Nuclear Power Plant Daily Events 1/20-1/21/2000

greenspun.com : LUSENET : Grassroots Information Coordination Center (GICC) : One Thread

Daily Events Report U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/20/2000 - 01/21/2000 ** EVENT NUMBERS ** 36595 36607 36608 36609 36610 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------------------------+ |Hospital |Event Number: 36595 | +----------------------------------------------------+ +----------------------------------------------------+ | REP ORG: VA COMMONWEALTH UNIV. HOSPITAL |NOTIFICATION DATE: 01/16/2000| |LICENSEE: VA COMMONWEALTH UNIV. HOSPITAL |NOTIFICATION TIME: 10:15[EST]| | CITY: RICHMOND REGION: 2 |EVENT DATE: 01/15/2000| | COUNTY: STATE: VA |EVENT TIME: 15:30[EST]| |LICENSE#: 45-00048-17 AGREEMENT: N |LAST |UPDATE DATE: 01/20/2000| | DOCKET: |+---------------------+ | |PERSON ORGANIZATION | | |ROBERT HAAG R2 | | |CHARLEY HAUGHNEY NMSS | +-------------------------+ | | NRC NOTIFIED BY: MARY BETH TAORMINA | | | HQ OPS OFFICER: BOB STRANSKY | | +-------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | MEDICAL MISADMINISTRATION | | | | A patient received a 30% underdose after one of four | strands of Ir-192 seeds | | became dislodged immediately following implantation. | The activity of the | | strands was 7.5 mCi, 8.7 mCi, 6.0 mCi, and 7.6 mCi. | (The licensee did not | | specify which strand became dislodged.) The strand | was removed from the | patient's bed shortly | thereafter when the linen was changed. The licensee | is | | currently reconstructing this event but does not | believe that any employee | | received a significant dose. | | | | (Call the NRC operations office for a contact | telephone number.) | | | | * * * UPDATE 0838 EST ON 1/20/00 FROM MARY BETH | TAORMINA TO S. SANDIN * * | | * | | | | The licensee is retracting this report based on a | re-evaluation of the | | patient treatment plan which concluded that the | underdose was 15% and, as | | such, did not meet the 20% criteria for a | misadministration. This finding | was discussed | with Region 2. Notified R2DO (Fredrickson) and NMSS | (Moore). | +----------------------------------------------------+ +----------------------------------------------------+ |Power Reactor |Event Number: 36607 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 01/18/2000| | UNIT: [1] [2] [] STATE: IL |NOTIFICATION TIME: 19:15[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/18/2000| +----------------------+EVENT TIME: 18:02[CST]| | NRC NOTIFIED BY: R. T. THORTON |LAST | UPDATE DATE: 01/20/2000| | HQ OPS OFFICER: LEIGH TROCINE +----------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DAVID HILLS R3 | |10 CFR SECTION: |ROBERTA WARREN IAT | |DDDD 73.71 UNSPECIFIED PARAGRAPH |JIM CREED IAT | | |JIM BELANGER IAT | | |DICK ROSANO IAT | | |STEVE REYNOLDS R3 | +-----+------+-------+-------+-------+-------+-------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+------+-------+-------+-------+-------+-------+ |1 N N 0 Decommissioned |0 Decommissioned | |2 N N 0 Decommissioned |0 Decommissioned | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | SECURITY REPORT | | | | UNSUBSTANTIATED BOMB THREAT. COMPENSATORY MEASURES | TAKEN. LICENSEE | | INFORMED THE LOCAL POLICE DEPARTMENT. | +----------------------------------------------------+ +----------------------------------------------------+ |Power Reactor |Event Number: 36608 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 01/20/2000| | UNIT: [] [] [3] STATE: CA |NOTIFICATION TIME: 17:31[EST]| | RXTYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 01/20/2000| +----------------------+EVENT TIME: 14:00[PST]| | NRC NOTIFIED BY: WILLIAMS |LAST | UPDATE DATE: 01/20/2000| | HQ OPS OFFICER: CHAUNCEY GOULD +---------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LINDA SMITH R4 | |10 CFR SECTION: | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+------+-------+-------+-------+-------+-------+ |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 +----------------------------------------------------+ | CABLES AND CONDUITS IN THE SALT WATER COOLING PIPE | TUNNEL FOUND WITHOUT A | | PORTION OF THEIR FIRE WRAPS. | | | | ON 1/19/00, FOLLOWING A PLANT WALKDOWN, IT WAS | DISCOVERED THAT SOME CABLES | AND CONDUITS IN THE | SALT WATER COOLING PIPE TUNNEL WERE MISSING | PORTIONS OF | | THEIR FIRE WRAPS. AFTER REVIEW OF PLANT | DOCUMENTATION, IT WAS DETERMINED | | THAT THIS CONDITION AFFECTED BOTH TRAIN "A" AND "B" | SALT WATER COOLING | PUMPS FOR UNIT 3. | CONSEQUENTLY ON 1/20/00 @ 1400 PST IT WAS CONCLUDED | THIS | CONDITION DID NOT MEET THE REQUIREMENTS OF | APPENDIX "R" TO ASSURE ONE TRAIN | | OF SAFE SHUTDOWN EQUIPMENT FREE OF FIRE DAMAGE IN | THE EVENT OF A DESIGN | | BASIS FIRE. | | | | THE LICENSEE IMMEDIATELY ENSURED THAT A ROVING FIRE | WATCH HAD BEEN | | POSTED(AND WAS ALREADY IN PLACE FOR OTHER UNRELATED | REASONS). THIS ACTION | | SATISFIED THEIR LCO ACTION STATEMENT REQUIREMENT. | | | | IN THE EVENT OF A FIRE, PLANT OPERATORS WOULD HAVE | BEEN ABLE TO RESTORE | POWER TO THE SALT WATER | COOLING SYSTEM(BY ISOLATING THE AFFECTED CABLES AND | | | STARTING A PUMP FROM ITS SECOND POINT OF CONTROL). | ADDITIONALLY, THE | | COMBUSTIBLE LOADING IN THE AFFECTED AREA IS | EXTREMELY LOW(2 MINUTE FIRE | | DURATION), AND THAT AREA IS PROTECTED BY FIRE | SPRINKLERS AND FIRE | | DETECTORS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +----------------------------------------------------+ +----------------------------------------------------+ |Power Reactor |Event Number: 36609 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 01/20/2000| | UNIT: [] [2] [] STATE: PA |NOTIFICATION TIME: 19:05[EST]| | RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/20/2000| +----------------------+EVENT TIME: 18:17[EST]| | NRC NOTIFIED BY: HYNES |LAST | UPDATE DATE: 01/20/2000| | HQ OPS OFFICER: CHAUNCEY GOULD +---------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |FELICIA HINSON 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 | +-----+------+-------+-------+-------+-------+-------+ | | | |2 N Y 100 Power Operation |100 Power Operation | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | INADEQUATE SHORT CIRCUIT PROTECTION ON CONTROL | WIRING ASSOCIATED WITH THE | | LINE STARTER FOR MAIN TURBINE DRAIN VALVES | | | | While performing a design analysis on Beaver Valley | Unit 2 (BV-2) to confirm | | adequate electrical fault protection, as follow-up | to an Engineering fire | protection | self-assessment completed in May 1999, it was | determined that the | | control wiring associated with the line starter for | the nine main turbine | | drain valves is not adequately protected from short | circuits. This | protection inadequacy | results from a lack of required fuse protection | and/or | | current limiting features described in Section | 9.5.A.1.2.1.5(4) of the | Updated Final Safety | Analysis Report. Due to this lack of adequate | current | | limiting protection, an electrical fault on this | circuit could result in a | fire in multiple fire | areas including the common Unit 1/2 Control Room, | BV-2 | | Service Building, BV-2 Cable Vault, BV-2 Cable | Tunnel, and BV-2 Turbine | | Building. The lack of current limiting protection | for this circuitry | | introduces the possibility of a potential fire in | these multiple areas, | | which is a violation of fire protection licensing | basis commitments | | regarding safe shutdown capability. | | | | The subject main turbine drain valves are non-safety | related and not | | required for safe shutdown. As an interim measure, | the circuit has been | | de-energized and will remain de-energized until | adequate electrical | | protection can be provided. | | | | The NRC Resident Inspector was notified. | +----------------------------------------------------+ +----------------------------------------------------+ |Power Reactor |Event Number: 36610 | +----------------------------------------------------+ +----------------------------------------------------+ | FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 01/21/2000| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 04:21[EST]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 01/21/2000| +----------------------+EVENT TIME: 02:39[CST]| | NRC NOTIFIED BY: JOHN SELL |LAST | UPDATE DATE: 01/21/2000| | HQ OPS OFFICER: STEVE SANDIN +----------+ +----------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |DAVID HILLS R3 | |10 CFR SECTION: | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+------+-------+-------+-------+-------+-------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+------+-------+-------+-------+-------+-------+ |1 M/R Y 40 Power Operation |0 Hot Standby | | | | | | | +----------------------------------------------------+ EVENT TEXT +----------------------------------------------------+ | UNIT 1 MANUALLY TRIPPED FROM 40% POWER DUE TO A | DECREASING FOREBAY LEVEL | | | | "UNIT 1 WAS MANUALLY TRIPPED FROM 40% POWER AFTER AN | ANTICIPATORY POWER | | REDUCTION AT 0239CST DUE TO DECREASING LEVEL IN THE | CIRC. WATER INLET | | FOREBAY. DECREASING LEVEL WAS APPARENTLY DUE TO | ICING OF THE INTAKE | STRUCTURE. UNIT 1 | CIRC. WATER SYSTEM HAS BEEN SECURED AND FOREBAY | LEVEL HAS | | INCREASED. THE UNIT 1 CIRC. WATER SYSTEM WAS | SECURED TO MAINTAIN | | OPERABILITY OF THE SERVICE WATER SYSTEM. UNIT 2 | REMAINS AT 100% POWER AND | | IS STABLE." | | | | FOREBAY LEVEL HAD DECREASED TO -11 FT FROM THE | NORMAL OPERATING -8 FT. THE | -11 FT CORRESPONDS | TO THE MINIMUM DESIGN LIMIT FOR THE SERVICE WATER | SYSTEM. | CURRENTLY, LEVEL IS -6 FT 4 INCHES. STEAM | GENERATORS USING THE ATMOSPHERIC | DUMPS ARE | PROVIDING THE HEAT SINK FOR DECAY HEAT REMOVAL SINCE | THE CONDENSER | | IS NOT IN SERVICE. ALL CONTROL RODS FULLY INSERTED | FOLLOWING THE MANUAL | | TRIP. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | + +----------------------------------------------------+

-- B. Blakely (LeeeeeeB@webtv.net), January 21, 2000

Moderation questions? read the FAQ