Event Notification Report for May 24, 1999
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/21/1999 - 05/24/1999 ** EVENT NUMBERS ** 35644 35744 35746 35749 35750 35751 35752 35753 35754 35755 35756 35757 35758 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35644 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/27/1999| | UNIT: [1] [2] [] STATE: CA |NOTIFICATION TIME: 22:14[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/27/1999| +------------------------------------------------+EVENT TIME: 18:45[PDT]| | NRC NOTIFIED BY: RODERTO ARROYO |LAST UPDATE DATE: 05/21/1999| | HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DAVID GRAVES R4 | |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 50 Power Operation |50 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A SAFEGUARDS SYSTEM DEGRADATION RELATED TO A VITAL AREA | | BARRIER | | | | Security personnel discovered a safeguard system degradation related to the | | vital area barrier. Immediate compensatory actions were taken upon | | discovery. (Contact the NRC Operations Officer for additional details and | | for a licensee contact telephone number.) | | | | The licensee notified the NRC Resident Inspector. | | | | * * * UPDATE AT 1746 ON 05/26/99 BY JOHN HUBBLE TO JOLLIFFE * * * | | | | The licensee is retracting this event since adequate compensatory measures | | were already in place when this degradation was discovered. (Contact the | | NRC Operations Officer for additional details.) | | | | The licensee plans to notify the NRC Resident Inspector. | | | | The NRC Operations Officer notified the R4DO Gary Sanborn. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35744 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/20/1999| | UNIT: [] [] [3] STATE: CT |NOTIFICATION TIME: 10:23[EDT]| | RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/20/1999| +------------------------------------------------+EVENT TIME: 10:14[EDT]| | NRC NOTIFIED BY: BRADSKY |LAST UPDATE DATE: 05/21/1999| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | |3 N N 0 Refueling |0 Refueling | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FAILURE OF BOTH SAFETY RELATED CONTAINMENT CUBICAL SUMP AIR DRIVEN PUMPS | | - | | | | ON 5/16/99 DURING THE 18 MONTH SURVEILLANCE FOR THE SAFETY RELATED | | CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS, BOTH PUMPS FAILED | | TO DISCHARGE WATER FROM THE SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES | | BUILDING. A REVISION TO THE SURVEILLANCE TO INCREASE THE AIR PRESSURE TO | | THE PUMPS WAS APPROVED ON 5/19/99. ON 5/19/99, BOTH AIR DRIVEN PUMPS WERE | | DECLARED INOPERABLE WHEN PUMP DAS*P15A FAILED TO DISCHARGE WATER FROM THE | | SUMPS TO OUTSIDE THE ENGINEERING SAFETY FEATURES BUILDING WITH THE INCREASED | | AIR PRESSURE. | | | | THE SAFETY RELATED CONTAINMENT RECIRCULATION CUBICAL SUMP AIR DRIVEN PUMPS | | ARE REQUIRED FOLLOWING A LOCA WHEN THE ENGINEERING SAFETY FEATURES BUILDING | | IS INACCESSIBLE DUE TO HIGH DOSE RATES IN THE BUILDING. THE PLANT IS | | CURRENTLY IN A REFUELING OUTAGE AND THE NON-SAFETY RELATED CONTAINMENT | | RECIRCULATION CUBICAL SUMP PUMPS ARE FUNCTIONAL. | | | | THE CAUSE OF THE EVENT IS CURRENTLY UNDER INVESTIGATION. AT THIS TIME, IT | | IS HYPOTHESIZED THAT THE AIR CHAMBER OF THE PUMPS ARE FLOODED WITH | | LUBRICATING OIL WHICH REDUCES THEIR CAPABILITIES TO PUMP WATER. | | | | THE RESIDENT INSPECTOR WAS INFORMED. | | | | *** UPDATE ON 5/21/99 @ 0838 BY MARTIN TO GOULD *** | | | | THE DATE BOTH AIR DRIVEN PUMPS WERE DECLARED INOPERABLE WAS 5/20/99 INSTEAD | | OF 5/19/99 AS REPORTED IN THE INITIAL REPORT. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. REG 1 RDO (ESELGROTH) WAS INFORMED. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35746 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/20/1999| | UNIT: [] [3] [] STATE: NY |NOTIFICATION TIME: 14:23[EDT]| | RXTYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 12/01/1975| +------------------------------------------------+EVENT TIME: 12:00[EDT]| | NRC NOTIFIED BY: TOM McKEE |LAST UPDATE DATE: 05/21/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |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 Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - COMPONENT COOLING WATER PIPING IS RUN INSIDE A CRANE WALL (NOT MISSILE | | PROTECTED) - | | | | During a 10CFR50.54(f) review of the UFSAR, the licensee discovered a | | certain component cooling water (CCW) piping run inside a crane wall (i.e., | | not missile protected from LOCA generated missiles by the crane wall) [DER | | 99-0840]. After searching plant records, the licensee has not located any | | initial engineering documentation justifying the running of piping inside | | the crane wall. Based on this review, the licensee has concluded that the | | CCW piping may have been outside the system design basis stated in the UFSAR | | since original operation of the plant in December 1975. The licensee | | believes that the design requirement (i.e., protected from LOCA generated | | missiles) for the system was restored in March 1986 based on the NRC Safety | | Evaluation for Generic Safety Issue A-2. The Safety Evaluation Report (SER) | | states, in part, that "dynamic effects associated with postulated pipe | | breaks in the primary coolant system of this facility need not be a design | | basis." | | | | The licensee has declared the CCW piping operable based on the 1986 SER and | | is continuing to reconcile the design basis of this issue using the | | 10CFR50.59 process. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35749 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: L.A. COUNTY DEPT OF HEALTH SERVICES |NOTIFICATION DATE: 05/21/1999| |LICENSEE: KAISER PERMANENTE MED CARE PROGRAM |NOTIFICATION TIME: 11:15[EDT]| | CITY: LOS ANGELES REGION: 4 |EVENT DATE: 04/23/1999| | COUNTY: STATE: CA |EVENT TIME: 12:00[PDT]| |LICENSE#: 0372-19 AGREEMENT: Y |LAST UPDATE DATE: 05/21/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |GARY SANBORN R4 | | |LARRY CAMPER NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: STEPHEN DOERFLER | | | HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THERAPEUTIC MEDICAL MISADMINISTRATION AT KAISER PERMANENTE MEDICAL CARE | | PROGRAM OF SOUTHERN CALIFORNIA. | | | | A PATIENT WAS SCHEDULED FOR THREE THERAPEUTIC TREATMENTS FOR CANCER OF THE | | CERVIX USING THE HIGH DOSE RATE AFTERLOADER. PRIOR TO THE INITIATION OF THE | | FIRST TREATMENT ON 04/23/99, THE AUTHORIZED USER MADE A "LAST MINUTE" CHANGE | | IN THE TREATMENT PLAN WITH RESPECT TO THE SOURCE TRAVEL DISTANCE. AFTER THE | | CHANGE WAS MADE, THE SETUP CALLED FOR THE SOURCE TO BEGIN AT 989 | | MILLIMETERS. THE PHYSICIST, HOWEVER, SET UP THE UNIT SO THAT THE SOURCE | | BEGAN ITS TRAVEL AT 889 MILLIMETERS. PRIOR TO INITIATION OF THE TREATMENT, | | THE AUTHORIZED USER, PHYSICIST, AND TECHNOLOGIST SIGNED OFF ON THIS | | TREATMENT PLAN. THE PATIENT WAS THEN TREATED. THE SOURCE TRAVEL DISTANCE | | WAS 100 MILLIMETERS SHORTER THAN THE TREATMENT PLAN REQUIRED, AND DIFFERENT | | FROM THAT INTENDED. IT WAS NOT NOTED DURING OR AFTER COMPLETION OF THIS | | TREATMENT. | | | | THE SECOND TREATMENT OCCURRED ON 04/30/99. A SECOND PHYSICIST, WITHOUT | | VERIFYING THE ACCURACY OF THE FIRST TREATMENT, SET UP THE SECOND TREATMENT | | USING THE SAME PARAMETERS, A TRAVEL DISTANCE OF 894 MILLIMETERS. THE | | AUTHORIZED USER, PHYSICIST, AND TECHNOLOGIST SIGNED OFF ON THE SECOND | | TREATMENT PLAN. THE TREATMENT WAS ADMINISTERED TO A DIFFERENT LOCATION THAN | | INTENDED. THE ERROR WAS NOT NOTED PRIOR TO, DURING, OR AFTER THIS | | TREATMENT. | | | | THE THIRD TREATMENT PERFORMED ON 05/07/99 BY A THIRD PHYSICIST WHO SET UP | | THE PARAMETERS CORRECTLY, AS PLANNED (TRAVEL DISTANCE OF 994 MILLIMETERS) | | WAS COMPLETED WITHOUT INCIDENT. | | | | THE THIRD PHYSICIST PERFORMED A CHART REVIEW ON 05/11/99 AND FOUND THE ERROR | | IN THE 04/23/99 AND 04/30/99 TREATMENTS AND NOTIFIED THE RADIATION THERAPY | | ADMINISTRATOR AND CHIEF OF SERVICE. | | | | THE REGIONAL RADIATION SAFETY OFFICER (RSO) WAS NOTIFIED ON 05/17/99 BY THE | | SITE RSO IN VIOLATION OF THE REQUIRED 4 HOUR NOTIFICATION TIME. | | | | THE PATIENT AND HIS REFERRING PHYSICIAN WERE NOTIFIED OF THIS INCIDENT ON | | 05/18/99. | | | | A COMPLETE INVESTIGATION OF THESE INCIDENTS, INCLUDING A DOSE ASSESSMENT, | | AND THE DEVELOPMENT OF AN ACTION PLAN TO PREVENT FURTHER OCCURRENCES WILL BE | | MADE. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35750 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/21/1999| | UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 13:38[EDT]| | RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 05/21/1999| +------------------------------------------------+EVENT TIME: 09:39[CDT]| | NRC NOTIFIED BY: WAYNE AHO |LAST UPDATE DATE: 05/21/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GARY SANBORN R4 | |10 CFR SECTION: | | |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 Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM ISOLATION & EMERGENCY VENTILATION/FILTRATION SYSTEM (CREVS) | | ACTUATION | | | | A Health Physics Technician was transporting a spent fuel pool purification | | filter in the vicinity of the radiation detectors for the CREVS system. The | | filter had a contact reading of 131 mrem/hour, and 45.4 mrem/hour at 30 cm. | | The actuated radiation detector, #2RITS-8750-1B, has a setpoint of 140 | | counts per minute., This filter was placed near the detector, causing the | | actuation. | | | | This is not the normal transport path for contaminated filters. The filter | | was triple-bagged, but developed a leak during transport. The Health | | Physics Technician decided to place the filter in a barrel that is normally | | used for torn protective clothing, to prevent the spread of contamination. | | This barrel is in the vicinity of the control room ventilation radiation | | detectors. | | | | At 1035 CDT, the control room ventilation system was returned to normal. | | | | Unit 1 was unaffected by this event. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35751 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 05/21/1999| | UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 13:53[EDT]| | RXTYPE: [1] W-3-LP |EVENT DATE: 05/21/1999| +------------------------------------------------+EVENT TIME: 10:16[EDT]| | NRC NOTIFIED BY: MARK ELLINGTON |LAST UPDATE DATE: 05/21/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |ANN BOLAND R2 | |10 CFR SECTION: | | |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 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT START OF THE 'B' CONTAINMENT SPRAY PUMP DUE TO AN INVALID START | | SIGNAL | | | | While performing the test of the Sequencer Block Circuit and Containment Fan | | Cooler, Train 'B' (#OST- 1095) with the plant at 100% power, a maintenance | | technician placed multimeter leads on the wrong terminal points. These | | terminal points were adjacent to the desired points. This caused an | | inadvertent start of the 'B' Containment Spray Pump. This invalid actuation | | was the result of an invalid signal generated by the maintenance technician. | | Investigation indicates that no other components actuated. | | | | The pump was aligned in standby and no flow was admitted to containment. | | The pump operated for approximately two minutes with adequate recirculation | | flow before it was secured. No equipment damage occurred and the 'B' | | Containment Spray system is currently operable. The licensee has | | conservatively determined that the pump start constitutes an ESF actuation. | | | | The NRC Resident Inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35752 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 05/21/1999| | UNIT: [2] [] [] STATE: MI |NOTIFICATION TIME: 15:02[EDT]| | RXTYPE: [2] GE-4 |EVENT DATE: 05/21/1999| +------------------------------------------------+EVENT TIME: 10:14[EDT]| | NRC NOTIFIED BY: STEVE MAREK |LAST UPDATE DATE: 05/21/1999| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BRENT CLAYTON R3 | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 15 Power Operation |15 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 hour License Condition 2.C.(9) report concerning non-compliance with the | | approved fire protection program. | | | | During a design calculation review, plant engineering department personnel | | discovered that cable routing for safety/relief valve (SRV) 'G' is not in | | compliance with Appendix R design assumptions for cable separation. The SRV | | is used in the dedicated shutdown procedure to control reactor pressure and | | to depressurize the plant so that a cold shutdown condition can be achieved | | within 10 hours after plant shutdown (UFSAR commitment). An hourly fire | | watch has been established in the affected zone, pending an evaluation by | | engineering department personnel. | | | | The NRC Resident Inspector has been notified of this event notification by | | the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35753 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/21/1999| | UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 22:40[EDT]| | RXTYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/21/1999| +------------------------------------------------+EVENT TIME: 20:46[CDT]| | NRC NOTIFIED BY: RON RUSTICK |LAST UPDATE DATE: 05/22/1999| | HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BRENT CLAYTON R3 | |10 CFR SECTION: | | |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 Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNIT 1 SCRAMMED FROM 100% POWER DUE TO A SCRAM DISCHARGE VOLUME HIGH LEVEL | | SIGNAL - | | | | AT 2046 CDT ON 05/21/99, UNIT 1 RECEIVED A 'B' HALF SCRAM SIGNAL DUE TO A | | SCRAM DISCHARGE VOLUME HIGH LEVEL SIGNAL. APPROXIMATELY 45 SECONDS LATER, | | UNIT 1 RECEIVED A FULL SCRAM SIGNAL DUE TO A SCRAM DISCHARGE VOLUME HIGH | | LEVEL SIGNAL. THE REACTOR SCRAMMED FROM 100% POWER DUE TO A VALID SCRAM | | DISCHARGE VOLUME HIGH LEVEL SIGNAL POSSIBLY DUE TO A LEAKING VALVE ON A | | SCRAM DISCHARGE VOLUME HYDRAULIC CONTROL UNIT. | | | | ALL CONTROL RODS INSERTED COMPLETELY. NO SAFETY/RELIEF VALVES LIFTED. | | DECAY HEAT IS BEING DISSIPATED VIA THE STEAM JET AIR EJECTORS AND AUXILIARY | | LOADS. UNIT 1 PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 (STANDBY GAS | | TREATMENT SYSTEM) AND GROUP 3 (REACTOR WATER CLEANUP SYSTEM) ACTUATED. UNIT | | 1 IS STABLE IN OPERATIONAL CONDITION 3 (HOT SHUTDOWN). THE LICENSEE IS | | INVESTIGATING THE CAUSE OF THE SCRAM DISCHARGE VOLUME HIGH LEVEL SIGNALS. | | | | THIS EVENT HAD NO EFFECT ON UNIT 2 WHICH IS OPERATING AT 100% POWER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0800 EDT ON 5/22/99 BY RON RUSTICK TO FANGIE JONES * * * | | | | In review of the event it was noted that the Unit 1 diesel generator | | auto-started on the transfer of auxiliary power, an ESF actuation. | | | | It is also believed that a reactor water cleanup system relief valve lifted, | | pressurizing the reactor building drain tank and forcing backflow to fill up | | the scram discharge volume causing the reactor scram. | | | | The licensee informed the NRC Resident Inspector. The Headquarters | | Operations Officer informed the R3DO (Brent Clayton). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35754 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/22/1999| | UNIT: [2] [3] [] STATE: PA |NOTIFICATION TIME: 01:56[EDT]| | RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/21/1999| +------------------------------------------------+EVENT TIME: 22:20[EDT]| | NRC NOTIFIED BY: JIM KOVALCHICK |LAST UPDATE DATE: 05/22/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |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 Y 100 Power Operation |100 Power Operation | |3 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION DUE TO UNEXPECTED POWER LOSS | | | | "At 2220 [EDT] on 5/21/99 two of four 4 kVolt emergency electrical buses on | | Unit 2 and Unit 3 fast transferred to the alternate offsite feed when the | | normal offsite feed unexpectedly deenergized during switching operations. | | The momentary power loss that occurred during the fast transfer unexpectedly | | deenergized control logics that resulted in the following invalid Primary | | Containment Isolation System Isolation actuations: | | | | Unit 2 | | a) Outboard isolation of Drywell Instrument Nitrogen System | | b) Outboard isolation of Reactor Water Cleanup System | | c) Outboard isolation of Drywell Sump System | | | | Unit 3 | | a) Inboard isolation of Drywell Instrument Nitrogen System | | b) Inboard isolation of Drywell Sump System | | c) Full Reactor Water Cleanup System isolation | | d) Inboard isolation Containment Atmosphere Sampling System | | | | "The cause of the loss of feed is under investigation. Both units remain at | | 100 % power." Power has been restored to the normal offsite feed, but the | | busses are not being transferred back until the cause of the loss of power | | is determined. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35755 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/22/1999| | UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 05:10[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/22/1999| +------------------------------------------------+EVENT TIME: 03:15[CDT]| | NRC NOTIFIED BY: DENNIS HIGINBOLHAM |LAST UPDATE DATE: 05/22/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |BRENT CLAYTON R3 | |10 CFR SECTION: | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 60 Power Operation |60 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROCESS COMPUTER OUT-OF-SERVICE FOR PLANNED MAINTENANCE | | | | The Plant Process Computer was placed out-of-service for modification to a | | inverter power supply and temporary power was not available. This also | | placed the Safety Parameter Display System (SPDS) and the ability to link to | | the Emergency Response Data System (ERDS) out-of-service. | | | | Preparations for full restoration is in progress and it is expected to be | | complete by 0600 CDT. | | | | The licensee plans to notify the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35756 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 05/22/1999| | UNIT: [] [2] [] STATE: TX |NOTIFICATION TIME: 09:40[EDT]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/22/1999| +------------------------------------------------+EVENT TIME: 07:15[CDT]| | NRC NOTIFIED BY: GREGORY BRYAN |LAST UPDATE DATE: 05/22/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GARY SANBORN R4 | |10 CFR SECTION: | | |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 Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE 'A' SAFEGUARDS BUS DEENERGIZED CAUSING THE DIESEL GENERATOR TO START AND | | REENERGIZE IT | | | | The Train 'A' Safeguards 6.9 kV electrical bus experienced a lockout relay | | actuation (due to a neutral ground overcurrent). The diesel generator | | (2-01) started and energized the bus. The Blackout Sequencer actuated and | | restored the safeguards equipment on the affected bus. The ESF equipment | | that actuated included the 'A' Train Control Room HVAC, motor driven | | Auxiliary Feedwater Pump, turbine driven Auxiliary Feedwater Pump ( 'A' | | Train only), and the Blackout Sequencer. | | | | The unit entered the abnormal procedure to respond to the loss of the normal | | power supply to the Train 'A' Bus and restore from the Blackout Sequencer. | | | | | | The cause of the relay actuation is under investigation and the diesel | | generator will continue to power the bus until it is determined what caused | | the actuation. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 35757 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: MEAD PAPER CORPORATION |NOTIFICATION DATE: 05/22/1999| |LICENSEE: MEAD PAPER CORPORATION |NOTIFICATION TIME: 12:01[EDT]| | CITY: CHILLICOTHE REGION: 3 |EVENT DATE: 05/22/1999| | COUNTY: STATE: OH |EVENT TIME: 07:10[EDT]| |LICENSE#: 34-06188-09 AGREEMENT: N |LAST UPDATE DATE: 05/22/1999| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |BRENT CLAYTON R3 | | |CHARLEY HAUGHNEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM SEGELHORST, RSO | | | HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - OHMART DENSITY GAUGE (20 MILLICURIES Cs-137 SOURCE) IN A FIRE AT A PAPER | | PLANT - | | | | AT 0710 ON 05/22/99, A FIRE OCCURRED IN A WOOD CHIP CONVEYOR, POSSIBLY DUE | | TO A SEIZED BEARING, AT THE MEAD PAPER CORPORATION FACILITY IN CHILLICOTHE, | | OH. THE LOCAL FIRE DEPARTMENT WAS CALLED AND RESPONDED TO THE FIRE, WHICH | | WAS EXTINGUISHED WITHIN APPROXIMATELY 15 MINUTES. A OHMART DENSITY | | GAUGE(MODEL #SH1-00PS), WHICH IS INSTALLED IN THE AREA OF THE FIRE, HAD ITS | | OUTER CASE CHARRED AND SLIGHTLY DAMAGED. THE GAUGE, WHICH CONTAINS A 20 | | MILLICURIE CESIUM-137 RADIATION SOURCE, APPEARS NOT TO BE DAMAGED. | | | | JIM SEGELHORST, MEAD PAPER CORPORATION RADIATION SAFETY OFFICER (RSO) | | MEASURED THE SOURCE AND OBTAINED NORMAL READINGS AT A DISTANCE OF | | APPROXIMATELY ONE FOOT. THE RSO BARRICADED THE AREA AROUND THE GAUGE TO | | ISOLATE IT FROM PERSONNEL. A OHMART REPRESENTATIVE IS ON HIS WAY TO THE | | SITE AND PLANS TO TAKE POSSESSION OF THE GAUGE AROUND 1500 AND SHIP IT BACK | | TO THE MANUFACTURER. NO PERSONNEL WERE EXPOSED TO RADIATION. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35758 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 05/23/1999| | UNIT: [2] [] [] STATE: PA |NOTIFICATION TIME: 09:30[EDT]| | RXTYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 05/23/1999| +------------------------------------------------+EVENT TIME: 08:53[EDT]| | NRC NOTIFIED BY: CAMERON CAMPBELL |LAST UPDATE DATE: 05/23/1999| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PETER ESELGROTH R1 | |10 CFR SECTION: | | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |2 N Y 100 Power Operation |100 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM OUT OF SERVICE DUE TO PLANNED MAINTENANCE | | | | The safety parameter display system (SPDS) was placed out of service due to | | planned computer maintenance. Outage on the plant monitoring system | | computer will disable SPDS for up to 24 hours. Operators are taking | | compensatory measures for monitoring parameters. | | | | The licensee has notified the NRC resident inspector. | | | | ******************** UPDATE AT 2049 ON 05/23/99 FROM SCOTT PABIS TO LEIGH | | TROCINE ******************** | | | | The planned computer maintenance outage has been completed, and SPDS was | | returned to service at 2026. | | | | The licensee plans to notify the NRC resident inspector of this update. The | | NRC operations officer notified the R1DO (Eselgroth). | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021