U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/27/95 - 11/28/95 ** EVENT NUMBERS ** 29518 29524 29642 29643 29644 29645 29646 29647 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29518 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/28/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 01:33 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/27/95 | +------------------------------------------------+EVENT TIME: 23:50[EDT]| |NRC NOTIFIED BY: MATHEW MORGAN |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD BELLAMY 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOW SEAL WATER PRESSURE TO THE '21A' SERVICE WATER PUMP TRIGGERED ACTUATION | | OF THE BACK-UP SUPPLY. | | | | SERVICE WATER PUMP '21A' REGISTERED A LOW SEAL WATER PRESSURE ALARM WHEN A | | BREAK IN AN AIR LINE CAUSED THE NORMAL SEAL WATER SUPPLY VALVE TO CLOSE. | | THE BACK-UP SYSTEM AUTOMATICALLY RESTORED THE SEAL WATER SUPPLY (AN ESF | | ACTUATION). THE BACK-UP SOURCE OF SEAL WATER IS THE SERVICE WATER PUMP | | DISCHARGE. THE CAUSE OF THE AIR LINE BREAK IS UNDER INVESTIGATION BY THE | | LICENSEE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 15:54 NOVEMBER 27, 1995, UPDATE FROM DULICK TAKEN BY TROCINE * * * | | | | THIS EVENT IS BEING RETRACTED. THE LICENSEE HAS REVIEWED THIS EVENT AND | | HAS DETERMINED THAT THE SIGNALS WERE NOT VALID ESF SIGNALS. THE SIGNALS | | WERE ACTUALLY LOW PRESSURE SIGNALS, AND THEY DID NOT COME FROM THE SOLID | | STATE PROTECTION SYSTEM WHICH TELLS THE PUMPS TO SWAP. THEREFORE, BY THE | | GUIDANCE IN NUREG 1022, THIS EVENT IS NOT REPORTABLE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (NICHOLSON). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29524 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 10/30/95 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 10/30/95 | +------------------------------------------------+EVENT TIME: 11:30[EST]| |NRC NOTIFIED BY: TOM RESTUCCIO |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED INOPERABILITY OF A SINGLE TRAIN SAFETY SYSTEM, HIGH PRESSURE CORE | | SPRAY (HPCS) | | | | DURING THE PERFORMANCE OF A PRE-PLANNED SURVEILLANCE TEST, SERVICE WATER | | SYSTEM VALVES 2SWP*V201A AND 2SWP*V201B FAILED THE REVERSE FLOW TEST. THESE | | VALVES ARE CHECK VALVES LOCATED ON THE INLET COOLING WATER SUPPLY LINE TO | | DIVISION III EMERGENCY SWITCHGEAR UNIT COOLER 2HVC*UC102. THIS UNIT COOLER | | PROVIDES VENTILATION TO THE DIVISION III SWITCHGEAR AND CABLE AREAS. THE | | UNIT COOLER FAN IS NORMALLY RUNNING AND RECIRCULATES THE AIR IN THE | | SWITCHGEAR AND CABLE AREAS. COOLING WATER IS SUPPLIED TO THE UNIT COOLER | | BY THE SERVICE WATER SYSTEM. | | | | AT 08:46, THE DIVISION III EMERGENCY SWITCHGEAR WAS DECLARED INOPERABLE DUE | | TO THE PRE-PLANNED SURVEILLANCE TESTING. AT 11:30, THE LICENSEE FOUND THAT | | VALVES 2SWP*V201A AND 2SWP*V201B HAD FAILED THE REVERSE FLOW REQUIREMENTS. | | PER TECHNICAL SPECIFICATION 3.8.3.1, WITH THE DIVISION III EMERGENCY | | SWITCHGEAR INOPERABLE, THE LICENSEE DECLARED THE HPCS SYSTEM INOPERABLE AND | | INITIATED THE ACTIONS REQUIRED BY TECHNICAL SPECIFICATION 3.5.1. PROVIDED | | EMERGENCY CORE COOLING SYSTEM (ECCS) DIVISIONS I AND II AND THE REACTOR | | CORE ISOLATION COOLING SYSTEM ARE OPERABLE WITH THE ECCS DIVISION III | | (HPCS) INOPERABLE, TECHNICAL SPECIFICATION 3.5.1 REQUIRES THE LICENSEE TO | | RESTORE THE INOPERABLE DIVISION TO OPERABLE STATUS WITHIN 14 DAYS. | | | | THE LICENSEE INITIATED REPAIR ACTIONS TO CORRECT THESE FAILURES, AND A WORK | | REQUEST WAS INITIATED TO HAVE THESE VALVES CLEANED. FOLLOWING CLEANING, | | THE LICENSEE FOUND SOME ZEBRA MUSSELS ON THE CHECK VALVES, AND THE SPRINGS | | ON THE CHECK WERE ALSO CORRODED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 18:00 NOVEMBER 27, 1995, UPDATE FROM DRAGOMER TAKEN BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE LICENSEE'S ENGINEERING | | CALCULATIONS DEMONSTRATED THAT THE HPCS SYSTEM WAS IN FACT OPERABLE EVEN | | WITH THE REDUCED SERVICE WATER FLOW RESULTING FROM THE FAILED CHECK VALVES. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R1DO (NICHOLSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29642 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 11/27/95 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 02:33 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 11/26/95 | +------------------------------------------------+EVENT TIME: 21:00[MST]| |NRC NOTIFIED BY: ECKLUND |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BARNES 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP FROM 35% POWER AND MAIN STEAM ISOLATION DUE TO HIGH | | STEAM GENERATOR WATER LEVEL | | | | AT APPROXIMATELY 2100 MST WITH THE UNIT OPERATING AT 100% POWER, THE MAIN | | TURBINE TRIPPED. THE TURBINE TRIP WAS DUE TO A LOW VACUUM CONDITION IN THE | | MAIN CONDENSER. A REACTOR POWER CUTBACK TO 35% WAS INITIATED UPON THE | | TURBINE TRIP. THE STEAM BYPASS CONTROL SYSTEM ACTUATED TO CONTROL STEAM | | GENERATOR PRESSURE; HOWEVER, DUE TO THE LOW CONDENSER VACUUM CONDITION, | | STEAM BYPASS CONTROL VALVES 1001 - 1006 WERE LOCKED OUT LEAVING ONLY VALVES | | 1007 AND 1008 OPEN TO CONTROL PRESSURE. THIS RESULTED IN A SECONDARY | | SYSTEM PRESSURE INCREASE WHICH CAUSED FOUR OF THE MAIN STEAM SAFETY VALVES | | TO OPEN. THE LARGE INCREASE IN STEAM FLOW CAUSED BY THE OPENING OF THE | | MAIN STEAM SAFETY VALVES CAUSED STEAM GENERATOR LEVELS TO SWELL, AND THE | | UNIT RECEIVED A REACTOR TRIP AND MAIN STEAM ISOLATION ON STEAM GENERATOR #2 | | HIGH LEVEL AT 2107 MST. | | | | ALL CONTROL RODS INSERTED FOLLOWING THE TRIP, AND ALL SYSTEMS FUNCTIONED AS | | EXPECTED. OPERATORS MANUALLY INITIATED THE AUXILIARY FEEDWATER SYSTEM TO | | MAINTAIN STEAM GENERATOR WATER LEVELS. THE LICENSEE IS CURRENTLY | | INVESTIGATING THE CAUSE OF THE LOSS OF MAIN CONDENSER VACUUM. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE 0607 EST 11/27/95 * * * | | | | THE LICENSEE CALLED TO CORRECT INFORMATION PROVIDED IN THE INITIAL | | NOTIFICATION. THE REACTOR TRIP WAS CAUSED BY A HIGH LEVEL IN THE #1 STEAM | | GENERATOR, NOT THE #2 STEAM GENERATOR, AS HAD BEEN EARLIER REPORTED. | | NOTIFIED R4DO (BARNES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29643 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/27/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 04:55 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/27/95 | +------------------------------------------------+EVENT TIME: 01:49[CST]| |NRC NOTIFIED BY: BAILEY |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CLAYTON RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION DUE TO PERSONNEL ERROR | | (REFER TO EVENT NUMBER 29646 FOR ADDITIONAL INFORMATION.) | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "DURING THE PERFORMANCE OF A SURVEILLANCE ON THE REACTOR CORE ISOLATION | | COOLING (RCIC) STEAM LINE FLOW INSTRUMENTATION, THE CONTROL ROOM OPERATOR | | FAILED TO RESET THE LOGIC PRIOR TO HAVING THE BREAKER FOR THE VALVE | | ENERGIZED. THIS RESULTED IN AN ESF SIGNAL TO AUTOMATICALLY CLOSE THE RCIC | | STEAM INBOARD ISOLATION VALVE 2E51-F063. THE ISOLATION LOGIC WAS RESET, | | THE VALVE WAS REOPENED, AND THE SYSTEM ALIGNED FOR STANDBY OPERATION." | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29644 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 11/27/95 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 13:58 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/27/95 | +------------------------------------------------+EVENT TIME: 11:50[EST]| |NRC NOTIFIED BY: BILL CORBIN |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF AN UNPLANNED EMERGENCY SIREN ACTIVATION | | | | AT APPROXIMATELY 11:50, EMERGENCY SIREN #54 ACTIVATED FOR NO APPARENT | | REASON. WORK WAS BEING PERFORMED BY THE TELECOMMUNICATIONS DEPARTMENT AT | | THE SPOTSYLVANIA COUNTY 911 CENTER. THIS WAS AN UNPLANNED SIREN | | ACTIVATION. IN ADDITION, THE SIREN DID NOT SOUND CORRECTLY IN THAT THERE | | WAS NOT A LEVEL CONTINUOUS TONE AS EXPECTED. | | | | THE LICENSEE HAS INITIATED ELECTRONIC POLLS TO DETERMINE THE EXTENT OF THE | | ACTIVATION AND HAS DIRECTED TELECOMMUNICATIONS TO CEASE ALL TESTING. THE | | CAUSE OF THE UNPLANNED ACTIVATION IS STILL UNDER INVESTIGATION. | | | | THE STATE DEPARTMENT OF EMERGENCY SERVICES WAS NOTIFIED THAT THE ACTIVATION | | WAS NOT PLANNED OR REQUIRED. THE LICENSEE ALSO NOTIFIED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29645 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 11/27/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/27/95 | +------------------------------------------------+EVENT TIME: 15:20[EST]| |NRC NOTIFIED BY: THOMAS B. MARSHALL |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK (R2) RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ELINOR ADENSAM (NRR) EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |GARY BELCHER FEMA | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |ROGER HANNAH (R2) PAO | | |JOE GIITTER (ACTING) ERB | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED BASED ON POTENTIAL DEGRADATION OF PLANT SAFETY DUE | | TO ARCING ON THE UNIT 1 GENERATOR EXCITER | | | | AT APPROXIMATELY 1512, THE LICENSEE STARTED TO REDUCE REACTOR POWER FROM | | 100% DUE TO BALANCE-OF-PLANT INDICATION SWINGS. (BALANCE-OF-PLANT SYSTEMS | | WERE STABLE.) ARCING WAS DISCOVERED IN THE GENERATOR EXCITER AT 1515, AND | | A NOTICE OF UNUSUAL EVENT WAS DECLARED AT 1520 BASED ON POTENTIAL | | DEGRADATION OF PLANT SAFETY. UNIT 1 POWER WAS REDUCED TO LESS THAN 50%, | | AND THE LICENSEE MANUALLY TRIPPED THE TURBINE WITH THE REACTOR AT | | APPROXIMATELY 45% POWER. (AN AUTOMATIC REACTOR TRIP ON A TURBINE TRIP | | OCCURS WHEN THE REACTOR IS AT GREATER THAN 50% POWER.) THE UNUSUAL EVENT | | WAS TERMINATED AT 1539 WHEN THE EXCITER FIELD BREAKER WAS OPENED. FOLLOWING | | THE TURBINE TRIP, BOTH STEAM GENERATOR FEEDWATER PUMPS WERE TRIPPED. THIS | | IN TURN CAUSED AN AUTOMATIC START SIGNAL FOR THE AUXILIARY FEEDWATER SYSTEM | | WHICH HAD PREVIOUSLY BEEN STARTED MANUALLY. OTHER THAN THE ARCING IN THE | | GENERATOR EXCITER, ALL SYSTEMS FUNCTIONED AS REQUIRED. A FOLLOWUP | | INVESTIGATION IS CURRENTLY IN PROGRESS. | | | | THE UNIT IS CURRENTLY STABLE AT APPROXIMATELY 1% REACTOR POWER IN MODE 2. | | AUXILIARY FEEDWATER IS BEING SUPPLIED TO THE STEAM GENERATORS, AND | | SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER. PRESSURIZER HEATERS AND | | SPRAYS, NORMAL CHARGING AND LETDOWN, AND THE REACTOR COOLANT PUMPS ARE | | BEING USED FOR PRIMARY PRESSURE, INVENTORY, AND TRANSPORT CONTROL. OFFSITE | | POWER IS AVAILABLE, AND THE EMERGENCY DIESEL GENERATORS ARE OPERABLE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE. THE | | LICENSEE ALSO PLANS TO ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29646 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 11/27/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:45 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 11/27/95 | +------------------------------------------------+EVENT TIME: 12:49[CST]| |NRC NOTIFIED BY: J. B. REIS |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF THE REACTOR CORE ISOLATION COOLING SYSTEM DUE TO THE LACK OF A | | REDUNDANT ISOLATION SWITCH | | | | AT 1249 CST, THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM WAS DECLARED | | INOPERABLE BECAUSE THE LICENSEE CLOSED THE RCIC STEAM SUPPLY ISOLATION | | VALVES AND OPENED THE POWER SUPPLY BREAKERS UNDER ADMINISTRATIVE CONTROL. | | THIS ACTION WAS TAKEN WHEN IT WAS DETERMINED THAT THERE WAS NO REDUNDANT | | ISOLATION SWITCH TO A PREVIOUS FAILURE THAT WAS REPORTED AT 0355 CST ON | | NOVEMBER 27, 1995. (REFER TO EVENT NUMBER 29643 FOR ADDITIONAL | | INFORMATION.) (THE PREVIOUS FAILURE WAS CAUSED BY A BLOWN DIAPHRAGM.) | | | | THE ACTION TO ISOLATE THE RCIC SYSTEM WAS REQUIRED TO BE MADE WITHIN 24 | | HOURS (BY 0130 CST ON NOVEMBER 28, 1995) PER THE TECHNICAL SPECIFICATIONS. | | INOPERABILITY OF THE RCIC SYSTEM IS A 14-DAY TECHNICAL SPECIFICATION | | LIMITING CONDITION FOR OPERATION. HIGH PRESSURE CORE SPRAY, LOW PRESSURE | | CORE SPRAY, AND ALL THREE TRAINS OF LOW PRESSURE COOLANT INJECTION ARE | | FULLY OPERABLE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29647 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 11/27/95 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 19:30 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 11/27/95 | +------------------------------------------------+EVENT TIME: 12:30[PST]| |NRC NOTIFIED BY: GREG GIBSON |LAST UPDATE DATE: 11/27/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS VANDENBURGH RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CERTAIN POSTULATED HIGH ENERGY LINE BREAKS IN THE TURBINE BUILDING MIGHT | | HAVE CREATED A STEAM ENVIRONMENT FOR WHICH SOME COMPONENTS WERE NOT | | QUALIFIED TO OPERATE. | | | | AT APPROXIMATELY 12:30 PST, THE LICENSEE COMPLETED A PRELIMINARY REVIEW OF | | A BECHTEL ANALYSIS THAT THE LICENSEE CURRENTLY BELIEVES WAS PERFORMED | | DURING THE ORIGINAL DESIGN WORK IN THE 1972 TO 1981 TIME FRAME. IT USED A | | BECHTEL HIGH ENERGY LINE BREAK ANALYSIS WHICH WAS APPROVED BY THE NRC AND | | IS BELIEVED TO BE USED AT OTHER FACILITIES. THE LICENSEE'S REVIEW | | INDICATED THAT BECHTEL APPARENTLY DID NOT CONSIDER CERTAIN POSTULATED HIGH | | ENERGY LINE BREAKS. IN CERTAIN LIMITED AND VERY REMOTE CASES, THE EFFECTS | | OF THE HIGH ENERGY LINE BREAK MAY HAVE AFFECTED THE ABILITY OF SOME SYSTEMS | | TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. SPECIFICALLY, CERTAIN STEAM | | LINE BREAKS IN THE TURBINE BUILDING MIGHT HAVE CREATED A STEAM ENVIRONMENT | | FOR WHICH SOME COMPONENTS WERE NOT QUALIFIED TO OPERATE. STEAM FROM THIS | | POSTULATED LINE BREAK COULD HAVE ENTERED THE SAFETY EQUIPMENT BUILDING (AND | | OTHER AREAS OF THE PLANT) THROUGH UNEVALUATED VENTILATION DUCTS AND COULD | | HAVE INTRODUCED STEAM TO THAT BUILDING. ONE COMPONENT IN THE SAFETY | | EQUIPMENT BUILDING IS THE ELECTRICAL TRANSFER SWITCH FOR THE HIGH PRESSURE | | SAFETY INJECTION SWING PUMP. THIS ELECTRICAL TRANSFER SWITCH WAS NOT | | QUALIFIED FOR A HARSH ENVIRONMENT BECAUSE THE BECHTEL ANALYSIS DETERMINED | | THAT IT WAS ALL RIGHT, AND THE LICENSEE IS CONSERVATIVELY ASSUMING THAT IT | | MAY NOT HAVE FUNCTIONED IN A STEAM ENVIRONMENT. (THIS IS ONE EXAMPLE, AND | | THE LICENSEE IS CONTINUING ITS EVALUATION.) | | | | CURRENTLY, THERE ARE NO OTHER COMPONENTS AFFECTED, AND NO TECHNICAL | | SPECIFICATION LIMITING CONDITIONS FOR OPERATION HAVE BEEN ENTERED. AS A | | RESULT OF THIS ISSUE, THE LICENSEE HAS IMPLEMENTED CHANGES TO APPROPRIATE | | OPERATING PROCEDURES SUCH THAT IF OPERATORS WERE REQUIRED TO RELY ON THE | | SWING HIGH PRESSURE SAFETY INJECTION PUMP, THE OPERATORS WOULD PLACE THE | | TRANSFER SWITCH IN MANUAL. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO BRIEF AN | | ONSITE NRC ENGINEERING TEAM TOMORROW MORNING. THE LICENSEE IS ALSO | | CONSIDERING THE POTENTIAL FOR A 10 CFR PART 21 REPORT BECAUSE THIS IS A | | BECHTEL ISSUE. THE SAME MODEL MAY HAVE BEEN USED ELSEWHERE. THE LICENSEE | | PLANS TO CONTACT ITS SISTER PLANTS. | | | | * * * 20:06 EST NOVEMBER 27, 1995, UPDATE FROM GIBSON BY TROCINE * * * | | | | IN LIEU OF IMPLEMENTING CHANGES TO THE OPERATING PROCEDURES, THE LICENSEE | | NOW PLANS TO SHUT OFF THE VENTILATION TO THE DUCT AND PHYSICALLY CLOSE THE | | FIRE DAMPER. THIS WOULD ELIMINATE THE PROBLEM. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R4DO (VANDENBURGH). | +------------------------------------------------------------------------------+