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Event Notification Report for March 3, 2000
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/02/2000 - 03/03/2000 ** EVENT NUMBERS ** 36736 36741 36748 36749 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36736 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 02/28/2000| | UNIT: [1] [] [] STATE: IL |NOTIFICATION TIME: 18:24[EST]| | RXTYPE: [1] GE-6 |EVENT DATE: 02/28/2000| +------------------------------------------------+EVENT TIME: 14:15[CST]| | NRC NOTIFIED BY: MIKE BENSEN |LAST UPDATE DATE: 03/02/2000| | HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |MIKE JORDAN R3 | |10 CFR SECTION: | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY INOPERABLE | | | | High Pressure Core Spray was declared INOPERABLE following an overvoltage | | condition on the Division Three AC Power Distribution System. | | | | During performance of CPS 9080.02 Division Three Diesel Generator | | Operability Surveillance, the Division Three Diesel Generator was | | synchronized with the AC bus. Following synchronization, bus voltage went | | to | | approximately 4360V, which is above the limit of 4300V. The high voltage | | condition remained for approximately | | 3 1/2 minutes, until the Diesel Generator output breaker was opened and | | voltages returned to less than 4300V. | | | | The Division Three AC Power Distribution System was declared INOPERABLE due | | to being above 4300V pending an Engineering evaluation of the overvoltage | | condition. CPS Improved Technical Specification 3.8.9, Action E.1 requires | | High Pressure Core Spray to be declared INOPERABLE with the Division Three | | AC Power Distribution System INOPERABLE. | | | | The Division Three Diesel Generator was also declared INOPERABLE. | | | | The cause of the overvoltage is not known and is being investigated at this | | time. | | | | NRC Resident Inspector C. Brown was notified. | | | | | | * * * UPDATE ON 3/2/00 @ 1441 BY FUNCKHOUSER TO GOULD * * * | | | | All portions of the Division Three AC Distribution System were initially | | declared INOPERABLE. The Division Three AC Distribution System has had an | | Engineering Evaluation performed and restored to an OPERABLE status. At | | this time the High Pressure Core Spray (HPCS) System was restored to an | | OPERABLE status. The Division Three Diesel Generator is being worked to | | restore it to an OPERABLE status, subsequent to the abnormal conditions | | experienced during the Division 3 Diesel Generator run on Monday, February | | 28, 2000. | | | | The plants Technical Specifications Limited Condition for Operation (LCO) | | section 3.8.1, AC Sources Operating, does not require the Division 3 AC | | electrical power sources to be OPERABLE when the HPCS System is inoperable | | and it allows the use of the HPCS LCO in lieu of the Division 3 Diesel | | Generator. Thus, the High Pressure Core Spray (HPCS) System has been | | declared INOPERABLE at approximately 1000 on March 2, 2000 in lieu of the | | Division 3 AC Source (Division 3 DG). This is allowed by the LCO 3.8.1 | | Bases, Applicability section. The HPCS System LCO is covered in Technical | | Specifications section 3.5.1. | | | | At 1000 on 3/2/00 the plant exited LCO 3.8.1 and entered LCO 3.5.1. | | | | The NRC Resident Inspector was informed. | | | | The Reg 3 RDO(Jordan) was notified. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +------------------------------------------------------------------------------+ |General Information or Other |Event Number: 36741 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | REP ORG: US ARMY (ACALA) |NOTIFICATION DATE: 03/01/2000| |LICENSEE: US ARMY (ACALA) |NOTIFICATION TIME: 10:36[EST]| | CITY: ROCK ISLAND REGION: 3 |EVENT DATE: 02/17/2000| | COUNTY: STATE: IL |EVENT TIME: 12:00[CST]| |LICENSE#: 12-00722-06 AGREEMENT: Y |LAST UPDATE DATE: 03/02/2000| | DOCKET: |+----------------------------+ | |PERSON ORGANIZATION | | |MIKE JORDAN R3 | | |DON COOL NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: TIM MOHS | | | HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |IBAD 30.50(b)(1)(ii) MATL >5X LOWEST LIMIT | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - M1A1 COLLIMATOR WAS OVERPRESSURIZED AND RUPTURED - | | | | On 02/17/00, while the Third Army Corp Maintenance Unit from Fort | | Wainwright, AK, was performing a purge for Fort Hood units during training | | at Fort Irwin, CA, an M1A1 collimator containing 10 curies of tritium was | | overpressurized and ruptured. The M1A1 collimator was double bagged but not | | reported to the Fort Irwin Radiation Safety Officer. On 02/29/00, when the | | military van containing the M1A1 collimator was being readied for shipment | | back to Fort Wainwright, the broken M1A1 collimator was noted and surveyed. | | The survey came back contaminated (as high as 255,000 dpm). The military | | van is being held at Army/Marine Base, Yermo Annex, Barstow, CA, by Fort | | Hood personnel. Results are pending. The two individuals who performed the | | purge are being bioassayed. Results are pending. Further investigation of | | what happened and surveys to determine contamination status are ongoing. | | Army Incident #00-12. | | | | * * * UPDATE AT 1040 ON 03/02/00 FROM TIM MOHS TO JOLLIFFE * * * | | | | The results of the bioassays indicated that no dose was received by either | | individual. No personnel were contaminated. Radiation levels inside the | | van were less than release limits. Thus, the licensee desires to retract | | this event. | | | | The NRC Operations Officer notified the R3DO Mike Jordan and NMSS EO Brian | | Smith. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36748 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/02/2000| | UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 18:18[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/02/2000| +------------------------------------------------+EVENT TIME: 18:00[EST]| | NRC NOTIFIED BY: HUSSEY |LAST UPDATE DATE: 03/02/2000| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |LEN WERT R2 | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N Y 100 Power Operation |100 Power Operation | |2 N Y 100 Power Operation |100 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED NON-CONSERVATISM IN CRITICALITY CALCULATIONS FOR | | FUEL POOL STORAGE REQUIREMENTS. | | | | It was determined that certain assumptions may result in a K-effective | | (K-eff) in excess of 0.95 at 0 ppm boron concentration in the spent fuel | | pool. The Design Basis of the plant is that the fuel stored in the fuel | | pool will remain less than or equal to 0.95 K-eff when fully flooded with | | unborated water. As such the Licensee is reporting this as a condition | | outside the design basis of the plant in accordance with | | 10CFR50.72(b)(1)(ii)(B). | | | | Currently each spent fuel pool has boron concentrations in excess of 2675 | | ppm as required by Technical Specifications. Under these conditions, with | | routine monitoring of boron concentration as required by Technical | | Specifications, the plant will not require any compensatory measures to | | remain operable in the fuel pool. Duke will continue to evaluate the models | | to further evaluate this condition. | | | | The NRC Resident Inspector was informed. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 36749 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 03/02/2000| | UNIT: [1] [] [] STATE: TX |NOTIFICATION TIME: 19:25[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/02/2000| +------------------------------------------------+EVENT TIME: 16:30[CST]| | NRC NOTIFIED BY: MORRIS |LAST UPDATE DATE: 03/02/2000| | HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |CHARLES CAIN R4 | |10 CFR SECTION: | | |NLCO TECH SPEC LCO A/S | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE DID NOT COMPLY WITH LCO ACTION STATEMENTS | | | | On March 1, 2000 at 1008 hours, 125 VDC Battery System E1A11 was declared | | inoperable. Subsequently, in accordance with Technical Specifications | | 3.8.2.2, "D. C. Sources," and 3.8.3.2, "Onsite Power Distribution - | | Shutdown," Nuclear Instrumentation Source Range Detector 31 should have been | | declared inoperable or actions should have been initiated to suspend | | operations involving positive reactivity changes. Contrary to these | | requirements, Source Range Detector 31 was not declared inoperable, and at | | 0027 hours on March 2, 2000, control rods were moved as part of rapid | | refueling rod holdout operations. The rods were cycled 18 steps 3 times | | between the hours 0027 and 0400 @ 3/2/00. No movements have taken place | | since then. Detector 31 has been declared inoperable and is still | | inoperable. | | | | The NRC Resident Inspector has been notified. | | | | This notification is being made pursuant to Operating License NPF-76 | | Condition 2.G for operation or condition prohibited by Technical | | Specifications. | +------------------------------------------------------------------------------+