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 +------------------------------------------------------------------------------+ |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 +------------------------------------------------------------------------------+ | 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. | +------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021