U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/04/95 - 01/05/95 ** EVENT NUMBERS ** 27666 28075 28208 28209 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27666 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 08/13/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 15:15 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/13/94 | +------------------------------------------------+EVENT TIME: 11:00[CDT]| |NRC NOTIFIED BY: BILLESBACH |LAST UPDATE DATE: 01/04/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 +------------------------------------------------------------------------------+ | THE POTENTIAL FOR DIRECT DISCHARGE TO THE SECONDARY CONTAINMENT EXISTS IN | | THE EVENT OF A HIGH ENERGY LINE BREAK IN THE PRIMARY CONTAINMENT. | | | | THE FOLLOWING IS THE TEXT OF A LICENSEE FAX. | | | | "A RE-ASSESSMENT OF THE CONDITION DESCRIBED IN INFORMATION NOTICE 89-055 | | AND THE ENSUING ENGINEERING EVALUATION PERFORMED IN 1989 HAS RESULTED IN | | THE CONCLUSION THAT THE 8" REACTOR EQUIPMENT COOLING (REC) PIPING IN THE | | DRYWELL ADJACENT TO THE REACTOR RECIRCULATION PUMP DISCHARGE PIPING IS | | SUSCEPTIBLE TO JET IMPINGEMENT FORCES IN THE EVENT OF A HIGH ENERGY LINE | | BREAK (HELB) INSIDE CONTAINMENT. SHOULD THAT SCENARIO OCCUR, THE REC | | PIPING COULD DIRECTLY COMMUNICATE WITH PRIMARY CONTAINMENT ATMOSPHERE AND | | BE SUBJECT TO THE PRIMARY CONTAINMENT PRESSURIZATION TRANSIENT. AS | | DESCRIBED IN INFORMATION NOTICE 89-055, THE WATER IN THE REC RETURN PIPING | | FROM THE DRYWELL WOULD BE DISCHARGED OUT OF THE SURGE TANK WHICH, AT CNS, | | IS LOCATED IN THE REACTOR BUILDING (SECONDARY CONTAINMENT) AT ELEVATION 976 | | FEET, EMPTYING THE PIPING AND SURGE TANK AND ALLOWING PRIMARY CONTAINMENT | | ATMOSPHERE TO BE DISCHARGED DIRECTLY TO SECONDARY CONTAINMENT. ON AUGUST | | 13, AT APPROXIMATELY 11:00 AM, THIS CONDITION WAS DETERMINED TO BE | | REPORTABLE. | | | | THIS BREACH OF PRIMARY CONTAINMENT WOULD OCCUR PRIOR TO CLOSURE OF THE | | SINGLE CONTAINMENT ISOLATION VALVE IN THE REC RETURN PIPING FROM THE | | DRYWELL, REC-MOV-709MV. WHILE A CHECK VALVE IN THE REC INLET PIPING TO THE | | DRYWELL WOULD PREVENT THE INLET PIPING FROM BEING PRESSURIZED, THE PRIMARY | | CONTAINMENT ATMOSPHERE WOULD CONTINUE TO BE DISCHARGED TO SECONDARY | | CONTAINMENT UNTIL REC-MOV-709MV WAS CLOSED USING THE REMOTE MANUAL CONTROL | | SWITCH IN THE CONTROL ROOM. (NO AUTOMATIC CLOSURE FEATURE FOR THIS VALVE | | IS PROVIDED; CLOSURE REQUIRES OPERATOR ACTION). IN THE EVENT OF A LOSS OF | | POWER TO THIS VALVE OR FAILURE OF THE MOTOR OPERATOR, THE BREACH OF PRIMARY | | CONTAINMENT WOULD BE NON-ISOLABLE. WITH RESPECT TO THE REC INLET PIPING TO | | THE DRYWELL, ACTUATION OF THE CONTROL SWITCH FOR REC-MOV-709MV ALSO CAUSES | | CLOSURE OF A MOTOR OPERATED VALVE IN THE INLET PIPING, REC-MOV-702MV, | | PROVIDING A SECOND CONTAINMENT ISOLATION BARRIER IN SERIES WITH THE INLET | | CHECK VALVE. | | | | AT THE PRESENT TIME, THE PLANT IS IN COLD SHUTDOWN WITH THE RHR SYSTEM IN | | SERVICE IN THE SHUTDOWN COOLING MODE OF OPERATION. AN EVALUATION TO | | MITIGATE THE EFFECTS OF THIS SCENARIO IS BEING PERFORMED AND THE CONDITION | | WILL BE RESOLVED PRIOR TO PLANT STARTUP. | | | | END OF FAX | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1458EST 1/4/95 FROM ROBERT GODLEY BY S.SANDIN * * * | | THE LICENSEE IS RETRACTING THIS EVENT AFTER SEVERAL DISCUSSIONS WITH NRR PM | | (RANDY HALL), FINALIZED ON 12/16/94, BASED ON NOT BEING A CREDIBLE ACCIDENT | | AND, THEREFORE, IS NOT REPORTABLE. THE LICENSEE WILL INFORM THE NRC | | RESIDENT INSPECTOR. NOTIFIED R4DO(SANBORN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28075 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/27/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 00:41 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/26/94 | +------------------------------------------------+EVENT TIME: 21:30[CST]| |NRC NOTIFIED BY: SMALLFOOT |LAST UPDATE DATE: 01/04/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED BOTH STANDBY GAS TREATMENT SYSTEMS("A" & "B") | | INOPERABLE DUE TO THE CHARCOAL BED DOORS BEING IN AN UNDOGGED CONDITION. | | | | THE "A" & "B" SGTS WAS DECLARED INOPERABLE BECAUSE OF THE CHARCOAL BED | | DOORS BEING FOUND IN THE UNDOGGED CONDITION (IT ALLOWS BOTH DOORS TO HAVE | | APPROXIMATELY ONE EIGHTH TO ONE QUARTER INCH MOVEMENT ON THE UNHINGED SIDE | | OF THE DOORS). THIS MOVEMENT MAY CAUSE THE DOORS TO NO LONGER MAKE | | COMPLETE CONTACT WITH ITS SEAL, THUS DOOR SEALING INTEGRITY CAN NOT BE | | ASSURED. THE LICENSEE RE-DOGGED BOTH DOORS TO RESTORE DOOR TO SEAL CONTACT, | | BUT UNTIL TESTING PER TS CAN BE PERFORMED, STANDBY GAS TRAINS "A" & "B" | | WILL NOT BE OPERABLE. | | | | THESE DOORS HAVE A LOCKING MECHANISM WHICH HAS A SLOTTED ARM THAT RESTRICTS | | MOVEMENT OF DOOR TO APPROXIMATELY ONE EIGHTH TO ONE QUARTER INCH. ALTHOUGH | | TS SEALING REQUIREMENTS CAN NOT BE ABSOLUTELY ASSURED, THE LIMITED DOOR | | MOVEMENT WOULD PROVIDE AN EXTREMELY RESTRICTED LEAKAGE PATH. THE LOCK IS | | CURRENTLY INSTALLED AND HAS NOT BEEN REMOVED. THE LOCK PREVENTED ACTUAL | | OPENING OF EITHER DOOR, SO SEALS WERE NOT EXPOSED AND THEREFORE NO DAMAGE | | TO SEALING SURFACES SHOULD HAVE OCCURRED. | | | | TESTING WILL BE PERFORMED TO CONFIRM DOOR SEAL INTEGRITY BEFORE EITHER | | STANDBY GAS TRAIN IS RESTORED TO AN OPERABLE STATUS, BUT UNTIL TESTING IS | | PERFORMED SGTS WILL BE IN AN AVAILABLE STATUS SINCE BOTH DOORS ARE LOCKED | | DOGGED. | | | | THE RI WAS INFORMED. | | | | * * * UPDATE 1458EST 1/4/95 FROM ROBERT GODLEY BY S.SANDIN * * * | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | THE STANDBY GAS TREATMENT SYSTEM WAS SUCCESSFULLY LEAK TESTED ON 9/15/94. | | THERE IS NO REASON TO BELIEVE THAT THE SYSTEM WOULD NOT HAVE BEEN ABLE TO | | PERFORM ITS SAFETY FUNCTION PRIOR TO THIS DATE IF CALLED UPON. AFTER | | 9/15/94, THE SBGT SYSTEM WAS NOT REQUIRED DUE TO PLANT CONDITIONS. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. NOTIFIED R4DO(SANBORN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28208 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 01/04/95 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 16:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/04/95 | +------------------------------------------------+EVENT TIME: 13:30[PST]| |NRC NOTIFIED BY: GARY ANDERSON |LAST UPDATE DATE: 01/05/95 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF EMERGENCY SIREN CAPABILITY DUE TO LOCAL POWER OUTAGES CAUSED BY | | ADVERSE WEATHER CONDITIONS. | | | | DUE TO LOCAL OUTAGES, MORE THAN ONE-HALF (>75) OF THE EARLY WARNING SIRENS | | HAVE BEEN OUT OF SERVICE FOR MORE THAN ONE HOUR. THE LICENSEE (AN EMERGENCY | | PLANNER) IS MONITORING THE SITUATION FROM THE EOF. THE LICENSEE WILL INFORM | | THE NRC RESIDENT INSPECTOR. | | | | ** UPDATE DATE\TIME:1/5/95 @ 0318 EST ***FROM LICENSEE:DYE BY:McGINTY** | | AT 2024 PST, ONLY 35 OF 131 EARLY WARNING SIRENS REMAINED INOPERABLE DUE TO | | THE POWER OUTAGES. THE REMAINING SIRENS THAT ARE OUT AFFECT ONLY ABOUT 800 | | PEOPLE (THE REMAINING SIRENS WOULD AFFECT ABOUT 100,000 PEOPLE). THE | | LICENSEE WILL INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28209 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 01/05/95 | |UNIT: [ ] [2] [ ] STATE: TN |NOTIFICATION TIME: 01:59 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/05/95 | +------------------------------------------------+EVENT TIME: 00:15[EST]| |NRC NOTIFIED BY: HARRIS |LAST UPDATE DATE: 01/05/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR TRIP DUE TO MAIN BANK TRANSFORMER "B" PHASE | | DIFFERENTIAL RELAY OPERATION. | | | | AT 0015 EST ON 1/5/95, UNIT 2 EXPERIENCED A TURBINE TRIP/REACTOR TRIP DUE | | TO MAIN BANK TRANSFORMER "B" PHASE DIFFERENTIAL RELAY OPERATION. THE | | TURBINE FIRST OUT ANNUNCIATOR WAS "ELECTRICAL TROUBLE TURBINE TRIP", AND | | THE REACTOR TRIP FIRST OUT WAS THE "TURBINE TRIP REACTOR TRIP". NO | | ABNORMALITIES WERE NOTED DURING THE PLANT TRANSIENT AND ALL SAFETY SYSTEMS | | PERFORMED AS DESIGNED. THE PLANT IS CURRENTLY STABLE AT 547F AND 2235 | | PSIG. | | | | STEAM IS BEING REMOVED VIA THE MAIN STEAM DUMPS TO THE MAIN CONDENSER, AND | | THE GENERATORS ARE BEING FED BY AUXILIARY FEEDWATER (AFW AUTO-STARTED AS | | EXPECTED ON THE FEEDWATER ISOLATION WHEN Tavg DROPPED BELOW 550F). ALL | | ECCS's AND EDG's ARE OPERABLE. NO PRIMARY OR SECONDARY RELIEF VALVES | | LIFTED IN RESPONSE TO THE TRANSIENT, AND THERE WERE NO PROBLEMS WITH BUS | | TRANSFERS. ALL RODS FULLY INSERTED INTO THE CORE. | | | | THE LICENSEE WILL BE INVESTIGATING THE CAUSE OF THE PLANT TRIP, WITH A | | RESTART PENDING THE RESULTS OF THE INVESTIGATION. THE LICENSEE INFORMED | | THE RESIDENT INSPECTOR. | | | | HOO NOTE: DURING THE MORNING PLANT STATUS CALL, THE LICENSEE INDICATED | | THAT A LOOSE LIGHT SOCKET ON THE TURBINE BENCHBOARD PANEL MAY HAVE BEEN THE | | CAUSE AND THAT THE PLANT MAY BE STARTED UP LATER TODAY. | +------------------------------------------------------------------------------+