The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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  

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36260       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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  |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| 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.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36261       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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                                   
+------------------------------------------------------------------------------+
| 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.                   |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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.                 |
+------------------------------------------------------------------------------+


Page Last Reviewed/Updated Thursday, March 25, 2021