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Event Notification Report for October 6, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/05/1999 - 10/06/1999

                              ** EVENT NUMBERS **

36260  36261  36262  

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|Power Reactor                                    |Event Number:   36260       |
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| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 10/05/1999|
|    UNIT:  [1] [] []                 STATE:  IL |NOTIFICATION TIME: 03:52[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        10/04/1999|
+------------------------------------------------+EVENT TIME:        23:55[CDT]|
| NRC NOTIFIED BY:  KEN HILL                     |LAST UPDATE DATE:  10/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
|                                                   |                          |
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                                   EVENT TEXT                                   
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| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE                   |
|                                                                              |
| HPCI OUTBOARD STEAM SUPPLY ISOLATION VALVE, MO 1-2301-5, WAS UNABLE TO BE    |
| CLOSED USING THE CONTROL ROOM CONTROL SWITCH DURING A PLANNED VALVE TIMING   |
| SURVEILLANCE PRIOR TO A PLANNED HPCI SYSTEM OUTAGE.  PRIOR TO THIS, AT 2348  |
| CDT ON 10/4/99, THE HPCI SYSTEM WAS MADE INOPERABLE WHEN THE INBOARD STEAM   |
| SUPPLY ISOLATION VALVE, MO 1-2301-4, WAS CLOSED AS PART OF THE VALVE TIMING  |
| SURVEILLANCE TO ALLOW TESTING OF THE OUTBOARD VALVE.  SINCE MO 1-2301-5      |
| COULD NOT BE CLOSED, MO 1-2301-4 WAS KEPT CLOSED TO COMPLY WITH TECHNICAL    |
| SPECIFICATIONS 3.5.a  ACTION STATEMENTS AND STATION PROCEDURES FOR AN        |
| INOPERABLE CONTAINMENT ISOLATION VALVE.  HPCI COULD NOT BE RETURNED TO       |
| SERVICE, AS PLANNED, AND REMAINS INOPERABLE.  ALL EMERGENCY CORE COOLING     |
| SYSTEMS, EMERGENCY DIESEL GENERATORS, AND REACTOR CORE ISOLATION COOLING     |
| SYSTEM ARE FULLY OPERABLE.                                                   |
|                                                                              |
| THE NCR RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.       |
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|Power Reactor                                    |Event Number:   36261       |
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| FACILITY: GINNA                    REGION:  1  |NOTIFICATION DATE: 10/05/1999|
|    UNIT:  [1] [] []                 STATE:  NY |NOTIFICATION TIME: 08:54[EDT]|
|   RXTYPE: [1] W-2-LP                           |EVENT DATE:        10/05/1999|
+------------------------------------------------+EVENT TIME:        08:54[EDT]|
| NRC NOTIFIED BY:  JOE WIDAY                    |LAST UPDATE DATE:  10/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|10 CFR SECTION:                                 |VERN HODGE           NRR     |
|CCCC 21.21               UNSPECIFIED PARAGRAPH  |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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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| W2 SWITCH SUPPLIED BY WESTINGHOUSE DRAWN FROM STOCK DID NOT OPERATE          |
| PROPERLY                                                                     |
| AFTER BEING INSTALLED.                                                       |
|                                                                              |
| W2 SWITCH WAS SUPPLIED TO ROCHESTER GAS AND ELECTRIC CORPORATION BY          |
| WESTINGHOUSE ELECTRIC CORPORATION.  A SAFETY RELATED W2 SWITCH DRAWN FROM    |
| STOCK DID NOT OPERATE SATISFACTORILY AFTER BEING INSTALLED IN THE MAIN       |
| CONTROL BOARD FOR USE AS THE CONTROL SWITCH FOR SAFETY INJECTION PUMP 1C     |
| (1/SIP1 C2).   THE SWITCH DID WORK PROPERLY BEFORE INSTALLATION IN THE MAIN  |
| CONTROL BOARD POSITION.   HOWEVER, SUBSEQUENT TO INSTALLATION THE SWITCH     |
| MECHANISM WOULD BIND AND WOULD NOT SPRING RETURN TO THE "AFTER CLOSE"  OR    |
| "AFTER TRIP" POSITIONS.  THE SWITCH IS EXPECTED TO FUNCTION PROPERLY IN BOTH |
| POSITIONS.                                                                   |
|                                                                              |
| THE SUBSTANTIAL SAFETY HAZARD CREATED BY THE SWITCH POTENTIALLY BEING STUCK  |
| IN THE "TRIP" POSITION IS THAT THE ASSOCIATED ECCS PUMP BREAKER WOULD NOT    |
| AUTO-CLOSE FOLLOWING A SAFETY INJECTION ACTUATION SYSTEM SIGNAL; THEREFORE,  |
| THE ASSOCIATED ECCS PUMP WOULD NOT PERFORM ITS SAFETY FUNCTION.  THE         |
| POSTULATED FAILURE, IN CONJUNCTION WITH ANOTHER POSTULATED SINGLE FAILURE,   |
| COULD CAUSE A LOSS OF SAFETY FUNCTION FOR THE ECCS SYSTEM.                   |
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+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36262       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: VERMONT YANKEE           REGION:  1  |NOTIFICATION DATE: 10/05/1999|
|    UNIT:  [1] [] []                 STATE:  VT |NOTIFICATION TIME: 09:44[EDT]|
|   RXTYPE: [1] GE-4                             |EVENT DATE:        10/05/1999|
+------------------------------------------------+EVENT TIME:        09:00[EDT]|
| NRC NOTIFIED BY:  JIM BROOK                    |LAST UPDATE DATE:  10/05/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN KINNEMAN        R1      |
|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   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       99       Power Operation  |99       Power Operation  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| HIGH PRESSURE COOLANT INJECTION (HPCI) DECLARED INOPERABLE.                  |
|                                                                              |
| DURING DRILLING OPERATIONS TO INSTALL HILTI BOLTS IN THE HPCI ROOM, A WORKER |
| LEANED UP AGAINST AN OIL LINE AND CAUSED AN OIL LEAK.  THE LEAK WAS          |
| ESTIMATED WITH NO PRESSURE TO BE AT 60 DROPS PER MINUTE.  HPCI WAS DECLARED  |
| INOPERABLE PER TECHNICAL SPECIFICATION 3.5.E.2 (7 DAY LIMITING CONDITION OF  |
| OPERATION) .  ALL OTHER EMERGENCY CORE COOLING SYSTEMS, REACTOR CORE         |
| ISOLATION COOLING (RCIC), AND THE EMERGENCY DIESEL GENERATORS  ARE FULLY     |
| OPERABLE.                                                                    |
|                                                                              |
| THE NRC RESIDENT WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.                 |
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