DAMAGE TO SOME OUTLYING BUILDINGS. THE LICENSEE ALSO NOTED SEVERAL | | BREAKERS CYCLING IN THE 161 KV SWITCHYARD DURING THIS TIME. THE DATA FROM | | THE METEOROLOGICAL TOWER DID SHOW WIND GUST OF UP TO 50 MILES PER HOUR FOR | | A 3 TO 4 MINUTE PERIOD. THE GRID IS CURRENTLY STABLE, AND ALL ECCS SYSTEMS | | AND EDGS ARE OPERABLE FOR BOTH UNITS. | | | | THE LICENSEE HAS NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29068 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/15/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 02:43 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/14/95 | +------------------------------------------------+EVENT TIME: 22:54[EDT]| |NRC NOTIFIED BY: WALL |LAST UPDATE DATE: 07/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN 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 | A N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECEIVED A LOW REACTOR WATER LEVEL TRIP SIGNAL WHILE IN HOT | | SHUTDOWN. | | | | THIS LOW REACTOR WATER LEVEL TRIP SIGNAL OCCURRED ALONG WITH A GROUP 2 | | (DRYWELL FLOOR AND EQUIPMENT DRAINS) OUTBOARD ISOLATION OF "1-G16-F004" AND | | "1-G16-F020" WHICH WERE OPEN PRIOR TO THE SIGNAL. THERE WAS ALSO A GROUP 6 | | DIV 2 ISOLATION OF ALL CONTAINMENT ATMOSPHERIC MONITORS AND GROUP 8 | | SHUTDOWN COOLING OUTBOARD ISOLATION. THERE WERE NO TEMPERATURE INCREASES | | IN THE REACTOR COOLANT DURING SHUTDOWN COOLING ISOLATION BECAUSE THE FLOW | | WAS NOT VALVED INTO THE RHR HEAT EXCHANGER AT THAT TIME. THE CAUSE OF THIS | | LOW REACTOR WATER LEVEL TRIP SIGNAL IS UNDER INVESTIGATION, BUT IT APPEARS | | THAT THE CAUSE MAY HAVE BEEN A HYDRAULIC PERTURBATION ON THE COMMON | | VARIABLE LEG TO REACTOR WATER LOW LEVEL CHANNEL A2 AND B2. COMPUTER TRACES | | SHOW A MOMENTARY DIP ON THESE TWO CHANNELS AT THE TIME OF THE TRIP. A | | CHANNEL CHECK OF OTHER LEVEL INSTRUMENTS CONFIRMED REACTOR WATER LEVEL | | REMAINED CONSTANT DURING THE EVENT. THE SCRAM SIGNAL ALONG WITH ALL | | ISOLATION SIGNALS WERE RESET WITHIN 26 MINS. THE RESIDENT INSPECTOR WAS | | INFORMED. | | | | NOTE SEE EVENT #29069 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29069 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/15/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 07:26 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/15/95 | +------------------------------------------------+EVENT TIME: 04:25[EDT]| |NRC NOTIFIED BY: WALL |LAST UPDATE DATE: 07/15/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN 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 | A N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECEIVED A LOW REACTOR WATER LEVEL TRIP SIGNAL WHILE IN HOT | | SHUTDOWN. (SAME AS EVENT #29068) | | | | THIS LOW REACTOR WATER LEVEL TRIP SIGNAL OCCURRED ALONG WITH A GROUP 2 | | (DRYWELL FLOOR AND EQUIPMENT DRAINS) OUTBOARD ISOLATION OF "1-G16-F004" AND | | "1-G16-F020" WHICH WERE OPEN PRIOR TO THE SIGNAL. THERE WAS ALSO A GROUP 6 | | DIV 2 ISOLATION OF ALL CONTAINMENT ATMOSPHERIC MONITORS AND GROUP 8 | | SHUTDOWN COOLING OUTBOARD ISOLATION. THERE WERE NO TEMPERATURE INCREASES | | IN THE REACTOR COOLANT DURING SHUTDOWN COOLING ISOLATION BECAUSE THE FLOW | | WAS NOT VALVED INTO THE RHR HEAT EXCHANGER AT THAT TIME. THE CAUSE OF THIS | | LOW REACTOR WATER LEVEL TRIP SIGNAL IS UNDER INVESTIGATION. IT APPEARS | | THAT THE CAUSE MAY HAVE BEEN A HYDRAULIC PERTURBATION DUE TO | | NONCONDENSIBLES IN THE SENSING LINES ON THE COMMON VARIABLE LEG TO REACTOR | | WATER LOW LEVEL CHANNEL A2 AND B2. COMPUTER TRACES SHOW A MOMENTARY DIP ON | | THESE TWO CHANNELS AT THE TIME OF THE TRIP. A CHANNEL CHECK OF OTHER LEVEL | | INSTRUMENTS CONFIRMED REACTOR WATER LEVEL REMAINED CONSTANT DURING THE | | EVENT. THE SCRAM SIGNAL ALONG WITH ALL ISOLATION SIGNALS WERE RESET WITHIN | | 7 MINS. THE RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29070 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 07/15/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 12:34 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 07/15/95 | +------------------------------------------------+EVENT TIME: 08:08[CDT]| |NRC NOTIFIED BY: BRIAN DUNGAN |LAST UPDATE DATE: 07/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP DUE TO HIGH REACTOR COOLANT SYSTEM (RCS) PRESSURE CAUSED BY | | THE MAIN TURBINE GOVERNOR VALVES CLOSING. | | | | PRIOR TO THE GOVERNOR VALVES CLOSING, THE LICENSEE HAD OPENED ONE OF THE | | TWO GENERATOR OUTPUT BREAKERS TO PERFORM SCHEDULED MAINTENANCE. THE | | MAINTENANCE WAS BEING DONE ON BREAKER 5118 TO REPAIR AN AIR SYSTEM LEAK. | | WHEN THIS BREAKER WAS OPENED, THE TURBINE GOVERNOR VALVES UNEXPECTEDLY | | BEGAN TO CLOSE. (THE REMAINING OUTPUT BREAKER (5114) IS CAPABLE OF | | HANDLING 100% OF THE RATED OUTPUT OF THE GENERATOR.) THE LICENSEE IS | | INVESTIGATING WHAT CAUSED THE TURBINE GOVERNOR VALVES TO GO CLOSED UPON THE | | OPENING OF THE GENERATOR OUTPUT BREAKER (5118). | | | | THE POST-TRIP RESPONSE WAS NORMAL. NO PRIMARY SAFETY OR PORVs OPENED. THE | | SECONDARY SAFETIES DID OPEN AND RESEATED PROPERLY. THE MAIN CONDENSER IS | | AVAILABLE AS A HEAT SINK, AND THE MAIN FEEDWATER SYSTEM IS SUPPLYING WATER | | TO THE STEAM GENERATORS. ALL RODS INSERTED AND ALL ELECTRICAL BUSSES | | TRANSFERRED AS EXPECTED. ALL ECCS SYSTEMS AND EDGS ARE OPERABLE. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29071 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 07/15/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 16:51 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/15/95 | +------------------------------------------------+EVENT TIME: 16:51[EDT]| |NRC NOTIFIED BY: BERNIE HORNING |LAST UPDATE DATE: 07/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE IS MAKING A REPORT DUE TO THE LOSS OF 12 OFFSITE EMERGENCY SIRENS. | | (SEE EVENT # 29072). | | | | THE SIRENS WERE LOST LAST NIGHT AT 04:51 WHEN SEVERE WEATHER PAST THROUGH | | THE AREA CAUSING LOSS OF POWER TO OPERATE THE SIRENS. IN ACCORDANCE WITH | | THEIR PROCEDURES, THE LICENSEE HAS 12 HOURS TO RESTORE THE SIRENS. IF THE | | SIRENS ARE NOT RESTORED IN THIS TIME FRAME, A 1-HOUR REPORT IS REQUIRED. | | OTHER THAN THE LOSS OF THE SIRENS THERE WAS NO EFFECT ON THE PLANT DUE TO | | THE SEVERE WEATHER. THE LICENSEE PLANS TO HAVE POWER RESTORED TO THE | | SIRENS SOMETIME THIS EVENING. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND THE OSWEGO COUNTY | | WARNING POINT OF THE LOSS OF THE SIRENS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29072 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 07/15/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:00 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 07/15/95 | +------------------------------------------------+EVENT TIME: 16:51[EDT]| |NRC NOTIFIED BY: JOHN WEBERS |LAST UPDATE DATE: 07/15/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS MAKING A REPORT DUE TO THE LOSS OF 12 OFFSITE EMERGENCY | | SIRENS. ALSO SEE EVENT # 29071. | | | | THE SIRENS LOST POWER DUE TO SEVERE WEATHER. THE LICENSEE HAS INFORMED THE | | RESIDENT INSPECTOR AND THE OSWEGO COUNT WARNING POINT OF THE LOSS OF THE | | SIRENS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29073 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 07/16/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 06:40 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/16/95 | +------------------------------------------------+EVENT TIME: 06:30[EDT]| |NRC NOTIFIED BY: DENNIS |LAST UPDATE DATE: 07/16/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAD LOST 16 OF 71 OFF SITE EMERGENCY | | SIRENS. | | | | THIS WAS CAUSED BY A THUNDERSTORM WHICH PASSED THROUGH THE AREA AND TOOK | | OUT POWER TO THESE SIRENS. THREE OF THE SIRENS ARE IN DELAWARE, AND | | THIRTEEN ARE IN NEW JERSEY. THE LICENSEE WAS NOTIFIED THAT THE SIRENS | | SHOULD BE BACK IN SERVICE BY 09:00. THIS REPORT IS ALSO BEING MADE FOR | | SALEM UNITS 1 AND 2, AND THEY WILL NOT BE CALLING IN THE EVENT. THE | | RESIDENT INSPECTOR WILL BE NOTIFIED, AND STATE AND LOCAL AGENCIES HAVE BEEN | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29074 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 07/16/95 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 12:37 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/16/95 | +------------------------------------------------+EVENT TIME: 09:15[EDT]| |NRC NOTIFIED BY: JAMES JOHNSTONE |LAST UPDATE DATE: 07/16/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM RANKIN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH TRAINS OF SAFEGUARDS VENTILATION FOUND TO BE INOPERABLE. TECH SPEC | | 3.0.3 WAS ENTERED BRIEFLY. | | | | TRAIN "A" OF SAFEGUARDS VENTILATION HAD BEEN TAGGED OUT FOR MAINTENANCE, A | | SEVEN-DAY LCO. THE LICENSEE THEN DETERMINED THAT THE "B" TRAIN BECAME | | INOPERABLE AS A RESULT OF ONE OF THE MAINTENANCE ACTIVITIES ONGOING ON | | TRAIN "A". AN INSPECTION PORT IN DUCT WORK IN THE AUXILIARY BUILDING HAD | | BEEN OPENED FOR ACCESS NEEDED FOR THE TRAIN "A" WORK. THIS DUCT PROVIDES A | | SUCTION PATH FROM THE SAFEGUARDS BUILDING TO BOTH TRAIN'S VENTILATION FANS. | | | | WITH THE PORT OPEN SUCTION FLOW COULD BE FROM BOTH THE AUXILIARY BUILDING | | AND THE SAFEGUARDS BUILDING. THE RESULTANT REDUCTION IN FLOW FROM THE | | SAFEGUARDS BUILDING TO THE HEPA FILTERS WAS BELOW TECH SPEC LIMITS. | | THEREFORE, TRAIN "B" WAS CONSIDERED INOPERABLE WHILE THE INSPECTION PORT | | WAS OPEN, AND THE UNIT WAS IN TECH SPEC 3.0.3 FOR ONE HALF HOUR UNTIL THE | | PORT WAS REPLACED. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+