Event Notification Report for January 11, 2002
U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/10/2002 - 01/11/2002 ** EVENT NUMBERS ** 38621 38622 +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38621 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 01/10/2002| | UNIT: [1] [] [] STATE: WI |NOTIFICATION TIME: 16:01[EST]| | RXTYPE: [1] W-2-LP |EVENT DATE: 01/10/2002| +------------------------------------------------+EVENT TIME: 12:30[CST]| | NRC NOTIFIED BY: GARY HARRINGTON |LAST UPDATE DATE: 01/10/2002| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |DAVID HILLS R3 | |10 CFR SECTION: | | |AUNA 50.72(b)(3)(ii)(B) UNANALYZED CONDITION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 'B' COMPONENT COOLING WATER (CCW) PUMP DECLARED INOPERABLE | | | | On 1/9/02 during the shift of CCW pumps from train 'B' to train 'A', the | | operator noted that the casing temperature on the 'B' CCW pump increased | | after the 'A' CCW pump was started. Engineering evaluation and testing on | | 1/10/02 led to the conclusion that the 'A' CCW pump overpowers the 'B' CCW | | pump when they are run in parallel. The 'B' CCW pump is in effect | | "dead-headed" when the pumps are operated in parallel, which would lead to | | failure during extended operation. The 'B' CCW pump control switch has been | | placed in pull-to-lock to make it inoperable. Consequently, the plant is in | | the technical specifications limiting condition for operation for an | | inoperable CCW pump. This condition is reported due to the potential for a | | complete loss of CCW, an engineered safeguards feature. This is based on | | the assumption that the "dead-headed" pump would eventually fail and the | | subsequent failure of the only available CCW pump, resulting in a complete | | loss of CCW. These assumptions are consistent with the Kewaunee's design | | basis. | | | | "Additionally, this report is also being used to notify NRC that Kewaunee | | submittal according to the requirements of NRC Bulletin 88-04, "Potential | | Safety Related Pump Loss." Kewaunee's submittal indicated the CCW system | | was not vulnerable to this particular type of system failure." | | | | The plant's engineering and management staff are continuing to review the | | event and determine what corrective actions will be necessary to support | | continued plant operation. | | | | The licensee notified the NRC Resident Inspector. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 38622 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 01/11/2002| | UNIT: [] [2] [] STATE: NJ |NOTIFICATION TIME: 05:12[EST]| | RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/11/2002| +------------------------------------------------+EVENT TIME: 04:00[EST]| | NRC NOTIFIED BY: JOHN GARECHT |LAST UPDATE DATE: 01/11/2002| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: NON EMERGENCY |RONALD BELLAMY R1 | |10 CFR SECTION: | | |ASHU 50.72(b)(2)(i) PLANT S/D REQD BY TS | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | |2 N Y 100 Power Operation |65 Power Operation | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SHUTDOWN DUE TO # 2A EMERGENCY DIESEL GENERATOR NOT | | OPERATING PROPERLY. | | | | "A unit shutdown was initiated at 0400 on 01/11/02 as required by Technical | | Specifications. Technical Specification Action Statement 3.8.1.1.b action b | | was entered at 0303 on 01/08/02 for scheduled maintenance on the 2A | | emergency diesel generator. During post maintenance testing, oscillations | | associated with the generator voltage control system were observed. The | | cause of the voltage oscillations has not been identified or corrected. | | Troubleshooting activities are on-going in an attempt to identify the | | cause. | | | | "The 2B and 2C emergency diesel generator surveillance tests were performed | | within 24 hours to evaluate for common cause failures. A Common Cause | | Failure was not identified and the 2B and 2C surveillance tests were | | performed satisfactorily. | | | | "Salem Unit Two will be in Mode 3 by 0930 on 01/11/02 and in Mode 5 by 1503 | | on 01/12/02 as required by Technical Specifications. | | | | "Salem Unit one is not affected by this event and remains in Mode 1 at | | 100%" | | | | The NRC Resident Inspector was notified of this event notification by the | | licensee. | +------------------------------------------------------------------------------+
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