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
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|Power Reactor |Event Number: 35811 |
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| 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
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| 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. |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35812 |
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| 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). |
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+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 35813 |
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+------------------------------------------------------------------------------+
| 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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