Event Notification Report for November 23, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           11/22/1999 - 11/23/1999

                              ** EVENT NUMBERS **

36456  36457  

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|Power Reactor                                    |Event Number:   36456       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: COOK                     REGION:  3  |NOTIFICATION DATE: 11/22/1999|
|    UNIT:  [1] [2] []                STATE:  MI |NOTIFICATION TIME: 06:33[EST]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        11/22/1999|
+------------------------------------------------+EVENT TIME:        06:05[EST]|
| NRC NOTIFIED BY:  MARY BETH DEPUYDT            |LAST UPDATE DATE:  11/22/1999|
|  HQ OPS OFFICER:  FANGIE JONES                 +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |THOMAS KOZAK         R3      |
|10 CFR SECTION:                                 |                             |
|DDDD 73.71               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|2     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| SECURITY REPORT                                                              |
|                                                                              |
| Safeguards system degradation related to access control, immediate           |
| compensatory measures taken upon discovery.                                  |
|                                                                              |
| The licensee intends to notify the NRC Resident Inspector.                   |
|                                                                              |
| Refer to the HOO Log for additional details.                                 |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36457       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BROWNS FERRY             REGION:  2  |NOTIFICATION DATE: 11/22/1999|
|    UNIT:  [] [2] []                 STATE:  AL |NOTIFICATION TIME: 23:18[EST]|
|   RXTYPE: [1] GE-4,[2] GE-4,[3] GE-4           |EVENT DATE:        11/18/1999|
+------------------------------------------------+EVENT TIME:        19:00[CST]|
| NRC NOTIFIED BY:  CHRIS VAUGHN                 |LAST UPDATE DATE:  11/22/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |EDWARD MCALPINE      R2      |
|10 CFR SECTION:                                 |                             |
|AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|                                                   |                          |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) OIL SYSTEM PRESSURE BOUNDARY          |
| BREACHED                                                                     |
|                                                                              |
| At approximately 1636 CST on 11/18/99, during replacement of the Unit 2 HPCI |
| Oil Cooler Discharge Temperature Switch by Instrument Maintenance, the       |
| pressure boundary of the HPCI oil system was inadvertently breached for a    |
| total of approximately five minutes (the work package assumed that the       |
| Temperature Switch had a well, but it when the Temperature Switch was        |
| removed it was discovered that Switch did not have a well).  The breach      |
| occurred because adequate documentation was not included in the work         |
| package.   The switch was successfully replaced and the work document        |
| subsequently completed and closed out at 2005 CST on 11/18/99.  Upon further |
| evaluation of this work activity by Site Engineering and Operations          |
| personnel, it has been determined that the HPCI system would not have been   |
| capable of performing its intended design function during the time frame the |
| oil system was breached.                                                     |
|                                                                              |
| The NRC Resident Inspector was notified of this event by the licensee.       |
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