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
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|Power Reactor |Event Number: 38621 |
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| 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 |
| | |
| | |
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EVENT TEXT
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| '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. |
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|Power Reactor |Event Number: 38622 |
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| 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 |
| | |
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EVENT TEXT
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| 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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