U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/25/96 - 07/26/96 ** EVENT NUMBERS ** 30783 30784 30785 30786 30787 30788 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30783 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 07/25/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 04:33 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/25/96 | +------------------------------------------------+EVENT TIME: 02:42[EDT]| |NRC NOTIFIED BY: BREEDING |LAST UPDATE DATE: 07/26/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCFADDEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR SCRAM FROM 100% POWER DUE TO HIGH NEUTRON FLUX. | | | | WITH THE UNIT OPERATING AT 100% POWER, THE REACTOR AUTOMATICALLY SCRAMMED | | ON HIGH NEUTRON FLUX. THE LICENSEE REPORTED THAT AT LEAST ONE MAIN TURBINE | | CONTROL VALVE CYCLED, CAUSING A MOMENTARY PRESSURE SPIKE AND AN INCREASE IN | | NEUTRON FLUX. NO SAFETY/RELIEF VALVES LIFTED AS A RESULT OF THIS EVENT. | | FOLLOWING THE SCRAM, ALL CONTROL RODS INSERTED AND ALL SYSTEMS FUNCTIONED | | AS EXPECTED. REACTOR VESSEL WATER LEVEL DID NOT DECREASE FAR ENOUGH TO | | START EITHER HPCI OR RCIC. | | | | THE UNIT IS CURRENTLY STABLE IN CONDITION 3. THE LICENSEE INTENDS TO | | INVESTIGATE THE CAUSE OF THE CONTROL VALVE TRANSIENT. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE LICENSEE PLANS TO MAKE A | | PRESS RELEASE REGARDING THIS EVENT. | | | | * * * UPDATE 0029 7/26/96 FROM BREEDING TAKEN BY STRANSKY * * * | | | | THE LICENSEE'S PRELIMINARY EVALUATION OF DATA FROM THE AVERAGE POWER RANGE | | MONITORS INDICATES THAT CORE THERMAL POWER EXCEEDED THE LICENSE LIMIT OF | | 102% OF RATED DURING THE TURBINE CONTROL VALVE TRANSIENTS. THE CALCULATED | | PEAK HEAT FLUX REACHED 107.5% OF RATED FOR APPROXIMATELY 10 SECONDS (FROM | | 02:24:36 TO 02:24:46), WITH SUBSEQUENT TRANSIENTS CAUSING INCREASES TO | | APPROXIMATELY 102% OF RATED OR LESS. THE LICENSEE REPORTED THAT NO | | TECHNICAL SPECIFICATION SAFETY LIMITS WERE EXCEEDED BECAUSE OF THESE | | TRANSIENTS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | NOTIFIED R1DO (McFADDEN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30784 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 07/25/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 08:51 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/25/96 | +------------------------------------------------+EVENT TIME: 07:03[CDT]| |NRC NOTIFIED BY: MINTLER |LAST UPDATE DATE: 07/25/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHILLIPS RDO | |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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED SAFEGUARDS SYSTEM DEGRADATION RELATED TO A | | MALFUNCTIONING ALARM. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. | | THE RI WAS NOTIFIED. SEE HOO LOG FOR FURTHER DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30785 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WINDHAM HOSPITAL |NOTIFICATION DATE: 07/25/96 | | CITY: WILLIMANTIC REGION: 1 |NOTIFICATION TIME: 13:29 [ET]| | COUNTY: STATE: CT |EVENT DATE: 07/25/96 | |LICENSE#: 06-15203-01 AGREEMENT: N |EVENT TIME: 08:30[EDT]| | DOCKET: |LAST UPDATE DATE: 07/25/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JOHN MCFADDEN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ROBERT PETERSON | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MEDICAL MISADMINISTRATION | | | | THE LICENSEE REPORTED THAT A Tc-99m MDP DOSE FOR A BONE SCAN WAS | | INADVERTENTLY GIVEN TO A CARDIAC PATIENT. THE DOSE CONTAINED 27.3 mCi OF | | Tc-99m. THE PATIENT AND THE ATTENDING PHYSICIAN HAVE BEEN NOTIFIED. NO | | ADVERSE HEALTH EFFECTS ARE EXPECTED FROM THIS EVENT. | | | | A CONTACT PHONE NUMBER IS AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30786 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/25/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/25/96 | +------------------------------------------------+EVENT TIME: 18:27[EDT]| |NRC NOTIFIED BY: RICK HENRIQUEZ |LAST UPDATE DATE: 07/25/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN 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 +------------------------------------------------------------------------------+ | SAFETY CLASS PIPING COULD EXCEED ITS DESIGN PRESSURE UNDER LOCA CONDITIONS | | | | PIPING IN SIX DIFFERENT SYSTEMS WHICH PENETRATE CONTAINMENT HAVE THE | | POTENTIAL TO CAUSE A LOSS OF CONTAINMENT INTEGRITY UNDER LOCA CONDITIONS. | | EACH OF THESE PIPES HAS THE POTENTIAL TO BE WATER FILLED AND EACH HAS NO | | PRESSURE RELIEF. UNDER LOCA CONDITIONS, THE TEMPERATURE INCREASE IN THE | | CONTAINMENT WOULD RAISE THE TEMPERATURE OF THE WATER IN THESE PIPES, AND | | THEREBY INCREASE THE PRESSURE IN THE PIPING, POTENTIALLY OVER PRESSURIZING | | THE PIPING. THE SYSTEMS INVOLVED ARE: (1) REACTOR BUILDING CLOSED COOLING | | WATER, (2) RHR SHUTDOWN COOLING LINE, (3) MAIN STEAM LINE DRAINS, | | (4) CONTAINMENT FLOOR DRAINS, (5) CONTAINMENT EQUIPMENT DRAINS, AND | | (6) RECIRC SAMPLE LINE. | | | | THE LICENSEE CONSIDERS THESE SYSTEMS OPERABLE BASED ON DISCUSSIONS BETWEEN | | GE AND THEIR ENGINEERING STAFF. VALVE LEAKAGE SHOULD LIMIT THE PRESSURE | | RISE IN THE AFFECTED PIPING TO LESS THAN THE DUCTILE FAILURE LIMIT. LONG | | TERM CORRECTIVE ACTION IS STILL UNDER DEVELOPMENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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: 07/25/96 | |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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30788 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 07/25/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 21:39 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/25/96 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: ROBERT MALONEY |LAST UPDATE DATE: 07/25/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VENT VALVE MOVs INOPERABLE BECAUSE THE WRONG VALVE STEM MATERIAL WAS USED | | | | MOVs ON THE REACTOR AND PRESSURIZER VENT LINES MAY NOT OPEN UNDER FULL | | SYSTEM DIFFERENTIAL PRESSURE. THERE ARE TWO VALVES IN SERIES IN EACH LINE | | AND TECH SPECS REQUIRE THESE VALVES TO BE OPERABLE DURING TRANSTHERMAL AND | | HIGHER OPERATING CONDITIONS. THE PLANT IS CURRENTLY IN COLD SHUTDOWN. | | | | THIS CONDITION WAS DISCOVERED DURING A CLOSE OUT REVIEW OF MOV PROGRAM | | ISSUES. THE ENGINEERS NOTED THAT THE VALVE STEM MATERIAL ASSUMED IN THE | | VALVE VENDOR'S ORIGINAL WEAK LINK ANALYSIS DIFFERED FROM THE STEM MATERIAL | | IDENTIFIED ON THE VENDOR'S DRAWING PROVIDED FOR THE INSTALLED VALVES. MAINE | | YANKEE REQUESTED A REVISED CALCULATION USING VALUES FOR THE INSTALLED STEM | | MATERIAL. THE REVISED CALCULATIONS SHOWED THAT THE ACTUAL TORQUE | | CAPABILITY OF THE INSTALLED VALVE STEMS IS 17.5 FT-LBS VICE THE 41 FT-LBS | | CONTAINED IN THE ORIGINAL 1992 CALCULATION. THE VALVES REQUIRE AS MUCH AS | | 35.5 FT-LBS TORQUE TO STROKE AGAINST A DELTA-P OF UP TO 2200 PSID DURING AN | | ACCIDENT. | | | | THE VALVES ARE CONVAL 1" CLASS 1500 CLAMPSEAL, Y-PATTERN, GLOBE VALVES | | (DWG# 12G2P-316) WITH LIMITORQUE SMB MOTOR ACTUATORS. ORIGINAL (INSTALLED) | | STEM MATERIAL SA479-TYPE 321. REPLACEMENT STEM MATERIAL (USED IN THE | | ORIGINAL CALCULATION) SA479-XM19H. | | | | THIS CONDITION WILL BE REPAIRED PRIOR TO EXITING COLD SHUTDOWN. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+