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Event Notification Report for June 11, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           06/10/1999 - 06/11/1999

                              ** EVENT NUMBERS **

35811  35812  35813  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35811       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 06/10/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 13:56[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        05/11/1999|
+------------------------------------------------+EVENT TIME:        13:35[EDT]|
| NRC NOTIFIED BY:  MCCOY                        |LAST UPDATE DATE:  06/10/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN CARUSO          R1      |
|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                                   
+------------------------------------------------------------------------------+
| BOTH DIESEL GENERATORS DECLARED INOPERABLE                                   |
|                                                                              |
| During the review (on 6/10/99 @ 1330) of an event in which the "A"  Diesel   |
| Generator output breaker failed to close during periodic testing, it was     |
| discovered that the plant had operated for a period of time with both        |
| required Diesel Generators inoperable. Based on the identified failure mode, |
| the  "A"  Diesel Generator breaker was in an inoperable state since the last |
| time it was tripped. This occurred following the performance of periodic     |
| testing on 5/11/99 @ 11:48 AM. On 5/11/99 @ 1334 the  "B"  Diesel Generator  |
| was declared inoperable for the performance of periodic testing, which       |
| resulted in both Diesel Generators being inoperable and the plant entering a |
| 3.0.3 TS LCO action statement. Therefore, during the periodic testing of the |
| "B"  Diesel Generator, there would have been an inability to automatically   |
| respond to an event coincident with a loss of offsite power.  The "B" Diesel |
| Generator was immediately returned to service following the test.  The "A"   |
| Diesel Generator was restored to an operable status 6/9/99.                  |
|                                                                              |
| The Resident Inspector was notified.                                         |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35812       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PEACH BOTTOM             REGION:  1  |NOTIFICATION DATE: 06/10/1999|
|    UNIT:  [2] [] []                 STATE:  PA |NOTIFICATION TIME: 15:29[EDT]|
|   RXTYPE: [2] GE-4,[3] GE-4                    |EVENT DATE:        06/10/1999|
+------------------------------------------------+EVENT TIME:        14:30[EDT]|
| NRC NOTIFIED BY:  CAMPBELL                     |LAST UPDATE DATE:  06/11/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN CARUSO          R1      |
|10 CFR SECTION:                                 |                             |
|AARC 50.72(b)(1)(v)      OTHER ASMT/COMM INOP   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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                                   
+------------------------------------------------------------------------------+
| PLANT LOST THEIR SAFETY PARAMETER DISPLAY SYSTEM (SPDS)                      |
|                                                                              |
| A HARDWARE FAILURE OCCURRED ON THE UNIT 2 PLANT PROCESS COMPUTER SYSTEM.     |
| THIS RESULTED IN THE LOSS OF THE SPDS, WHICH IS ONE METHOD USED FOR          |
| EMERGENCY ASSESSMENT.  ALL THE CONTROL ROOM INDICATIONS ARE OPERABLE AND     |
| AVAILABLE FOR EMERGENCY ASSESSMENT.                                          |
|                                                                              |
| THE RESIDENT INSPECTOR WAS NOTIFIED.                                         |
|                                                                              |
| * * * UPDATE AT 0250 BY EILOLA, TAKEN BY WEAVER * * *                        |
|                                                                              |
| THE HARDWARE FAILURE HAS BEEN REPAIRED AND THE SYSTEM HAS BEEN RETURNED TO   |
| SERVICE.  THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR.  THE          |
| OPERATIONS OFFICER NOTIFIED THE R1DO (CARUSO).                               |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   35813       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: MONTICELLO               REGION:  3  |NOTIFICATION DATE: 06/10/1999|
|    UNIT:  [1] [] []                 STATE:  MN |NOTIFICATION TIME: 16:01[EDT]|
|   RXTYPE: [1] GE-3                             |EVENT DATE:        06/10/1999|
+------------------------------------------------+EVENT TIME:        14:00[CDT]|
| NRC NOTIFIED BY:  HASBRUCK                     |LAST UPDATE DATE:  06/10/1999|
|  HQ OPS OFFICER:  CHAUNCEY GOULD               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |BRUCE JORGENSEN      R3      |
|10 CFR SECTION:                                 |                             |
|AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD  |                             |
|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 COOLANT INJECTION (HPCI) SYSTEM COULD HAVE BEEN INOPERABLE     |
| DURING PAST SURVEILLANCES.                                                   |
|                                                                              |
| The licensee discovered a condition during HPCI surveillances that could     |
| result in the system becoming inoperable.  The HPCI test return isolation    |
| valve, MO-2071, is opened to support HPCI testing and it may not close as    |
| required during a required activation of the system.  There are valve        |
| components, which are not part of the pressure boundary, that could exceed   |
| their structural limits.  MO-2071 is normally closed and HPCI is currently   |
| operable.  This condition is being reported due to failure to enter          |
| appropriate plant Technical Specification LCOs during past plant operation   |
| when MO-2071 was open during surveillance testing.                           |
|                                                                              |
| The licensee notified the NRC Resident Inspector as well as the state and    |
| local agencies.                                                              |
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