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Event Notification Report for January 2, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 12/31/2001 - 01/02/2002 ** EVENT NUMBERS ** 38599 38600 38601 38602 38603 38604 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38599 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 12/31/2001| | UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 02:00[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/31/2001| +------------------------------------------------+EVENT TIME: 00:10[EST]| | NRC NOTIFIED BY: S. SAUER |LAST UPDATE DATE: 12/31/2001| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |MICHELE EVANS R1 | |10 CFR SECTION: | | |ACCS 50.72(b)(2)(iv)(A) ECCS INJECTION | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 AND SAFETY INJECTION DUE TO SPRAY VALVE FAILING OPEN | | | | The unit experienced a reactor trip and safety injection as a result of a | | pressurizer spray valve (2PS3) failing open. This caused a reactor trip on | | Overtemperature DeltaT and a safety injection on low reactor coolant system | | pressure. All emergency equipment responded properly, all safety injection | | pumps started and all control rods fully inserted. The emergency diesels | | started, but were not required to load. The auxiliary feedwater pumps | | started on low steam generator level. The pressurizer spray valve closed | | when the valve's operating air was isolated. | | | | The unit is stable in Mode 3 (Hot Standby) at normal temperature and | | pressure. Auxiliary feedwater and steam dumps are in use to maintain steam | | generator level and remove excess heat. An investigation of the failure is | | underway. | | | | The licensee intends to notify the NRC Resident Inspector and the local | | Township. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38600 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 01/01/2002| | UNIT: [1] [] [] STATE: OH |NOTIFICATION TIME: 03:19[EST]| | RXTYPE: [1] B&W-R-LP |EVENT DATE: 12/31/2001| +------------------------------------------------+EVENT TIME: 19:22[EST]| | NRC NOTIFIED BY: RICHARD WALLEMAN |LAST UPDATE DATE: 01/01/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |GARY SHEAR R3 | |10 CFR SECTION: | | |ACOM 50.72(b)(3)(xiii) LOSS COMM/ASMT/RESPONSE| | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM (SPDS) INOPERABLE | | | | The licensee reported that the SPDS display screens were locked up and thus | | unavailable for use in case of an incident. Several procedures including | | the Emergency Operating Procedures refer to the displays for information. | | With the system unavailable for greater than 8 hours a report under loss of | | assessment capabilities was made. The SPDS is being worked on at this time | | and is expected back in service in a short period of time. | | | | The licensee intends to notify the NRC Resident Inspector. | | | | * * * UPDATE 1622EST ON 1/1/02 FROM TOM COBBLEDICK TO S. SANDIN * * * | | | | The SPDS was restored to service as of 1615EST. The licensee will inform | | the NRC Resident Inspector. Notified R3DO(Shear). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38601 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 01/01/2002| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 09:41[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 01/01/2002| +------------------------------------------------+EVENT TIME: 00:42[CST]| | NRC NOTIFIED BY: STEVE WHEELER |LAST UPDATE DATE: 01/01/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |BLAIR SPITZBERG R4 | |10 CFR SECTION: | | |AIND 50.72(b)(3)(v)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 10 Power Operation |10 Power Operation | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) TURBINE DETERMINED TO BE INOPERABLE | | | | The licensee determined during surveillance testing that the HPCI turbine | | was inoperable due to the minimum flow valve cycling open and closed due to | | problem with the associated flow switch. The problem is being worked on. | | | | The licensee intends to notify the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38602 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 01/01/2002| | UNIT: [3] [] [] STATE: FL |NOTIFICATION TIME: 10:08[EST]| | RXTYPE: [3] B&W-L-LP |EVENT DATE: 01/01/2002| +------------------------------------------------+EVENT TIME: 09:19[EST]| | NRC NOTIFIED BY: BILL BANDHAUER |LAST UPDATE DATE: 01/01/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANNE BOLAND R2 | |10 CFR SECTION: | | |APRE 50.72(b)(2)(xi) OFFSITE NOTIFICATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE RESCUED SEA TURTLE | | | | EN #37902 started the biennial report period. | | | | On January 1, 2002 at 0919, a rescued sea turtle was identified as a green | | sea turtle. This is the 62nd rescue of a live sea turtle at Crystal River | | Unit 3 (CR-3) in this biennial period. Notification to the National Marine | | Fisheries Service and the Florida Fish and Wildlife Conservation Commission. | | | | | | The licensee intends to notify the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 38603 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/01/2002| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 22:36[EST]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/01/2002| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 21:32[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/01/2002| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |GARY SHEAR R3 | | DOCKET: 0707002 |THOMAS ESSIG NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: JIM McCLEERY | | | HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NON EMERGENCY | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4-HOUR REPORT DUE TO EPA NOTIFICATION REGARDING AN OPACITY VIOLATION | | | | The M4 electrical feeder was lost causing instrumentation associated with | | Boiler #3 control to deenergize. This resulted in pollutant discharge | | exceeding the 60% opacity limit specified by EPA to occur between 1620 and | | 1720EST. Operations notified the Ohio Environmental Protection Agency | | (OEPA) of the violation. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38604 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 01/02/2002| | UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 04:56[EST]| | RXTYPE: [1] W-3-LP |EVENT DATE: 01/02/2002| +------------------------------------------------+EVENT TIME: 03:05[EST]| | NRC NOTIFIED BY: SCOTT SAUNDERS |LAST UPDATE DATE: 01/02/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |ANNE BOLAND R2 | |10 CFR SECTION: | | |ARPS 50.72(b)(2)(iv)(B) RPS ACTUATION - CRITICA| | |AESF 50.72(b)(3)(iv)(A) VALID SPECIF SYS ACTUAT| | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 M/R Y 7 Power Operation |0 Hot Standby | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO DECREASING STEAM GENERATOR WATER LEVEL. | | | | During a plant start-up at 7% reactor power, feedwater oscillations occurred | | on all three steam generators. At 0215 on 01/02/02 the main feedwater | | regulator bypass valves were placed in manual control to stabilize level. | | The bypass valves were then returned to automatic control at 0245 on | | 01/02/02, and the oscillations continued within the normal operating band of | | 52-62%. At 0300 0n 01/02/02. The Control Operator noted lowering level on | | the "C" steam generator at approximately 55% with indication that the "C" | | main feedwater regulator bypass valve was shut. The operator placed the "C" | | bypass valve in manual control and attempted to open the valve with no | | response noted in valve position indication. At 30% indicated level in the | | "C" steam generator and a lowering trend, the Unit Shift Control Operator | | ordered a manual reactor trip prior to receipt of a steam generator low | | water level trip signal at 25%. All safety systems functioned as expected. | | Both Motor Driven Auxiliary Feedwater Pumps automatically actuated on the | | subsequent 'C" steam generator low water level signal. All rods fully | | inserted into the core and the electrical grid is stable. An investigation | | into what caused this event is in progress. | | | | The NRC resident inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+