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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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