U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/13/96 - 08/14/96 ** EVENT NUMBERS ** 30787 30869 30870 30871 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30787 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 07/25/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 21:02 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/25/96 | +------------------------------------------------+EVENT TIME: 18:00[CDT]| |NRC NOTIFIED BY: TERRY RATZLAFF |LAST UPDATE DATE: 08/13/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | APPENDIX R SAFE AND ALTERNATE SHUTDOWN ANALYSIS REPORT CONTAINS ASSUMPTIONS | | THAT MAY NOT BE CONSERVATIVE | | | | "AS PART OF A CORRECTIVE ACTION FOR LER 94-016, A RE-EVALUATION OF THE | | COOPER NUCLEAR STATION APPENDIX R SAFE SHUTDOWN AND ALTERNATE SHUTDOWN | | ANALYSIS REPORT DETERMINED THAT CERTAIN ASSUMPTIONS USED IN THAT ANALYSIS | | MAY NOT HAVE BEEN CONSERVATIVE. SPECIFICALLY, POSTULATING A FIRE ON 931' | | REACTOR BUILDING NORTH AND ASSUMING MULTIPLE GROUND CABLE FAULTS, THE | | REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM CONTROLLER COULD BECOME | | DISABLED. CNS PROCEDURE 5.4.3.1 CREDITS RCIC FOR SAFE SHUTDOWN FOLLOWING A | | FIRE IN THIS AREA. DURING THIS POSTULATED EVENT, OTHER SYSTEMS WOULD BE | | AVAILABLE TO COMPENSATE FOR THE LOSS OF RCIC CONTROL. IN ADDITION, | | ASSUMING MULTIPLE GROUND CABLE FAULTS DURING A POSTULATED ALTERNATE | | SHUTDOWN, FIRE COULD RESULT IN THE FAILURE OF DIESEL GENERATOR NO. 2 (DG-2) | | CONTROL POWER FUSE PRIOR TO ISOLATION OF THE DG-2 CONTROL CIRCUITS FROM THE | | FIRE AREA. CURRENT MITIGATION PROCEDURES DO NOT DIRECT OPERATORS TO | | REPLACE THE DG-2 CONTROL POWER FUSE, NOR DO NRC REGULATIONS ALLOW CREDITING | | THIS ACTION (HOT SHUTDOWN REPAIR) WITHOUT PRIOR NRC REVIEW AND APPROVAL." | | | | AN HOURLY FIRE WATCH PATROL HAS BEEN ESTABLISHED FOR THE AFFECTED AREAS AS | | AN IMMEDIATE CORRECTIVE ACTION. THE REEVALUATION EFFORT FOR APPENDIX R IS | | CONTINUING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 2335EDT 8/13/96 FROM TERRY BORGAN TO S.SANDIN * * * | | | | THE LICENSEE PROVIDED THE FOLLOWING UPDATE: | | | | "AS A SUPPLEMENT AND FOLLOWUP TO THE PREVIOUS FOUR HOUR REPORT SUBMITTED ON | | JULY 25, 1996 REGARDING AN ONGOING RE-EVALUATION OF THE COOPER NUCLEAR | | STATION (CNS) APPENDIX R SAFE SHUTDOWN AND ALTERNATE SHUTDOWN ANALYSIS | | REPORT (SSAR), CNS HAS DETERMINED THAT FOUR TYPES OF ASSUMPTIONS MAY NOT | | HAVE BEEN FULLY ADDRESSED IN THE ORIGINAL SSAR. THESE ARE: (1) MULTIPLE | | GROUND FAULTS WERE NOT ASSUMED TO INDUCE HOT SHORTS IN UNGROUNDED DC | | CONTROL CIRCUITS, (2) AUTOMATIC INITIATION CIRCUITS FOR CERTAIN SYSTEMS | | WERE NOT ASSUMED TO RESULT IN A SPURIOUS OPERATION, (3) UNDER CERTAIN | | CONDITIONS, THE POTENTIAL FOR REACTOR BUILDING CLOSED COOLING WATER SYSTEM | | PUMP RUN OUT WAS NOT FULLY ADDRESSED, AND (4) NOT ALL DAMPER FAILURE | | POSITIONS FOR THE HVAC IN THE CONTROL BUILDING DC SWITCHGEAR AREAS WERE | | FULLY EVALUATED. CNS BELIEVES THAT THESE CONCERNS CAN BE ADDRESSED THROUGH | | PROCEDURE ENHANCEMENTS." | | | | "CNS CONSERVATIVELY CONCLUDED THAT IT WOULD SUPPLEMENT ITS JULY 25, 1996 | | NOTIFICATION AND REPORT THESE ADDITIONAL FINDINGS UNDER | | 10CFR50.72(b)(2)(iii)(A). AN HOURLY FIRE WATCH PATROL CONTINUES TO BE IN | | PLACE FOR THE AFFECTED AREAS AS AN IMMEDIATE CORRECTIVE ACTION. PROCEDURAL | | CHANGES WILL BE INSTITUTED AS APPROPRIATE AND THE SSAR RE-EVALUATION EFFORT | | FOR APPENDIX R IS CONTINUING." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED | | R4DO(SPITZBERG). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30869 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 08/13/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 10:45 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 08/13/96 | +------------------------------------------------+EVENT TIME: 10:20[EDT]| |NRC NOTIFIED BY: BURTON |LAST UPDATE DATE: 08/13/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT BOTH "A" AND "B" TRAINS OF ESF AND SERVICE | | WATER SYSTEMS WERE INOPERABLE, PUTTING THEM IN A LCO ACTION STATEMENT. | | | | THIS CONDITION WAS DISCOVERED DURING A DRAWING REVIEW WHEN IT WAS NOTICED | | THAT TORNADO HOLD DOWN BARS FOR 5 MANHOLE COVERS ILLUSTRATED IN THE | | DRAWING, WERE NOT IN PLACE OVER THE COVERS. THESE MANHOLE COVERS PROVIDE | | MISSILE PROTECTION FOR VITAL CABLES THAT SUPPLY BOTH "A" AND "B" SAFETY | | TRAINS. IT APPEARS THAT THESE MANHOLE COVERS NEVER HAD THE TORNADO HOLD | | DOWN BARS INSTALLED SINCE INITIAL CONSTRUCTION. PRELIMINARY DISCUSSIONS FOR | | CORRECTIVE ACTION TO BE TAKEN TO SATISFY THE LCO ACTION STATEMENT, WILL BE | | TO PLACE CONCRETE BARRIERS ON TOP OF THE COVERS THAT WILL BE IN EXCESS OF | | THE CALCULATED POTENTIAL LIFT FORCE FROM THE DIFFERENTIAL PRESSURE | | GENERATED BY A TORNADO. THEY WILL BE CONDUCTING FURTHER INVESTIGATION ON | | THE CAUSE OF THIS EVENT. THE RI WAS INFORMED | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30870 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 08/13/96 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 16:56 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/13/96 | +------------------------------------------------+EVENT TIME: 16:14[EDT]| |NRC NOTIFIED BY: JIM ANDERSON |LAST UPDATE DATE: 08/13/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI ISOLATION DUE TO PERSONNEL ERROR DURING SURVEILLANCE TESTING. | | | | "UNIT 2 HPCI ISOLATED DURING PERFORMANCE OF A CALIBRATION PROCEDURE, | | 57SV-SUV-012-2S. THE I&C TECH WAS PERFORMING A CALIBRATION ON A HPCI | | EXHAUST DIAPHRAGM INSTRUMENT, 2E41-N655B, WHEN HE INADVERTENTLY MOVED THE | | TEST CHANNEL SELECT SWITCH TO A HPCI STEAM LINE DP INSTRUMENT AND CAUSED A | | HPCI STEAM LINE ISOLATION VALVE TO CLOSE, 2E41-F003." | | | | "THE PROCEDURE WAS STOPPED AND RETURNED TO NORMAL. THE ISOLATION WAS RESET | | AND HPCI RESTORED TO STANDBY." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30871 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/13/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/13/96 | +------------------------------------------------+EVENT TIME: 19:21[EDT]| |NRC NOTIFIED BY: VINCENT DeCLEMENTE |LAST UPDATE DATE: 08/13/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN CARUSO RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL CONSERVATION WAS NOTIFIED OF THE | | EMERGENCY DIESEL FUEL OIL STORAGE TANK'S FAILURE TO MEET TIGHTNESS | | REQUIREMENTS. | | | | AT 1921 HOURS, INDIAN POINT 3 NOTIFIED THE NEW YORK STATE DEPARTMENT OF | | ENVIRONMENTAL CONSERVATION (REPORT NUMBER 96-06167) DUE TO THE FAILURE OF A | | TANK TIGHTNESS TEST PERFORMED ON "33" EMERGENCY DIESEL GENERATOR FUEL OIL | | STORAGE TANK. THE TEST RESULTS INDICATE A TEST LEAK RATE OF >0.05 GPH FOR | | THIS TANK/SYSTEM. THE LICENSEE DOES NOT BELIEVE THAT THE TANK IS LEAKING | | BASED ON DAILY INVENTORY CHECKS. THE LEAK RATE MAY BE DUE TO LEAK BY OF | | VALVES IN THE SYSTEM OR FROM OTHER AREAS WHICH DO NOT CONTAIN FUEL UNDER | | NORMAL OPERATIONS BUT DO DURING THE OVERFILL TESTING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+