U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/25/94 - 10/26/94 ** EVENT NUMBERS ** 27945 27946 27947 27948 27949 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27945 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 10/25/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 09:25 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 10/25/94 | +------------------------------------------------+EVENT TIME: 07:56[CDT]| |NRC NOTIFIED BY: TOM OSELAND |LAST UPDATE DATE: 10/25/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |L. ROBERT GREGER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ED GOODWIN EO | | |AUSTIN FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED BASED ON THE OFFSITE TRANSPORTATION OF A POTENTIALLY | | CONTAMINATED MAN | | | | AN UNUSUAL EVENT WAS DECLARED AT 0756 CDT WHEN A POTENTIALLY CONTAMINATED | | MAN WAS TRANSPORTED TO A LOCAL HOSPITAL. THE MAN WAS INJURED IN A FALL IN | | A RADIOACTIVELY CONTROLLED AREA (RCA). IT WAS NOT A CONTAMINATED AREA. THE | | UE WAS TERMINATED AT 0827 CDT WHEN THE HOSPITAL CONFIRMED THE MAN WAS NOT | | CONTAMINATED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27946 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 10/25/94 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 15:06 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/25/94 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: BEINKE |LAST UPDATE DATE: 10/25/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LANDIS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT GROUP 1 (MSIV) ISOLATION SIGNAL WHILE STARTING TURBINE EHC | | PUMP. | | | | WHILE STARTING THE TURBINE EHC PUMPS, A CONTAINMENT GROUP 1 ISOLATION | | SIGNAL WAS GENERATED WHEN SEVERAL TURBINE STOP VALVES OPENED. (A LOW | | CONDENSER VACUUM PLUS OPENING OF TURBINE STOP VALVES GENERATES A GROUP 1 | | ISOLATION SIGNAL.) THE UNIT IS CURRENTLY IN A REFUELING OUTAGE, AND THE | | MSIVs WERE ALREADY CLOSED AT THE TIME OF THE EVENT. THE LICENSEE STATED | | THAT 2/4 MAIN STEAM LINE DRAIN VALVES (LOCATED ON THE "A" AND "C" STEAM | | LINES) DID NOT CLOSE UPON THE RECEIPT OF THE GROUP 1 ISOLATION SIGNAL. THE | | LICENSEE IS INVESTIGATING THE FAILURE TO CLOSE, BUT SUSPECTS THAT IT MAY | | HAVE BEEN CAUSED BY A DIFFERENCE IN THE CLOSURE LOGIC BETWEEN THE MSIVs AND | | DRAIN VALVES. | | | | THE LICENSEE REPORTED THAT GENERAL ELECTRIC HAD BEEN PERFORMING A TURBINE | | OVERHAUL, AND THAT SOME MECHANICAL LINKAGES IN THE TURBINE CONTROL SYSTEM | | HAD BEEN BLOCKED SO THAT THE TURBINE COULD NOT BE TRIPPED OR RESET. WHEN | | EHC PRESSURE WAS PROVIDED TO THE VALVES, THE VALVES OPENED. FURTHER, THE | | LICENSEE HAD REMOVED LINKS TO PREVENT THE GROUP 1 ISOLATION SIGNAL DUE TO | | TURBINE STOP VALVE MOVEMENT, BUT HAD REINSTALLED THE LINKS YESTERDAY FOR | | TESTING. THE RI HAS BEEN INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27947 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 10/25/94 | |UNIT: [1] [2] [ ] STATE: MN |NOTIFICATION TIME: 16:25 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/25/94 | +------------------------------------------------+EVENT TIME: 12:11[CDT]| |NRC NOTIFIED BY: HARKINSON |LAST UPDATE DATE: 10/25/94 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GREGER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | AUXILIARY BUILDING SPECIAL VENTILATION SYSTEM ACTUATION DUE TO VALID HIGH | | RADIATION SIGNAL. | | | | WHILE VENTING THE UNIT 2 SEAL WATER RETURN FILTER PRIOR TO PLACING IN | | SERVICE, A VALID HIGH RADIATION SIGNAL WAS RECEIVED FROM THE NORMAL | | (NON-ESF) VENTILATION SYSTEM EXHAUST RADIATION MONITORS. THE FILTER WAS | | BEING VENTED IN ACCORDANCE WITH ESTABLISHED PLANT PROCEDURES AT THE TIME OF | | THE EVENT. THE HIGH RADIATION SIGNAL WAS CAUSED BY AN UNUSUALLY HIGH | | GASEOUS RELEASE FROM THE FILTER DUE TO LEAKING FUEL IN THE UNIT 2 REACTOR, | | AND RESULTANT HIGH ACTIVITY LEVELS IN THE RCS. | | | | THE LICENSEE MANUALLY STARTED THE SECOND TRAIN OF THE AUX BUILDING SPECIAL | | VENT SYSTEM TO HELP CLEAN UP THE AUX BUILDING ATMOSPHERE. TEN PLANT | | EMPLOYEES RECEIVED GASEOUS CONTAMINATION DUE TO THE RELEASE. THE LICENSEE | | REPORTED THAT APPROXIMATELY 2 Ci OF NOBLE GASES (AT A RELEASE RATE OF | | 2 E-4 Ci/SEC) WERE RELEASED TO THE ATMOSPHERE THROUGH THE AUX BUILDING | | VENTILATION SYSTEM (APPROXIMATELY 5% OF TECHNICAL SPECIFICATION LIMITS). | | THE RI HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27948 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BW/IP INTERNATIONAL, INC |NOTIFICATION DATE: 10/25/94 | | CITY: VERNON REGION: 4 |NOTIFICATION TIME: 17:37 [ET]| | COUNTY: STATE: CA |EVENT DATE: 10/25/94 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[PDT]| | DOCKET: |LAST UPDATE DATE: 10/25/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: K. HUBER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BW/IP INTERNATIONAL HAS IDENTIFIED A POTENTIAL DESIGN PROBLEM WITH 6-INCH | | 900PSI MOTOR OPERATED Y-GLOBE VALVES. | | | | THE FOLLOWING IS AN EXTRACT FROM THE FACSIMILE PROVIDED BY THE VENDOR: | | | | "DESIGN CALCULATIONS OF STEM THRUST REQUIRED TO CLOSE THE VALVE WERE BASED | | ON THE SEAT AREA OF THE VALVE. QUANTITATIVE MEASUREMENTS OF THE REFERENCED | | VALUE AS PART OF THE EPRI MOV PERFORMANCE PREDICTION PROGRAM IN RESPONSE TO | | NRC GENERIC LETTER 89-10, SHOWED THAT, WHEN FLOW THROUGH THE VALVE EXCEEDS | | 5 FPS, THE STEM THRUST SHOULD BE BASED ON THE DIFFERENTIAL PRESSURE ACTING | | ACROSS THE VALVE GUIDE AREA. REQUIRED STEM THRUST USING THE VALVE GUIDE | | AREA CAN BE MORE THAN DOUBLE THE VALUE CALCULATED USING THE SEATING AREA. | | | | THE CALCULATED FORCES ARE USED TO SIZE THE VALVE ACTUATOR AND MOTOR AND TO | | SET THE ACTUATOR TORQUE SWITCH. IF THE STEM THRUST REQUIRED TO CLOSE THE | | VALVE AGAINST A DIFFERENTIAL PRESSURE IS HIGHER THAN THE DESIGN VALUE, THE | | VALVE MAY FAIL TO PERFORM ITS INTENDED SAFETY FUNCTION." | | | | THE VENDOR INDICATED THAT THESE VALVES ARE IN USE AT THE FOLLOWING PLANTS: | | ST. LUCIE, COMANCHE PEAK, WNP-3, WATTS BAR, BROWNS FERRY, ANO-1, PALO | | VERDE, PERRY, McGUIRE, AND CATAWBA. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27949 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 10/26/94 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 04:30 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 10/26/94 | +------------------------------------------------+EVENT TIME: 01:26[CDT]| |NRC NOTIFIED BY: STEVE KUCZYNSKI |LAST UPDATE DATE: 10/26/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |L. ROBERT GREGER RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A N 0 REFUELING | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT SCRAM SIGNAL DURING SURVEILLANCE TESTING. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE REPORTING THIS EVENT: | | "AT 01:26 WITH UNIT 3 IN THE REFUEL MODE, A FULL REACTOR SCRAM SIGNAL WAS | | RECEIVED ON LOW REACTOR WATER LEVEL. THIS IN TURN RESULTED IN GROUP II AND | | GROUP III ISOLATION SIGNALS WITH REACTOR BUILDING VENTILATION ISOLATION AND | | THE START OF THE STANDBY GAS TREATMENT SYSTEM. | | | | THE INSTRUMENT MAINTENANCE DEPARTMENT WAS PERFORMING A SURVEILLANCE ON | | REACTOR HIGH PRESSURE SWITCHES AT THE TIME OF THE FULL SCRAM. THE REACTOR | | HIGH PRESSURE SCRAM SWITCHES ARE LOCATED IN CLOSE PROXIMITY TO THE REACTOR | | LOW LEVEL SCRAM AND ISOLATION SWITCHES. ROOT CAUSE DETERMINATION IS IN | | PROGRESS. | | | | ALL SYSTEMS RESPONDED AS EXPECTED AS A RESULT OF THE FULL SCRAM SIGNAL. | | ACTUAL WATER LEVEL DID NOT DECREASE DURING THIS EVENT." | | | | THE LICENSEE STATED THAT SHUTDOWN COOLING WAS ISOLATED FOR APPROXIMATELY 14 | | MINUTES WITH NO DETECTABLE INCREASE IN WATER TEMPERATURE WHEN IT WAS | | RESTORED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+