U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/24/96 - 05/28/96 ** EVENT NUMBERS ** 30367 30415 30531 30533 30534 30535 30536 30537 30538 30539 30540 30541 30542 30543 30544 30545 30546 30547 30548 30549 30550 30551 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30367 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/25/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:44 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/25/96 | +------------------------------------------------+EVENT TIME: 16:06[CDT]| |NRC NOTIFIED BY: JAN BOSTELMAN |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT OPERATIONS OUTSIDE OF DESIGN BASIS DURING 1995 REFUELING OUTAGE - | | | | THE LICENSEE IS REQUIRED TO ANALYZE RADIOLOGICAL DOSE CONSEQUENCES TO | | CONTROL ROOM OPERATORS AS A RESULT OF UPDATED SAFETY ANALYSIS REVIEW | | (USAR) CHAPTER 14 EVENTS AS SPECIFIED IN 10CFR50, APPENDIX A, CRITERION 19. | | THE INTENT OF THE CRITERION IS TO DEMONSTRATE CONTROL ROOM HABITABILITY. | | | | A DISCREPANCY BETWEEN THE FUEL HANDLING EQUIPMENT OPERATION PROCEDURE | | (#OI-FH-1) AND DESIGN BASIS CONTROL ROOM HABITABILITY RADIOLOGICAL | | CONSEQUENCES CALCULATION ASSUMPTIONS (USAR 14.18) WAS IDENTIFIED IN THE | | CONDITION REPORTING SYSTEM. SPECIFICALLY, CHANGES WHICH WERE MADE TO | | #OI-FH-1 TO REMOVE THE REQUIREMENT FOR HAVING ONE TRAIN OF THE CONTROL | | ROOM FILTRATION SYSTEM IN OPERATION PRIOR TO REFUELING OPERATIONS WERE | | UNSUBSTANTIATED. THE ANALYSIS OF RECORD FOR FUEL HANDLING ACCIDENT | | RADIOLOGICAL RELEASES CREDITS AT LEAST ONE TRAIN OF CONTROL ROOM FILTRATION | | BEING IN OPERATION AND NOT JUST OPERABLE. CONSEQUENTLY, #OI-FH-1 ALLOWED | | OPERATIONS DURING THE SPRING 1995 REFUELING OUTAGE WITH THE SYSTEM BEING | | OPERABLE BUT NOT OPERATING OUTSIDE OF AN ASSUMPTION IN THE DESIGN BASIS | | FOR FUEL HANDLING ACCIDENT RADIOLOGICAL DOSE CONSEQUENCES TO OPERATORS. | | | | TO ASSURE MITIGATION OF RADIOLOGICAL RELEASES IN THE EVENT OF A FUEL | | HANDLING ACCIDENT, A PROCEDURE CHANGE TO #OI-FH-1 WILL BE IMPLEMENTED TO | | REQUIRE THE CONTROL ROOM FILTRATION SYSTEM BE IN EMERGENCY MODE PRIOR TO | | MOVING IRRADIATED FUEL. THE NEXT REFUELING OUTAGE IS SCHEDULED TO BEGIN IN | | 09/96. LONG TERM CORRECTIVE ACTIONS WILL INCLUDE REVISING CONTROL ROOM | | RADIOLOGICAL CONSEQUENCES ANALYSIS AS A RESULT OF FUEL HANDLING ACCIDENTS | | IN CONTAINMENT OR THE AUXILIARY BUILDING. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | | | | * * * UPDATE 1631 5/24/96 FROM MATZKE TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. | | | | FCS HAS REVISED ITS ANALYSIS OF THE CONTROL ROOM RADIOLOGICAL CONSEQUENCES | | AS A RESULT OF FUEL HANDLING ACCIDENTS IN THE CONTAINMENT OR IN THE | | AUXILIARY BUILDING. THE CURRENT ANALYSIS SHOWS THAT THE CONTROL ROOM | | FILTRATION SYSTEM WAS AND IS CURRENTLY ABLE TO PERFORM ITS REQUIRED | | ACCIDENT MITIGATION FUNCTION EITHER IN AN OPERABLE MODE OR ACTUALLY | | OPERATING BEFORE THE START OF THE DESIGN BASIS FUEL HANDLING ACCIDENT. | | | | DUE TO THE COMPLETION OF THIS ANALYSIS, THE FORT CALHOUN STATION IS | | WITHDRAWING THE ORIGINAL NOTIFICATION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R4DO (JOHNSON). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30415 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 05/04/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 23:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/04/96 | +------------------------------------------------+EVENT TIME: 21:37[CDT]| |NRC NOTIFIED BY: ROBERT YURKOVICH |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK RING RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | M/R N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL OPENING OF THE REACTOR TRIP BREAKERS WITH THE UNIT IN MODE 5 DUE TO | | FAILURE OF TWO RODS TO WITHDRAW DURING DIGITAL ROD POSITION INDICATION | | OPERABILITY TESTING | | | | DURING THE PERFORMANCE OF PROCEDURE BWVS1.3.3-1, "DIGITAL ROD POSITION | | INDICATION OPERABILITY CHECKOUT", RODS P-12 AND M-14 DID NOT WITHDRAW AS | | EXPECTED. ALL OTHER RODS IN SHUTDOWN BANK 'A' INDICATED 12 STEPS ON THE | | DIGITAL ROD POSITION INDICATION WITH GROUP 'A1' DEMAND INDICATING 9 STEPS | | AND GROUP 'A2' INDICATING 8 STEPS. SPECIAL TEST EXCEPTION 3.10.5, "TESTING | | OF THE DIGITAL ROD POSITION INDICATION," WAS IN PROGRESS, AND THE REACTOR | | TRIP BREAKERS WERE IMMEDIATELY OPENED. ALL RODS FULLY INSERTED. | | TROUBLESHOOTING IS CURRENTLY IN PROGRESS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1233 5/24/96 FROM ZOLAN TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. UPON FURTHER REVIEW, THE | | LICENSEE HAS DETERMINED THAT THE OPENING OF THE REACTOR TRIP BREAKERS WAS | | DISCUSSED IN THE PRE-TEST BRIEFING, AND WAS THEREFORE PART OF A PREPLANNED | | EVOLUTION. ADDITIONALLY, THE LICENSEE HAS DETERMINED THAT SINCE THE | | POSITION OF THE CONTROL GROUPS DID NOT EXCEED 12 STEPS, THE OPENING OF THE | | REACTOR TRIP BREAKERS WAS A CONSERVATIVE ACTION TAKEN BY THE OPERATORS, AND | | WOULD BE CONSIDERED AN INVALID ACTUATION. THE NRC RESIDENT INSPECTOR HAS | | BEEN INFORMED. NOTIFIED R3DO (McCORMICK-BARGER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30531 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 05/23/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 09:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/23/96 | +------------------------------------------------+EVENT TIME: 08:04[CDT]| |NRC NOTIFIED BY: DAVE COLTMAN |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROBERT DENNIG, NRR EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |HOWARD EARL FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION |FRANK CONGEL, IRD AEOD | |ANLI 50.72(b)(1)(iii) LIGHTNING | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1: UNUSUAL EVENT DUE TO A COMPLETE LOSS OF OFFSITE POWER DURING A | | SEVERE LIGHTNING STRIKE WITH THE UNIT IN A REFUELING OUTAGE - UNIT 2: | | MANUAL TRIP FROM 100% POWER DUE TO THE LOSS OF INSTRUMENT AIR AND SERVICE | | WATER | | | | DURING A REFUELING OUTAGE WITH THE FUEL RELOADED INTO THE CORE, UNIT 1 | | SUFFERED A COMPLETE LOSS OF OFFSITE POWER DURING A SEVERE LIGHTNING STRIKE | | AT 0804 CDT. AT 0822 CDT, THE LICENSEE DECLARED AN UNUSUAL EVENT ON UNIT 1 | | DUE TO THE LOSS OF OFFSITE POWER FOR GREATER THAN 15 MINUTES. THE | | LIGHTNING STRIKE APPARENTLY CAUSED A FAULT ON PHASE 'AB' OF 6.9-KV STATION | | AUXILIARY TRANSFORMER (SAT) 142-2 WHICH RESULTED IN SAT 142-2 DELUGE | | INITIATION. THE DELUGE INITIATION IN TURN CAUSED AN '86' LOCK-OUT (BUS | | OVERCURRENT) ON SATs 142-2 AND 142-1. BOTH UNIT 1 SAFETY BUSSES WERE | | RE-ENERGIZED BY THE EMERGENCY DIESEL GENERATORS. | | | | PRIOR TO THE EVENT, THE UNIT 2 STATION AIR COMPRESSOR WAS OUT OF SERVICE | | FOR MAINTENANCE, AND UNIT 2 INSTRUMENT AIR WAS BEING SUPPLIED VIA THE UNIT | | 1 FEED. AS A RESULT, THE LICENSEE MANUALLY TRIPPED UNIT 2 FROM 100% AT | | 0806 CDT DUE TO A LOSS OF INSTRUMENT AIR AND SERVICE WATER. ALL RODS FULLY | | INSERTED, AND ALL UNIT 2 SAFEGUARDS EQUIPMENT FUNCTIONED AS REQUIRED. IN | | ADDITION, THERE WAS A FEEDWATER ISOLATION AND AN AUTOMATIC AUXILIARY | | FEEDWATER ACTUATION AS A RESULT OF THE TRIP. UNIT 2 SOURCE RANGE | | INSTRUMENT N-31 DID NOT RE-ENERGIZE AFTER THE MANUAL REACTOR TRIP, AND AN | | INVESTIGATION IS IN PROGRESS. SOURCE RANGE INSTRUMENT N-32 IS AVAILABLE. | | | | UNIT 2 IS CURRENTLY STABLE IN MODE 3 (HOT STANDBY). CHARGING THROUGH THE | | REACTOR COOLANT PUMP SEALS, PRESSURIZER PRESSURE-OPERATED RELIEF VALVES AND | | HEATERS, AND THE REACTOR COOLANT PUMPS ARE BEING UTILIZED FOR PRIMARY | | SYSTEM INVENTORY, PRESSURE, AND TRANSPORT CONTROL. AUXILIARY FEEDWATER IS | | BEING SUPPLIED TO THE STEAM GENERATORS, AND SECONDARY STEAM IS BEING | | RELIEVED TO ATMOSPHERE MANUALLY VIA THE STEAM GENERATOR POWER-OPERATED | | RELIEF VALVES. THERE HAS BEEN NO HISTORY OF STEAM GENERATOR TUBE LEAKAGE. | | THE UNIT 2 EMERGENCY DIESEL GENERATORS ARE ALSO AVAILABLE IF NEEDED. | | | | ALL SYSTEMS FUNCTIONED AS REQUIRED ON BOTH UNITS WITH THE EXCEPTION OF UNIT | | 2 SOURCE RANGE INSTRUMENT N-31. THE LICENSEE IS CURRENTLY INVESTIGATING | | THE EXTENT OF THE DAMAGE DUE TO THE LIGHTNING STRIKE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. | | | | * * * 1125 MAY 23, 1996, HOO NOTE FROM REGION 3 (MILLER) * * * | | | | THE SITE HAS THREE 100% NON-ESSENTIAL SERVICE WATER PUMPS WHICH FEED A | | COMMON HEADER AND BRANCH TO EITHER UNIT. THE SERVICE WATER THEN PROVIDES | | TURBINE, FEEDWATER, AND SERVICE AIR COOLING. THE SERVICE AIR COMPRESSOR IN | | TURN SUPPLIES INSTRUMENT AIR. THE POWER SUPPLIES FOR TWO OF THE THREE | | SERVICE WATER PUMPS COME FROM UNIT 1 NON-ESSENTIAL POWER SUPPLIES, AND THE | | REMAINING SERVICE WATER PUMP IS SUPPLIED FROM A UNIT 2 NON-ESSENTIAL POWER | | SUPPLY. AT THE TIME OF THE EVENT, THE SERVICE WATER PUMP THAT IS POWERED | | FROM UNIT 2 WAS OUT OF SERVICE FOR MAINTENANCE, AND UNIT 2 SERVICE WATER | | WAS BEING SUPPLIED FROM THE SERVICE WATER PUMPS THAT WERE POWERED FROM THE | | UNIT 1 NON-ESSENTIAL POWER SUPPLIES. AS A RESULT, WHEN THE LOSS OF POWER | | OCCURRED ON UNIT 1, SERVICE WATER WAS LOST TO UNIT 2. | | | | THE REGION RECEIVED AN UPDATE THAT THE LICENSEE HAD CROSS-TIED ONE | | ESSENTIAL POWER SUPPLY TO A NON-ESSENTIAL POWER SUPPLY TO RESTORE SERVICE | | WATER TO UNIT 2. THERE WERE ALSO EFFORTS UNDERWAY TO PROVIDE AN ALTERNATE | | METHOD OF RELIEVING SECONDARY STEAM IN LIEU OF UTILIZING THE STEAM | | GENERATOR POWER-OPERATED RELIEF VALVES. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE NRR EO (DENNIG). | | | | * * * UPDATE 1539 5/24/96 FROM SHAW TAKEN BY STRANSKY * * * | | | | UE TERMINATED AT 1430 CDT WHEN POWER TO UNIT 1 WAS RESTORED. THE NRC | | RESIDENT HAS BEEN INFORMED BY THE LICENSEE. THE HOO NOTIFIED R3DO | | (McCORMICK-BARGER), EO (ROE), FEMA (SWEITZER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30533 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 05/24/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 01:40 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/24/96 | +------------------------------------------------+EVENT TIME: 00:58[EDT]| |NRC NOTIFIED BY: STEVE SAUER |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF ALL OVERHEAD ANNUNCIATORS FOR APPROXIMATELY FOUR MINUTES DURING | | FUNCTIONAL TESTING WITH THE UNIT DEFUELED | | | | DURING THE PERFORMANCE OF FUNCTIONAL TESTING ON THE OVERHEAD ANNUNCIATOR | | SYSTEM, ALL OVERHEAD ANNUNCIATORS WERE LOST. THE SYSTEM HAS TWO COMPUTERS | | (A PRIMARY AND A BACKUP). THE LOSS OCCURRED WHEN LICENSEE PERSONNEL | | TRANSFERRED FROM THE BACKUP COMPUTER SYSTEM TO THE NORMAL COMPUTER SYSTEM | | PER THE TEST PROCEDURE. APPARENTLY, THE NORMAL SYSTEM DID NOT FUNCTION | | PROPERLY. OVERHEAD ANNUNCIATORS WERE RESTORED WITHIN A FEW MINUTES WHEN | | THE SYSTEM WAS RETURNED TO THE BACKUP COMPUTER SYSTEM. THE CAUSE IS | | UNKNOWN AT THIS TIME. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * 0353 MAY 24, 1996, UPDATE FROM SAUER RECEIVED BY TROCINE * * * | | | | THE LICENSEE PROVIDED THE FOLLOWING INFORMATION IN ORDER TO CLARIFY THE | | INFORMATION THAT WAS INITIALLY REPORTED: | | | | WHILE PERFORMING TESTING OF THE UNIT 2 OVERHEAD ANNUNCIATOR SYSTEM, THE | | PRIMARY CONTROLLER (SER 'A') FAILED TO ASSUME CONTROL WHEN MANUALLY | | TRANSFERRED FROM THE BACKUP CONTROLLER (SER 'B') AT 0058. THIS RESULTED IN | | THE SYSTEM BEING UNAVAILABLE FOR APPROXIMATELY FOUR MINUTES. THE SYSTEM | | WAS THEN TRANSFERRED BACK TO SER 'B' AT 0102. A SECOND ATTEMPT WAS MADE TO | | MANUALLY TRANSFER AT 0105, AND IT ALSO WAS UNSUCCESSFUL. AT THIS POINT, | | THE SYSTEM WAS LEFT ON SER 'B' AND FUNCTIONALLY TESTED SATISFACTORILY. A | | HISTORICAL DATA PRINT WAS RETRIEVED FROM SER 'B', AND NO ALARMS OF | | CONSEQUENCE HAD BEEN RECEIVED DURING THE PERIOD OF UNAVAILABILITY. | | | | DURING THE EVOLUTION, AN EXTRA OPERATOR HAD BEEN ASSIGNED IN THE CONTROL | | ROOM FOR INCREASED OBSERVATION OF THE CONTROL BOARD INDICATORS (IN CASE A | | FAILURE DID OCCUR). THE ABNORMAL OPERATING PROCEDURE WAS ENTERED, AND THE | | SYSTEM WAS VERIFIED TO BE OPERATING PROPERLY ON THE BACKUP CONTROLLER. AT | | THE PRESENT TIME, THE SYSTEM IS BEING FUNCTIONALLY CHECKED BY PERFORMING A | | LAMP CHECK EVERY 15 MINUTES. | | | | DUE TO THE SHORT DURATION OF THE UNAVAILABILITY OF THE SYSTEM, THERE WAS NO | | THREAT TO THE SAFE SHUTDOWN CONDITION OF THE PLANT. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (DURR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 30534 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF MISS, JACKSON, MS |NOTIFICATION DATE: 05/24/96 | | CITY: JACKSON REGION: 2 |NOTIFICATION TIME: 11:28 [ET]| | COUNTY: STATE: MS |EVENT DATE: 05/23/96 | |LICENSE#: MS-MBL-01 AGREEMENT: Y |EVENT TIME: 11:00[CDT]| | DOCKET: |LAST UPDATE DATE: 05/24/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS CHRISTENSEN RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+HENRY BAILEY AEOD | |NRC NOTIFIED BY: GOFF, MS DIV RAD HEALTH | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | |NAGR AGREEMENT STATE | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MEDICAL MISADMINISTRATION, AGREEMENT STATE EVENT - | | | | BOB GOFF & B. J. SMITH, MISSISSIPPI DIVISION OF RADIATION HEALTH, REPORTED | | THAT THE WRONG RADIOACTIVE SOURCES WERE INSERTED INTO TWO PATIENTS AT THE | | UNIVERSITY OF MISSISSIPPI MEDICAL CENTER (MEDICAL RESEARCH FACILITY), | | JACKSON, MS, DURING A TREATMENT FOR CERVICAL CANCER. (STATE ORIGINAL ITEM | | NO. MS-96-05). | | | | THE PRESCRIBED DOSE FOR THE FIRST PATIENT WAS 86.3 MILLICURIES OF CS-137 | | (2000 CENTIGRAYS); THE ACTUAL DOSE GIVEN WAS 51.5 MILLICURIES OF CE-137 | | (1342 CENTIGRAYS). THIS CONSTITUTES A 33% UNDEREXPOSURE. THE LICENSEE | | STATED THAT THERE WERE NO ADVERSE MEDICAL EFFECTS TO THE PATIENT. | | | | THE PRESCRIBED DOSE FOR THE SECOND PATIENT WAS 85.1 MILLICURIES OF CS-137 | | (2000 CENTIGRAYS); THE ACTUAL DOSE GIVEN WAS 119.8 MILLICURIES OF CS-137 | | (2690 CENTIGRAYS). THIS CONSTITUTES A 35% OVEREXPOSURE. THE LICENSEE | | REPORTED, SINCE THIS TREATMENT WAS A GIVEN IMMEDIATELY PRIOR TO A SCHEDULED | | OPERATION TO REMOVE THE CERVIX, THERE WERE NO ADVERSE MEDICAL EFFECTS TO | | THE PATIENT. | | | | BOTH PATIENTS AND THEIR PHYSICIAN (SAME PHYSICIAN) WERE NOTIFIED. | | | | THE LICENSEE REPORTED EVENT APPEARS TO MEET THE ABNORMAL OCCURRENCE | | CRITERIA (NUREG-0090). | | | | SEE HOO LOG FOR THE TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30535 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 05/24/96 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 10:00 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/21/96 | +------------------------------------------------+EVENT TIME: 10:34[EDT]| |NRC NOTIFIED BY: LANCE FRITZ |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TURBINE DRIVEN EMERGENCY FEEDWATER PUMP SEAL IMPROPERLY INSTALLED - | | | | DURING THE PERFORMANCE OF A QUARTERLY TECH SPEC SURVEILLANCE TEST OF THE | | TURBINE DRIVEN EMERGENCY FEEDWATER PUMP #1FWP-37A, SPARKS WERE OBSERVED | | EMANATING FROM THE OUTBOARD MECHANICAL SEAL AREA. CONTROL ROOM OPERATORS | | TRIPPED THE PUMP AND DECLARED IT INOPERABLE. | | | | THE LICENSEE DISASSEMBLED THE THE PUMP SEAL AND DETERMINED THAT THE SEAL | | HAD BEEN IMPROPERLY INSTALLED DURING THE LAST REFUELING OUTAGE | | (NOV/DEC 95). | | | | THIS CONDITION WAS NOT APPARENT DURING POST MAINTENANCE TESTS OR TECH SPEC | | SURVEILLANCE TESTS THAT WERE CONDUCTED SINCE DEC 95. | | | | AT 0915 ON 05/24/96, THE LICENSEE DETERMINED THIS EVENT TO BE REPORTABLE TO | | THE NRC. | | | | THE LICENSEE HAS REPAIRED THE PUMP, SATISFACTORILY TESTED IT, DECLARED IT | | OPERABLE, AND RESTORED IT TO SERVICE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30536 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 05/24/96 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 14:16 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 05/24/96 | +------------------------------------------------+EVENT TIME: 13:25[EDT]| |NRC NOTIFIED BY: BREEN |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRISTENSEN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 85 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS DUE TO FOUR CONTROL | | ELEMENT ASSEMBLIES BEING DECLARED INOPERABLE. | | | | THE LICENSEE COMMENCED A UNIT SHUTDOWN AFTER DECLARING FOUR CONTROL ELEMENT | | ASSEMBLIES (CEAs) INOPERABLE BUT TRIPPABLE. AT 0920, A CEA HIGH VOLTAGE | | ALARM WAS RECEIVED FOR A SUBGROUP OF THE GROUP 5 CEAs. THE CEAs OF THIS | | SUBGROUP WERE TRANSFERRED TO THE CEA HOLD BUS. THE CEAs ARE TRIPPABLE, BUT | | CANNOT BE STEPPED INTO OR OUT OF THE CORE. TECHNICAL SPECIFICATION 3.1.3.1 | | ACTION 'C' REQUIRES THAT THE UNIT BE PLACED IN HOT STANDBY WITHIN 6 HOURS | | WITH MORE THAN ONE CEA INOPERABLE. | | | | DURING THE SHUTDOWN, AT 1332, SHUTDOWN GROUP 'B' CEA 12 DROPPED INTO THE | | CORE. OPERATORS REDUCED TURBINE POWER TO MATCH REACTOR OUTPUT, THE UNIT | | SHUTDOWN WAS SUSPENDED, AND THE DROPPED CEA WAS RECOVERED. THE UNIT | | SHUTDOWN HAS BEEN RESUMED. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE HIGH VOLTAGE ALARM AND THE | | DROPPED CEA. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE 1612 5/24/96 FROM BREEN TAKEN BY STRANSKY * * * | | | | THE LICENSEE TERMINATED THE SHUTDOWN AT 1430. UPON FURTHER EVALUATION, THE | | LICENSEE DETERMINED THAT THE CEAs WERE OPERABLE BECAUSE THEY WERE | | TRIPPABLE. THE UNIT WILL REMAIN AT 80% POWER FOR CONDENSER WATERBOX | | CLEANING. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. THE HOO NOTIFIED | | R2DO (CHRISTENSEN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30537 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/24/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:20 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/24/96 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: DONOVAN |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DURR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RELAYS IN LOGIC FOR GAS TURBINE AND DIESEL GENERATOR NOT SEISMICALLY | | QUALIFIED. | | | | DURING A REVIEW OF UNRESOLVED SAFETY ISSUE (USI) A-46, THE LICENSEE | | DETERMINED THAT RELAYS IN THE LOGIC FOR THE GAS TURBINE AND DIESEL | | GENERATOR ARE NOT SEISMICALLY QUALIFIED, AND COULD CAUSE THE TURBINE AND | | DIESEL GENERATOR TO BE LOCKED OUT DURING A SEISMIC EVENT. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30538 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/24/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:52 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/24/96 | +------------------------------------------------+EVENT TIME: 13:35[CDT]| |NRC NOTIFIED BY: KIMLER |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCCORMICK-BARGER 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM HAS BEEN PLACED IN CONFIGURATIONS OUTSIDE OF THE FSAR DESIGN | | BASIS DURING PLANT OPERATION. | | | | THE LICENSEE HAS DETERMINED THAT, DURING POWER OPERATION, THE HPCI SYSTEM | | WAS PLACED IN A CONFIGURATION THAT MAY BE OUTSIDE OF THE FSAR DESIGN | | REQUIREMENTS FOR THE SYSTEM. SPECIFICALLY, FOLLOWING A HPCI TRIP ON HIGH | | REACTOR VESSEL WATER LEVEL, MOTOR-OPERATED EXHAUST LINE VACUUM BREAKER | | ISOLATION VALVES WERE ROUTINELY CLOSED IN ACCORDANCE WITH AN APPROVED | | PROCEDURE. HOWEVER, SUBSEQUENT RESTARTS OF THE HPCI SYSTEM WITH THESE | | VALVES CLOSED COULD CAUSE STRESS LEVELS TO EXCEED FSAR ALLOWABLE LIMITS DUE | | TO WATER HAMMER. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30539 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GE NUCLEAR ENERGY |NOTIFICATION DATE: 05/24/96 | | CITY: SAN JOSE REGION: 4 |NOTIFICATION TIME: 17:02 [ET]| | COUNTY: STATE: CA |EVENT DATE: 03/28/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[PDT]| | DOCKET: |LAST UPDATE DATE: 05/24/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: NOEL SHIRLEY | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEF 21.21(b)(2) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GESTAR II GENERIC SAFETY LIMIT MINIMUM CRITICAL POWER RATIO (MCPR) MAY BE | | NONCONSERVATIVE WHEN APPLIED TO SOME CORE AND FUEL DESIGNS. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE VENDOR: | | | | "THE SAFETY LIMIT MCPR IS A SPECIFIED ACCEPTABLE FUEL DESIGN LIMIT AS | | DEFINED BY GENERAL DESIGN CRITERION 10 OF 10CFR50 APPENDIX A. THE SAFETY | | LIMIT MCPR IS APPLIED TO ENSURE FUEL CLADDING INTEGRITY IS NOT LOST AS A | | RESULT OF OVERHEATING. THE SAFETY LIMIT MCPR DEFINES THE MINIMUM ALLOWABLE | | CRITICAL POWER RATIO (CPR) AT WHICH 99.9 PERCENT OF THE RODS IN THE CORE | | ARE EXPECTED TO AVOID BOILING TRANSITION DURING THE MOST LIMITING | | ANTICIPATED OPERATIONAL OCCURRENCE (AOO). | | | | THE SAFETY LIMIT MCPR IS DETERMINED FOR EACH FUEL DESIGN UNDER THE | | CONDITIONS SPECIFIED BY NEDE-24011-P-A-11, "GESTAR II: GENERAL ELECTRIC | | STANDARD APPLICATION FOR REACTOR FUEL," NOVEMBER 17, 1995, USING THE | | CALCULATIONAL METHODOLOGY DEFINED IN NEDO-10958-A, "GENERAL ELECTRIC BWR | | THERMAL ANALYSIS BASIS (GETAB): DATA, CORRELATION AND APPLICATION," JANUARY | | 1977. STATISTICAL ANALYSES ARE PERFORMED WHICH PROVIDE SAFETY LIMIT MCPR | | VALUES APPLICABLE FOR EACH GE FUEL (PRODUCT LINE) DESIGN. THE STATISTICAL | | PROCEDURE, WHEN COMBINED WITH THE CONDITIONS SET FORTH IN SECTION 1 OF | | GESTAR II, INCORPORATES CONSERVATISMS AS A MECHANISM TO ENSURE THAT THE | | STATISTICAL ANALYSIS IS APPLICABLE TO THE RANGE OF BWR/2-6 INITIAL AND | | RELOAD CORE CYCLES. | | | | RECENT ANALYSES HAVE INDICATED THAT THE SAFETY LIMIT MCPR CALCULATED ON A | | GENERIC BASIS WITH THE GE METHODOLOGY MAY BE NONCONSERVATIVE WHEN APPLIED | | TO SOME ACTUAL CORE AND FUEL DESIGNS. | | | | GE HAS INITIATED ACTION TO EVALUATE THE ADEQUACY OF THE GENERIC SAFETY | | LIMIT MCPRs FOR ALL PLANTS USING THE GESTAR LICENSING BASIS. SUCH | | EVALUATION ARE BEING PERFORMED USING THE CYCLE-SPECIFIC POWER DISTRIBUTIONS | | WHILE APPLYING THE GENERIC, CONSERVATIVE UNCERTAINTIES. SELECTED ANALYSES | | HAVE SHOWN THAT IF REALISTIC UNCERTAINTIES WERE EMPLOYED, THE SAFETY LIMIT | | MCPR WOULD BE BOUNDED BY THE GESTAR GENERIC ANALYSES." | | | | THIS REPORT POTENTIALLY AFFECTS THE FOLLOWING UNITS: OYSTER CREEK, NINE | | MILE POINT 1 AND 2, PILGRIM, MONTICELLO, MILLSTONE 1, QUAD CITIES 1 AND 2, | | BROWNS FERRY 2 AND 3, VERMONT YANKEE, COOPER, FITZPATRICK, BRUNSWICK 1 AND | | 2, DUANE ARNOLD, PEACH BOTTOM 2 AND 3, HATCH 1 AND 2, HOPE CREEK, FERMI 2, | | LIMERICK 1 AND 2, LASALLE 1 AND 2, RIVER BEND, CLINTON, AND PERRY. | | | | [HOO NOTE: ALSO SEE EVENTS 30293, 30298, 30383, 30407 AND 30527] | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30540 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 05/24/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 23:51 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/24/96 | +------------------------------------------------+EVENT TIME: 23:47[EDT]| |NRC NOTIFIED BY: DOUGLAS MCCRACKEN |LAST UPDATE DATE: 05/24/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION - STATE POLICE CALLED | | | | THE STATE POLICE WERE CALLED TO ASSIST IN THE REMOVAL OF AN INDIVIDUAL FROM | | OUTSIDE THE PROTECTED AREA. THE INDIVIDUAL IS AN UNARMED, OFF-DUTY, | | SECURITY FORCE MEMBER. HE WAS EXHIBITING UNUSUAL BEHAVIOR AND THAT | | PROMPTED THE CALLS FOR AN AMBULANCE AND THE STATE POLICE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30541 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/25/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 00:45 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/24/96 | +------------------------------------------------+EVENT TIME: 23:47[EDT]| |NRC NOTIFIED BY: JIM PHILLIPS |LAST UPDATE DATE: 05/25/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - THE "2A" EDG AUTOSTARTED | | | | A FAULT IN THE SWITCHYARD CAUSED THE LOSS OF THE "2A" BUS LINE. THIS | | CAUSED A LOSS OF POWER TO ESSENTIAL BUS "2A" AND AN AUTOSTART OF THE "2A" | | EDG. THE EDG DID NOT LOAD ON TO ITS BUS BECAUSE THE "2A" LINE IMMEDIATELY | | SWAPPED TO ITS ALTERNATE POWER SUPPLY, THEREBY RESTORING POWER TO THE "2A" | | ESSENTIAL BUS. | | | | SHUTDOWN COOLING WAS NOT LOST BECAUSE IT WAS BEING SUPPLIED BY TRAIN "B". | | THE LICENSEE BELIEVES THE FAULT WAS CAUSED BY A LIGHTNING STRIKE IN THE | | SWITCHYARD AND IS INVESTIGATING. THE "2A" EDG HAS BEEN RETURNED TO | | STANDBY. BOTH EDGs ARE OPERABLE AND ONLY ONE SOURCE OF OFFSITE POWER IS | | REQUIRED BY TECH SPECS IN MODE 5. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30542 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 05/25/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 05:14 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/25/96 | +------------------------------------------------+EVENT TIME: 02:53[EDT]| |NRC NOTIFIED BY: CECIL WILLIAMS |LAST UPDATE DATE: 05/25/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP ON LOSS OF FEED TO THE #1 STEAM GENERATOR | | | | AT 0251, THE BALANCE-OF-PLANT (BOP) OPERATOR NOTICED FEED FLOW RELATED | | ALARMS ON S/G #1, INCLUDING STEAM FLOW / FEED FLOW MISMATCH AND S/G #1 | | HI-LO DEVIATION. THE BOP OPERATOR ATTEMPTED TO RAISE FEED FLOW. THE SHIFT | | SUPERINTENDENT NOTED THE LACK OF INDICATION LIGHTS FOR MAIN FEED ISOLATION | | VALVE 1-HV-5227 TO S/G #1. THE UNIT SHIFT SUPERVISOR DIRECTED THE REACTOR | | OPERATOR TO TRIP THE REACTOR. ALL SYSTEMS FUNCTIONED AS REQUIRED, AND THE | | PLANT IS STABLE IN MODE 3. ALL RODS FULLY INSERTED AND AUXILIARY FEEDWATER | | STARTED AS EXPECTED. | | | | PRELIMINARY INVESTIGATION HAS REVEALED A BLOWN FUSE IN THE MAIN FEED | | ISOLATION VALVE CONTROL CIRCUIT. | | | | AN EVENT REVIEW TEAM HAS BEEN FORMED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30543 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/25/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 14:43 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/25/96 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: READY |LAST UPDATE DATE: 05/25/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DURR RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 10 STARTUP | 10 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | APPROXIMATELY ONE GALLON OF OIL SPILLED ONSITE | | | | THE LICENSEE NOTIFIED THE NEW YORK STATE DEPARTMENT OF ENVIRONMENTAL | | CONSERVATION AND THE WESTCHESTER COUNTY DEPARTMENT OF HEALTH REGARDING THE | | SPILLAGE OF APPROXIMATELY ONE GALLON OF OIL. THE SPILL OCCURRED FROM AN | | OVERFLOW TANK AT GAS TURBINE NUMBER ONE. THE OIL WAS SPILLED ONTO THE | | GRAVEL, AND NO OIL HAS REACHED ANY DRAINS. THE LICENSEE IS CURRENTLY | | CLEANING UP THE SPILL. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30544 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 05/26/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 06:35 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/26/96 | +------------------------------------------------+EVENT TIME: 05:17[EDT]| |NRC NOTIFIED BY: FRANK GORLEY |LAST UPDATE DATE: 05/28/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 18 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM FROM 18% POWER FOLLOWING SPURIOUS TRIP OF REACTOR | | FEEDWATER PUMPS. | | | | FAX RECEIVED FROM THE LICENSEE: | | | | MANUALLY SCRAMMED REACTOR FOLLOWING A RFP TURBINE TRIP CAUSED BY THE THRUST | | BEARING WEAR TRIP. REACTOR WATER LEVEL HAD DECREASED TO 10" AT THE TIME OF | | THE SCRAM. USED RCIC TO RECOVER LEVEL. RECEIVED GROUP 2 ISOLATION AT + 3 | | INCHES. ALL VALVES CLOSED AS REQUIRED. LOWEST RX WATER LEVEL OBSERVED WAS | | - 30 INCHES. RESTORED RX WATER LEVEL TO + 37 INCHES. RETURNED RCIC TO | | STANDBY. CRD FLOW PRESENTLY CONTROLLING RWL. | | | | END OF FAX. | | | | OPERATORS MANUALLY SCRAMMED UNIT 1 AFTER RECEIVING A SPURIOUS THRUST | | BEARING WEAR TRIP ON BOTH REACTOR FEEDWATER PUMPS (RFP). THE "A" RFP WAS | | SUPPLYING WATER TO THE VESSEL WITH THE "B" RFP IN STANDBY AT 2000 RPM. ALL | | RODS FULLY INSERTED. THE LICENSEE HAD REDUCED POWER AND TAKEN THE TURBINE | | OFFLINE FOR REPAIR OF AN EHC LEAK PRIOR TO THE MANUAL SCRAM. THE LICENSEE | | IS CURRENTLY TROUBLE SHOOTING THE MARK 5 RFP CONTROLLER WHICH WAS INSTALLED | | IN THE SPRING OUTAGE THIS YEAR. THE GROUP 2 ISOLATION SIGNAL CLOSES | | PRIMARY CONTAINMENT ISOLATION VALVES. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. THE LICENSEE HAS NO PLANS FOR A PRESS RELEASE AND | | ANTICIPATES RESTART LATE 5/26. | | | | * * * UPDATE 0430EDT 5/28/96 BY S. SANDIN DURING MORNING STATUS CALL * * * | | LICENSEE IDENTIFIED PROBLEM WAS RELATED TO FAILURE OF SINGLE POWER SUPPLY | | COMMON TO BOTH RFP CONTROLLERS. THEY SUSPECT THAT ONE OF THE TEST LEADS | | TIED INTO THE PANEL WAS GROUNDED CAUSING THE FAILURE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30545 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 05/26/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 06:47 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 05/26/96 | +------------------------------------------------+EVENT TIME: 05:15[EDT]| |NRC NOTIFIED BY: PAUL KIEL |LAST UPDATE DATE: 05/26/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 93 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - TORUS WATER MANAGEMENT OUTBOARD ISOLATION VALVES CLOSED | | | | WHILE REPLACING A POWER INDICATING LAMP IN THE DIVISION 2 TORUS WATER | | MANAGEMENT SYSTEM (TWMS) VALVE LOGIC PANEL, THE SOCKET CAME APART AND A | | LEAD GROUNDED. THE SHORT CAUSED 2 LOGIC FUSES TO BLOW AND THE OUTBOARD | | TWMS VALVES (4) TO CLOSE. THIS OCCURRED AT 0515. | | | | ALTHOUGH NO ISOLATION SIGNAL OCCURRED, THE NORMALLY ENERGIZED CIRCUIT LOGIC | | CAUSED THE VALVES TO CLOSE WHEN THE FUSES BLEW. AT 0612, THE SOCKET WAS | | ISOLATED, FUSES REPLACED, AND THE TWMS VALVES WERE RETURNED TO THE NORMAL | | VALVE LINE-UP. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30546 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 05/26/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 07:58 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/26/96 | +------------------------------------------------+EVENT TIME: 03:43[CDT]| |NRC NOTIFIED BY: TERRY REISDORFF |LAST UPDATE DATE: 05/26/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED BY STATE POLICE OF BOATING ACCIDENT ON OWNER CONTROLLED | | PROPERTY. | | | | "THE NEBRASKA STATE PATROL NOTIFIED FORT CALHOUN STATION CONTROL ROOM THAT | | A BOATING ACCIDENT HAD OCCURRED NEAR THE PLANT ABOUT 1/2 MILE DOWNSTREAM. | | THE INJURED PEOPLE (NINE) WERE TAKEN ASHORE JUST SOUTH OF THE SECURITY | | BUILDING WHICH IS OUTSIDE THE PROTECTED AREA BUT ON THE OWNER CONTROLLED | | PROPERTY." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30547 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 05/26/96 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 09:11 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/26/96 | +------------------------------------------------+EVENT TIME: 06:09[EDT]| |NRC NOTIFIED BY: CALVIN FIELDS |LAST UPDATE DATE: 05/26/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ESF ACTUATION - FOUR EDGs STARTED DURING TESTING | | | | RELAY K609 ACTUATED DURING CIRCUIT TESTING CAUSING ALL FOUR EDGs TO START. | | THERE WAS NO LOSS OF POWER TO THE EMERGENCY BUSES. OTHER EQUIPMENT | | OPERATED BY THIS RELAY WAS EITHER TAGGED OUT OR ALREADY IN THE CONDITION | | REQUIRED BY THE RELAY ACTUATION, I.E. ACTUATION OF THIS RELAY CAUSES A PUMP | | TO TRIP AND THAT PUMP WAS ALREADY OFF. | | | | INSTRUMENTATION PERSONNEL WERE PERFORMING A RESPONSE TIME TEST ON RELAY | | K649 AT THE TIME K609 ACTUATED. THE EQUIPMENT ASSOCIATED WITH K649 DID NOT | | RESPOND. THE LICENSEE IS INVESTIGATING WHY RELAY K609 ACTUATED. THESE | | RELAYS ARE BOTH PART OF THE SAME ESF CIRCUIT. | | | | ALL FOUR EDGs HAVE BEEN RETURNED TO STANDBY. NO SAFETY EQUIPMENT HAS BEEN | | DECLARED INOPERABLE BECAUSE OF THIS EVENT. THIS TESTING REQUIRED THAT UNIT | | TWO BE IN COLD SHUTDOWN. HOWEVER, THE ESF RELAY INVOLVED (K609) IS COMMON | | TO THE EDGs FROM BOTH UNITS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30548 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/26/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 17:39 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/26/96 | +------------------------------------------------+EVENT TIME: 15:40[CDT]| |NRC NOTIFIED BY: KIMLER |LAST UPDATE DATE: 05/26/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McCORMICK-BARGER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INSUFFICIENT VOLTAGE TO RHR/LPCI INJECTION VALVE MOTOR OPERATORS WHEN PLANT | | OPERATING AT DEGRADED VOLTAGE | | | | THE LICENSEE HAS DETERMINED THAT THE RHR/LPCI INJECTION VALVES ARE | | INOPERABLE BECAUSE OF INSUFFICIENT VOLTAGE AT THE MOTOR OPERATORS WHEN THE | | UNIT IS OPERATED AT A DEGRADED VOLTAGE. THE LICENSEE REPORTED THAT THIS IS | | THE SAME CONDITION REPORTED FOR UNIT 1 ON 5/23/96 (SEE EVENT NO. 30532). | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30549 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 05/27/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 14:26 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/27/96 | +------------------------------------------------+EVENT TIME: 10:31[EDT]| |NRC NOTIFIED BY: HUNTER |LAST UPDATE DATE: 05/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE HAD A PARTIAL GROUP 6C PRIMARY CONTAINMENT ISOLATION DUE TO A | | RAD MONITOR FAILURE. | | | | THE OCCURRENCE OF THE GROUP 6C PRIMARY CONTAINMENT ISOLATION RESULTED IN | | THE FOLLOWING VALVES ASSOCIATED WITH THE DRYWELL/SUPPRESSION POOL H2/O2 | | ANALYZER AND THE PRIMARY CONTAINMENT LEAK DETECTOR RECEIVING A CLOSE | | SIGNAL: SV-057-232, SV-057-234, SV-057-250, SV-057-281, SV-026-290B AND | | SV-026-290D. OPERATIONS AND I&C PERSONNEL PERFORMED TROUBLESHOOTING AND | | DETERMINED THAT THE INVALID ISOLATION SIGNAL WAS CAUSED BY THE FAILURE OF | | THE REACTOR ENCLOSURE EXHAUST RADIATION MONITOR. THE LICENSEE ALSO ENTERED | | TS LCO ACTION STATEMENT WHICH ALLOWS 30 DAYS TO RETURN THE CONTAINMENT LEAK | | DETECTOR TO SERVICE(SINCE VALVES ARE NOW CLOSED) AND 7 HRS TO VERIFY THAT | | ALL VALVES THAT RECEIVE THE SIGNAL FROM THE FAILED RAD MONITOR ARE CLOSED. | | THE RI WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30550 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/27/96 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 22:43 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 05/27/96 | +------------------------------------------------+EVENT TIME: 20:54[CDT]| |NRC NOTIFIED BY: VANBUSKIRK |LAST UPDATE DATE: 05/27/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED BOTH EMERGENCY DIESEL GENERATORS(EDG) INOPERABLE, | | PUTTING THE PLANT IN A TS REQUIRED SHUTDOWN TO BE IN HOT STANDBY WITHIN | | 6HRS. | | | | THIS CONDITION STARTED AT 15:50 WHEN #1 EDG WAS DECLARED INOPERABLE DUE TO | | FUEL OIL TANK WATER CONTENT BEING GREATER THAN TS LIMIT(.05%). TWO SAMPLES | | TAKEN MEASURED 1.4% AND 0.8%. AT 19:58 #2 EDG WAS DECLARED INOPERABLE FOR | | THE SAME REASON. THE INITIAL SAMPLE MEASURED 0.3%, BUT THE LAST TWO SAMPLES | | TAKEN WERE LESS THAN TS LIMIT. THEY HAVE ALSO TAKEN ONE SAMPLE FROM THE #2 | | EDG DAY TANK WHICH WAS BELOW THE TS LIMIT. IF THE SECOND SAMPLE FROM THE | | DAY TANK IS BELOW THE TS LIMIT, #2 EDG WILL BE DECLARED OPERABLE, AND THEY | | WILL TERMINATE PLANT S/D. THEY ARE REDUCING POWER AT APPROXIMATELY 3%/HR. | | THE HAVE NOT DETERMINED THE CAUSE OF THE HIGH WATER CONTENT IN THE TANKS. | | THE RI WAS INFORMED AND THE STATE WILL BE NOTIFIED. | | | | ***UPDATE AT 5/27/96 @ 23:29 BY VANBUSKIRK TO GOULD*** THE #2 EDG WAS | | DECLARED OPERABLE AT 22:23 CDT AND THE PLANT S/D WAS TERMINATED AT 95% | | POWER. THE RI WAS INFORMED. REG 4 JOHNSON WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30551 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 05/28/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:36 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 05/28/96 | +------------------------------------------------+EVENT TIME: 03:46[EDT]| |NRC NOTIFIED BY: GORDON MOSTERT |LAST UPDATE DATE: 05/28/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK DURR RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SECURITY OFFICER FITNESS FOR DUTY QUESTIONED DUE TO INATTENTIVENESS ON | | WATCH. IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE LICENSEE | | WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+