U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/29/95 - 11/30/95 ** EVENT NUMBERS ** 29652 29653 29654 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29652 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 11/29/95 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 03:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/28/95 | +------------------------------------------------+EVENT TIME: 22:15[PST]| |NRC NOTIFIED BY: BOB MAGRUDER |LAST UPDATE DATE: 11/29/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 50 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIPPED MANUALLY IN ANTICIPATION OF AN AUTOMATIC TRIP FOLLOWING THE | | LOSS OF A MAIN FEEDWATER PUMP. | | | | THE UNIT HAD REACHED 50% POWER AND WAS STABLE FOLLOWING A REFUELING OUTAGE. | | ONE MAIN FEEDWATER PUMP WAS IN SERVICE, AND THE OTHER PUMP WAS OUT OF | | SERVICE FOR MAINTENANCE. THE OPERATING PUMP TRIPPED FOR REASONS THAT ARE | | NOT YET UNDERSTOOD. THE OPERATORS MANUALLY TRIPPED THE REACTOR IN | | ANTICIPATION OF A LOW-LOW STEAM GENERATOR LEVEL AUTOMATIC TRIP. ALL | | CONTROL RODS INSERTED FULLY FOLLOWING THE TRIP. DECAY HEAT REMOVAL IS VIA | | STEAM DUMP VALVES TO THE MAIN CONDENSER. | | | | EMERGENCY DIESEL GENERATOR (EDG) "1-1" STARTED DUE TO LOW VOLTAGE ON BUS 1. | | EDG "1-1" DID NOT LOAD BECAUSE VOLTAGE TO BUS 1 RECOVERED DURING THE EDG | | START SEQUENCE. THE LICENSEE SUSPECTS THAT THE AUTOMATIC TRANSFER OF BUS 1 | | FROM THE MAIN TRANSFORMER TO THE STARTUP TRANSFORMER IS SLIGHTLY SLOWER | | THAN THE ACTUATION OF THE UNDER VOLTAGE RELAY THAT STARTS THE EDG. SIMILAR | | STARTS OF EDG "1-1" HAVE BEEN OBSERVED BY THE LICENSEE IN THE PAST. ALL | | AUXILIARY FEEDWATER PUMPS ALSO STARTED DUE TO SHRINK IN THE STEAM | | GENERATORS FOLLOWING THE REACTOR TRIP. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29653 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COOPER ENERGY SERVICES |NOTIFICATION DATE: 11/29/95 | | CITY: GROVE CITY REGION: 1 |NOTIFICATION TIME: 13:30 [ET]| | COUNTY: STATE: PA |EVENT DATE: 11/06/95 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/29/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LARRY NICHOLSON (R1) RDO | | |GUS LAINAS (NRR) EO | +------------------------------------------------+KERRY LANDIS R2DO | |NRC NOTIFIED BY: ANDREW STEFFAN/FACSIMILE |VERN HODGE (PCEB) NRR | |HQ OPS OFFICER: LEIGH TROCINE |MARTIN FARBER R3DO | +------------------------------------------------+LAWRENCE YANDELL R4DO | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT FROM COOPER ENERGY SERVICES REGARDING A POTENTIAL | | DESIGN DEFECT OF THE KSV EMERGENCY DIESEL GENERATOR SYSTEM | | | | ON NOVEMBER 6, 1995, BRAIDWOOD REPORTED TO COOPER ENERGY SERVICES THAT | | DURING MAINTENANCE ACTIVITIES, EXCESSIVE WEAR AND RUST WAS NOTED IN THE | | UPPER PORTION OF THE GOVERNOR DRIVE ASSEMBLY (ASSEMBLY NO. KSV-17-6). THE | | FOLLOWING DAY, BRAIDWOOD REPORTED THAT THE OIL HOLE IN THE TOP FLANGE OF | | THE BEARING RETAINER DID NOT APPEAR TO EXTEND THROUGH THE INSIDE OF THE | | FLANGE. THE REPORT INDICATED THAT THIS WAS DUE TO A SLEEVE REPAIR OF THE | | BORE BLOCKING THE OIL HOLE. | | | | THE LACK OF OIL IN THIS AREA COULD RESULT IN FAILURE OF THIS ASSEMBLY WHICH | | IN TURN COULD RESULT IN EMERGENCY DIESEL GENERATOR INOPERABILITY. DUE TO | | THE POTENTIAL OF THIS DEFECT AND THE EASE OF VERIFICATION, COOPER ENERGY | | SERVICES HAS RECOMMENDED THAT ALL UTILITIES VERIFY AN OPEN OIL PASSAGE IN | | THIS ASSEMBLY. COOPER ENERGY SERVICES HAS ALSO RECOMMENDED THAT ALL | | UTILITIES VERIFY THE SIMILAR OVERSPEED GOVERNOR AND DRIVE ASSEMBLY (NO. | | KVS-17-7). | | | | THE ASSEMBLY IS INSTALLED ON ALL COOPER-BESSEMER KSV EMERGENCY DIESEL | | GENERATORS EXCEPT AT ZION AND COOPER. SIMILAR ASSEMBLIES FOR THESE | | STATIONS ARE NO. KVS-17-1 AT ZION AND COOPER, NO. KVS-17-2 AT ZION, AND NO. | | KVS-17-5 AT COOPER. | | | | THE NRC OPERATIONS CENTER ALSO NOTIFIED THE REGION 4 FIELD OFFICE (RANDY | | HUEY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29654 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/29/95 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 17:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/29/95 | +------------------------------------------------+EVENT TIME: 00:00[EST]| |NRC NOTIFIED BY: SAUER |LAST UPDATE DATE: 11/29/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NICHOLSON RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE | | | | AFTER REVIEWING EMERGENCY DIESEL GENERATOR (EDG) RUN DATA, THE LICENSEE HAS | | DETERMINED THAT THE GENERATORS MAY HAVE BEEN OPERATED WITH A PHASE | | AMPLITUDE IMBALANCE GREATER THAN THE MANUFACTURER'S RECOMMENDATION. THIS | | COULD LEAD TO EVENTUAL ROTOR DAMAGE IN THE GENERATORS. THE LICENSEE'S | | INVESTIGATION SUGGESTS THAT THIS CONDITION ONLY OCCURS WHEN THE EDGs ARE | | RUN WHILE THE UNITS ARE SHUT DOWN DUE TO ELECTRICAL BUS ALIGNMENTS. | | | | THE ENGINEERING DEPARTMENT IS CONTINUING TO INVESTIGATE THE EXACT CAUSE OF | | THE CONDITION. THE LICENSEE DOES NOT BELIEVE THAT THE PROBLEM IS BEING | | CAUSED BY THE GENERATORS BUT THAT THE GENERATORS ARE SUBJECTED TO THE | | CONDITION WHEN LOADED TO THE ELECTRICAL BUSES. THE LICENSEE HAS DECLARED | | ALL EDGs INOPERABLE AND IS IN THE PROCESS OF ESTABLISHING CONTAINMENT | | INTEGRITY IN UNIT 2. THE LICENSEE PLANS TO INSPECT EACH OF THE GENERATOR | | ROTORS FOR ANY DAMAGE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+