U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/03/96 - 10/04/96 ** EVENT NUMBERS ** 30996 31084 31085 31086 31087 31088 31089 31090 31091 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30996 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/12/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:30 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/12/96 | +------------------------------------------------+EVENT TIME: 14:12[EDT]| |NRC NOTIFIED BY: TABONE |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |COSTELLO 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 +------------------------------------------------------------------------------+ | OPERATION IN SUPPRESSION POOL COOLING MODE OF RHR PLACES UNIT OUTSIDE OF | | DESIGN BASIS. | | | | THE LICENSEE HAS DETERMINED THAT OPERATION OF THE PLANT IN THE SUPPRESSION | | POOL (TORUS) COOLING MODE OF RHR PLACES THE UNIT OUTSIDE OF ITS DESIGN | | BASIS. SPECIFICALLY, IN THE EVENT OF A DC POWER FAILURE, THE TORUS TEST | | RETURN VALVES WOULD NOT CLOSE. THIS CONDITION IN CONJUNCTION WITH A LOCA | | WOULD CAUSE THE LPCI MODE OF RHR TO INJECT LESS WATER TO THE REACTOR VESSEL | | THAN ASSUMED IN THE ACCIDENT ANALYSIS. THE LICENSEE PLANS TO EVALUATE THIS | | PROBLEM. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1102 10/3/96 FROM McCOLLUM TAKEN BY STRANSKY * * * | | | | THE LICENSEE WISHES TO RECLASSIFY THE REPORTABILITY OF THIS EVENT FROM 10 | | CFR 50.72(b)(1)(ii) [DEGRADED CONDITION DURING OPERATION] TO 50.72(b)(2)(i) | | [DEGRADED CONDITION FOUND WHILE SHUT DOWN]. FURTHER, THE LICENSEE CLARIFIED | | THAT THIS FINDING PLACES THE UNIT IN AN UNANALYZED CONDITION, NOT OUTSIDE | | OF ITS DESIGN BASIS. NOTIFIED R1DO (JOYNER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31084 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 10/03/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 11:47 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 10/03/96 | +------------------------------------------------+EVENT TIME: 10:45[EDT]| |NRC NOTIFIED BY: RICCI |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING A REVIEW OF THEIR USAR, THE LICENSEE DETERMINED THAT FIGURE 9.4-13 | | WAS IN ERROR. | | | | THE INCORRECT VALUE RESULTED IN A CALCULATED MAXIMUM OPENING IN THE CONTROL | | ROOM NEGATIVE PRESSURE AREA TO BE AT 200 SQ.IN. THE PRELIMINARY | | CALCULATION USING THE CORRECTED FIGURE RESULTED IN A CONTROL ROOM NEGATIVE | | PRESSURE AREA OF 40 SQ.IN. AT THE TIME, DUE TO ONGOING MAINTENANCE, THEY | | HAD A TOTAL OPENING OF 82.65 SQ.IN. WHICH RESULTED IN BOTH TRAINS OF THE | | CONTROL ROOM EMERGENCY VENT SYSTEM BEING DECLARED INOPERABLE. AT 10:45 THE | | PLANT ENTERED TS 3.0.3 AND INFORMED MAINTENANCE TO BACK DOWN FROM THEIR MWO | | AND CLOSE UP THE HOLE. THE OPENING WAS REDUCED TO 15.4 SQ.IN. AT 11:25 AND | | TS 3.0.3 WAS EXITED. THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31085 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/03/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 12:19 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/03/96 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: JOE BERGIN |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM GENERATOR SAFETY VALVE SETPOINT DOES NOT CONSIDER PIPING RUN | | | | A REVIEW OF THE STEAM GENERATOR DESIGN FOUND THAT THE PRESSURE DROP BETWEEN | | THE STEAM GENERATOR AND THE SAFETY VALVES WAS NOT TAKEN INTO ACCOUNT IN | | DETERMINING THE SAFETY VALVES' SETPOINTS. THIS ERROR WAS DISCOVERED IN THE | | ANALYSIS FOR A SINGLE MSIV CLOSURE AT POWER. THE ADDITIONAL PRESSURE DROP | | COULD BE AS HIGH AS 100 TO 150 PSID. THE RESULTING STEAM GENERATOR | | PRESSURE WOULD EXCEED 110% OF ASME DESIGN PRESSURE. | | | | THE UNIT'S STEAM GENERATORS WERE REPLACED IN 1991-92. THIS CONDITION | | EXISTED ON THE OLD STEAM GENERATORS AND WAS WORSE. THE AMOUNT OF | | ADDITIONAL PRESSURE DROP ON THE OLD STEAM GENERATORS WAS NOT IMMEDIATELY | | AVAILABLE. | | | | STATE AND LOCAL GOVERNMENTS WERE NOTIFIED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31086 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/03/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 15:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/03/96 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: MIKE DAMMANN |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | BOTH TRAINS OF CONTROL ROOM EMERGENCY VENTILATION INOPERABLE | | | | THE LICENSEE DETERMINED THAT ON TWO DATES, 4/11/96 AND 8/5/96, BOTH TRAINS | | OF THE CONTROL ROOM EMERGENCY RECIRCULATION SYSTEM (CRERS) WERE INOPERABLE. | | WHEN THE DIVISION II SUPPLY BREAKER FOR CRERS TRIPPED ON 9/16/96, AN | | INVESTIGATION REVEALED THAT THE BREAKER WAS INOPERABLE SINCE INSTALLATION | | IN MARCH 96. THE CAUSE OF THE INOPERABILITY WAS A MIS-WIRING OF THE | | OVERCURRENT TRIP UNIT IN THE BREAKER. THE BREAKER WAS SUPPLIED BY ABB WHO | | HAS BEEN INFORMED OF THIS PROBLEM. | | | | THE LICENSEE DISCOVERED THAT DIV I CRERS WAS INOPERABLE ON 4/11/96 AND | | 8/5/96. THEREFORE, THIS SYSTEM WOULD NOT HAVE BEEN ABLE TO PERFORM ITS | | SAFETY FUNCTION ON THESE TWO DAYS. THE LICENSEE ALSO REPORTED THIS EVENT | | AS A 24 HOUR REPORT BECAUSE OF THE TECH SPEC VIOLATION ASSOCIATED WITH THE | | LOSS OF SAFETY FUNCTION. | | | | THE DIVISION II BREAKER HAS SINCE BEEN REPLACED AND IS NOW OPERABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31087 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 10/03/96 | |UNIT: [1] [ ] [3] STATE: SC |NOTIFICATION TIME: 17:15 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 10/03/96 | +------------------------------------------------+EVENT TIME: 16:45[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRESS RELEASE ISSUED ON SHUTTING DOWN UNITS 1 & 3 | | | | OCONEE ISSUED A PRESS RELEASE AT APPROXIMATELY 1645 TODAY STATING THAT THEY | | WILL BE SHUTTING DOWN UNITS 1 & 3. THE UNITS WILL BE SHUTDOWN TO FURTHER | | EVALUATE THE SAME SYSTEMS THAT WERE INVOLVED IN THE STEAM ACCIDENT ON UNIT | | 2 ON SEPTEMBER 24, 1996. THE UNITS WILL BE REMOVED FROM SERVICE TO | | COMPLETE THE EVALUATION AND TO MAKE MODIFICATIONS AS NEEDED. | | | | THEY EXPECT TO TAKE UNIT 1 OFF LINE TONIGHT AND UNIT 3 TOMORROW NIGHT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31088 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 10/03/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 17:18 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/03/96 | +------------------------------------------------+EVENT TIME: 12:33[CDT]| |NRC NOTIFIED BY: TERRY HALCOMBE |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAINMENT SAMPLE SYSTEM INOPERABLE | | | | THE POST ACCIDENT SAMPLE SYSTEM (PASS) PUMP FAILED AT 1233 CDT TODAY. THE | | LICENSEE DETERMINED THAT THE PUMP WOULD NOT BE ABLE TO BE REPAIRED WITHIN | | EIGHT HOURS AT 1555 CDT. THIS PUMP IS USED TO OBTAIN SAMPLES OF THE | | CONTAINMENT ATMOSPHERE. A REPLACEMENT PUMP IS NOT IMMEDIATELY AVAILABLE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31089 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PACIFIC SCIENTIFIC |NOTIFICATION DATE: 10/03/96 | | CITY: YORBA LINDA REGION: 4 |NOTIFICATION TIME: 17:31 [ET]| | COUNTY: STATE: CA |EVENT DATE: 10/03/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:00[PDT]| | DOCKET: |LAST UPDATE DATE: 10/03/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: BILL SCOTT |VERN HODGE NRR | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TELEPHONE REPORT OF A PART 21 ON SNUBBERS | | | | PACIFIC SCIENTIFIC NOTIFIED THE OPERATIONS CENTER THAT A COMPONENT IN THEIR | | PSA-35 SNUBBERS MAY BE DEFECTIVE. THE COMPONENT IN QUESTION IS PART OF THE | | THRUST BEARING ASSEMBLY AND ITS PART NUMBER IS 1801461-01. THIS COMPONENT | | MAY FAIL IN SUCH A WAY THAT THE SNUBBER WOULD BECOME INOPERABLE. | | | | EIGHTEEN SUSPECT SNUBBERS HAVE BEEN SHIPPED SINCE MAY 1995. THE COMPANIES | | RECEIVING THEM WERE COMMONWEALTH EDISON, DETROIT EDISON, GEORGIA POWER & | | LIGHT, CLEVELAND ELECTRIC AND A PROJECT IN KOREA (NO NAME GIVEN). | | | | A CONTACT PHONE NUMBER IS AVAILABLE IN THE HOO LOG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31090 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 10/03/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 22:00 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 10/03/96 | +------------------------------------------------+EVENT TIME: 18:20[EDT]| |NRC NOTIFIED BY: JEFF GROFF |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - CLOSURE OF A RECIRC PUMP ISOLATION VALVE | | | | ON 10/3/96, AT 1820, THE B31-F014A "RECIRC PUMP "A" INBOARD ISOLATION | | VALVE" CLOSED. AT THE TIME OF CLOSURE, TROUBLE SHOOTING WAS BEING | | PERFORMED ON B31-F014B "RECIRC PUMP "B" INBOARD ISOLATION VALVE" WITH AN | | APPROVED WORK PACKAGE. AN INVESTIGATION REVEALED THAT A LEAD, WHICH IS | | COMMON TO BOTH VALVES, WAS LIFTED, THEREBY DE-ENERGIZING AND CLOSING | | B31-F014A. THIS IS A DIVISION I PRIMARY CONTAINMENT ISOLATION VALVE. THE | | REACTOR RECIRCULATION SEAL PURGE SYSTEM WAS ALREADY REMOVED FROM SERVICE BY | | APPROVED PLANT PROCEDURES AT THE TIME OF THE EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31091 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 10/03/96 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 22:17 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/03/96 | +------------------------------------------------+EVENT TIME: 20:52[EDT]| |NRC NOTIFIED BY: MICHAEL S. BECKER |LAST UPDATE DATE: 10/03/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SINGLE FAILURE COULD CAUSE THE LOSS OF TWO CHARGING PUMPS | | | | AT 2052 ON 10/3/96, DURING THE INVESTIGATION OF A TRIP OF THE U2 "C" | | CHARGING PUMP, AN ANOMALY WAS IDENTIFIED IN THE CHARGING PUMP INTERLOCK | | CIRCUIT LOGIC. THE "C" CHARGING PUMP IS A SWING PUMP WHICH MAY BE POWERED | | FROM EITHER THE "H" OR THE "J" EMERGENCY BUS. THE "A" CHARGING PUMP IS | | ALWAYS POWERED FROM THE "H" BUS AND THE "B" PUMP IS ALWAYS POWERED FROM THE | | "J" BUS. THIS ANOMALY IS APPLICABLE TO BOTH UNITS AND WOULD OCCUR AS | | FOLLOWS: | | | | IF THE "C" PUMP IS RUNNING AND ITS ASSOCIATED BUS PUMP IS OUT OF SERVICE, A | | TECH SPEC ACTION STATEMENT IS NOT REQUIRED (ONLY TWO OPERABLE PUMPS ARE | | REQUIRED); THEREFORE THE SYSTEM MUST BE ABLE TO WITHSTAND A SINGLE FAILURE. | | | | IF THE SINGLE FAILURE IS A LOSS OF A DC BUS (CONTROL POWER TO THE BUS | | WITHOUT THE "C" PUMP), NO CHARGING PUMPS WOULD REMAIN RUNNING AFTER THE | | FAILURE. THE "C" PUMP WOULD TRIP BECAUSE IT WOULD RECEIVE A SIGNAL THAT THE | | OPPOSITE SIDE POWER SUPPLY BREAKER WAS RACKED IN. THE OTHER PUMP WOULD TRIP | | BECAUSE OF A LOSS OF CONTROL POWER. | | | | AN INFORMATION ONLY ACTION STATEMENT HAS BEEN ENTERED ON BOTH UNITS TO | | PREVENT A SUSCEPTIBLE PUMP LINE-UP. THE "C" CHARGING PUMPS WILL NOT BE | | CONSIDERED OPERABLE IF THEY ARE RUNNING. ENGINEERING IS PERFORMING A | | REVIEW OF THE CONDITION FOR CORRECTIVE ACTION RECOMMENDATIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+