U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/04/96 - 11/05/96 ** EVENT NUMBERS ** 31127 31273 31274 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31127 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/09/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 20:10 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/09/96 | +------------------------------------------------+EVENT TIME: 20:07[EDT]| |NRC NOTIFIED BY: JOE RUTTAR |LAST UPDATE DATE: 11/04/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PETER ESELGROTH RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LICENSEE DETERMINED THAT A LOSS OF INSTRUMENT AIR TO THE TURBINE DRIVEN | | AUXILIARY FEEDWATER PUMP (TDAFW) MAIN STEAM SUPPLY VALVES WOULD ALSO RESULT | | IN A LOSS OF CONTAINMENT ISOLATION. | | | | "LOSS OF INSTRUMENT AIR TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP MAIN | | STEAM SUPPLY VALVES CAUSES THESE VALVES TO FAIL OPEN. THESE VALVES CANNOT | | THEN PERFORM THEIR CONTAINMENT ISOLATION FUNCTION. CORRECTIVE ACTIONS ARE | | UNKNOWN AT THIS TIME." | | | | THE LICENSEE WILL INFORM STATE OFFICIALS AND HAS INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE 1252 11/4/96 FROM FRANKS TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. UPON FURTHER EVALUATION, THE | | LICENSEE HAS DETERMINED THAT THESE VALVES ARE DESIGNED TO FAIL OPEN IN | | ORDER TO PERMIT OPERATION OF THE TDAFW PUMP. THE NRC RESIDENT HAS BEEN | | INFORMED. THE HOO NOTIFIED R1DO (CONTE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31273 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 11/04/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:26 [ET]| |RX TYPE: [1] CE |EVENT DATE: 11/04/96 | +------------------------------------------------+EVENT TIME: 13:45[EST]| |NRC NOTIFIED BY: KOZUP |LAST UPDATE DATE: 11/04/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORDAN RDO | |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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SERVICE WATER SYSTEM ISOLATION VALVE FAILED TO STROKE WHEN TESTED | | | | WHILE TESTING THE NON-CRITICAL SERVICE WATER ISOLATION VALVE (CV-1359), THE | | VALVE FAILED TO STROKE. THE LICENSEE STATED THAT THE ASSOCIATED SOLENOID | | VALVE HAD FAILED TO REPOSITION THE VALVE. THIS VALVE ISOLATES THE | | NON-CRITICAL PORTION OF THE SERVICE WATER SYSTEM IN THE EVENT OF A SAFETY | | INJECTION SIGNAL. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31274 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/04/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:22 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/04/96 | +------------------------------------------------+EVENT TIME: 17:15[CST]| |NRC NOTIFIED BY: REIS |LAST UPDATE DATE: 11/04/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JORDAN RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RHR PUMP SEAL COOLERS NOT RATED FOR SYSTEM DESIGN PRESSURE. | | | | AN ENGINEERING ANALYSIS CONDUCTED BY THE LICENSEE DETERMINED THAT THE RHR | | PUMP SEAL COOLERS ARE NOT RATED FOR SYSTEM DESIGN PRESSURE. THE COOLERS ARE | | RATED TO 75 PSIG, WHILE THE RHR SYSTEM DESIGN PRESSURE IS 150 PSIG. THE | | LICENSEE DECLARED BOTH RHR SUBSYSTEMS INOPERABLE, AND HAS COMPLIED WITH ALL | | TECHNICAL SPECIFICATION ACTION STATEMENTS. THE LICENSEE PLANS TO REPLACE | | THE SEAL COOLERS WITH ONES HAVING THE PROPER PRESSURE RATING. THIS | | CONDITION HAS EXISTED SINCE INITIAL PLANT CONSTRUCTION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+