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 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| 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
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| 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. |
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+------------------------------------------------------------------------------+
|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 |
+------------------------------------------------------------------------------+
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| 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
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| 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
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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, 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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