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Event Notification Report for October 5, 1999

                    U.S. Nuclear Regulatory Commission
                              Operations Center

                              Event Reports For
                           10/04/1999 - 10/05/1999

                              ** EVENT NUMBERS **

36257  36258  36259  36260  

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|Power Reactor                                    |Event Number:   36257       |
+------------------------------------------------------------------------------+
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| FACILITY: COMANCHE PEAK            REGION:  4  |NOTIFICATION DATE: 10/04/1999|
|    UNIT:  [1] [] []                 STATE:  TX |NOTIFICATION TIME: 09:11[EDT]|
|   RXTYPE: [1] W-4-LP,[2] W-4-LP                |EVENT DATE:        10/04/1999|
+------------------------------------------------+EVENT TIME:        06:30[CDT]|
| NRC NOTIFIED BY:  TERRY MARSH                  |LAST UPDATE DATE:  10/04/1999|
|  HQ OPS OFFICER:  JOHN MacKINNON               +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |KRISS KENNEDY        R4      |
|10 CFR SECTION:                                 |                             |
|ADAS 50.72(b)(2)(i)      DEG/UNANALYZED COND    |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          N       0        Refueling        |0        Refueling        |
|                                                   |                          |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| GREATER THAN 1% OF STEAM GENERATOR #4 (WESTINGHOUSE MODEL "D4") TUBES HAVE   |
| BEEN FOUND TO BE POTENTIALLY DEFECTIVE                                       |
|                                                                              |
| MORE THAN 1% (46 TUBES OR MORE)  OF THE INSPECTED (INSPECTION STILL IN       |
| PROGRESS) IN #4 STEAM GENERATOR ARE POTENTIALLY DEFECTIVE.  THE DEFECTIVE    |
| TUBES ARE BEING EVALUATED TO BE REMOVED OUT OF SERVICE.  THIS EVENT MEETS    |
| THE CRITERIA OF C-3 AS DEFINED IN COMANCHE PEAK STEAM GENERATION STATION     |
| TECHNICAL SPECIFICATION  SECTION 5.5.9.  ADDITIONAL DATA IS BEING COLLECTED  |
| AND WILL BE ANALYZED TO ASSIST IN DETERMINING THE CAUSE OF THIS EVENT.  EACH |
| STEAM GENERATOR AT COMANCHE PEAK HAS 4578 TUBES.  STEAM GENERATOR #4 SO FAR  |
| IN THE INSPECTION PROCESS HAS 49 POTENTIALLY DEFECTIVE TUBES.                |
|                                                                              |
| THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.       |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36258       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: QUAD CITIES              REGION:  3  |NOTIFICATION DATE: 10/04/1999|
|    UNIT:  [1] [2] []                STATE:  IL |NOTIFICATION TIME: 11:27[EDT]|
|   RXTYPE: [1] GE-3,[2] GE-3                    |EVENT DATE:        10/04/1999|
+------------------------------------------------+EVENT TIME:        09:20[CDT]|
| NRC NOTIFIED BY:  DARYL NOHR                   |LAST UPDATE DATE:  10/04/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        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          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| POTENTIAL COMPROMISE OF SAFEGUARDS INFORMATION                               |
|                                                                              |
| Immediate compensatory measures taken upon discovery.                        |
|                                                                              |
| The NRC Resident will be notified.                                           |
|                                                                              |
| Refer to HOO log for additional details.                                     |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|Power Reactor                                    |Event Number:   36259       |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: POINT BEACH              REGION:  3  |NOTIFICATION DATE: 10/04/1999|
|    UNIT:  [1] [2] []                STATE:  WI |NOTIFICATION TIME: 14:49[EDT]|
|   RXTYPE: [1] W-2-LP,[2] W-2-LP                |EVENT DATE:        10/04/1999|
+------------------------------------------------+EVENT TIME:        13:21[CDT]|
| NRC NOTIFIED BY:  MIKE MEYER                   |LAST UPDATE DATE:  10/04/1999|
|  HQ OPS OFFICER:  WILLIAM POERTNER             +-----------------------------+
+------------------------------------------------+PERSON          ORGANIZATION |
|EMERGENCY CLASS:          N/A                   |JOHN JACOBSON        R3      |
|10 CFR SECTION:                                 |                             |
|AOUT 50.72(b)(1)(ii)(B)  OUTSIDE DESIGN BASIS   |                             |
|                                                |                             |
|                                                |                             |
|                                                |                             |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1     N          Y       100      Power Operation  |100      Power Operation  |
|2     N          Y       100      Power Operation  |100      Power Operation  |
|                                                   |                          |
+------------------------------------------------------------------------------+
                                   EVENT TEXT                                   
+------------------------------------------------------------------------------+
| OUTSIDE DESIGN BASIS DUE TO POTENTIAL FOR A FIRE TO ISOLATE NORMAL AND       |
| ALTERNATE SUPPLY SOURCES TO THE CHARGING PUMPS.                              |
|                                                                              |
| During an Appendix R Rebaselining project it was discovered that the         |
| potential exists for a fire to isolate the normal and alternate water supply |
| sources to the Unit 1 or 2 charging pumps.  Valve CV-112C (Normal Supply)    |
| and CV-112B (Alternate RWST) for either unit has virtually the same cable    |
| routing.  The licensee has initiated fire rounds in all affected fire        |
| zones.                                                                       |
|                                                                              |
| The NRC Resident will be notified.                                           |
+------------------------------------------------------------------------------+

+------------------------------------------------------------------------------+
|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, 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 NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE.       |
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