U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/08/96 - 03/11/96 ** EVENT NUMBERS ** 29808 29944 29971 29984 30079 30080 30081 30082 30083 30084 30085 30086 30087 30088 30089 30090 30091 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29808 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 01/07/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 22:43 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 01/07/96 | +------------------------------------------------+EVENT TIME: 19:00[EST]| |NRC NOTIFIED BY: MIKE RUHLMAN |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MICHAEL J. JORDAN RDO | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - LOCAL LEAK RATE OF PORTION OF MAIN STEAM SYSTEM EXCEEDS TECH SPEC LIMIT - | | | | THE MAIN STEAM SYSTEM DOWN STREAM OF THE MAIN STEAM ISOLATION VALVE LEAKED | | AT THE RATE OF 633 PSIG PER DAY DURING A LOCAL LEAK RATE TEST. THIS LEAK | | RATE CORRESPONDS TO A LEAK RATE VALUE OF 1.4. THE TECH SPEC LEAK RATE | | LIMIT IS 1.O. TECH SPEC LCO A/S 3.7 REQUIRES THE LICENSEE TO PLACE THE | | PLANT IN A HOT SHUTDOWN CONDITION WITHIN 12 HOURS AND A COLD SHUTDOWN | | CONDITION WITHIN THE FOLLOWING 24 HOURS WITH THE LEAK RATE ABOVE 1.0. THE | | PLANT IS PRESENTLY IN CONDITION 4 (COLD SHUTDOWN) IN A REFUELING OUTAGE. | | THE LICENSEE IS DETERMINING THE SOURCE OF THE LEAK. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1623 ON 03/08/96, FROM BOURASSA TO GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE ADMINISTRATIVE LIMITS WERE USED | | FOR DETERMINING REPORTABILITY, AND THEY WERE MORE RESTRICTIVE AND | | CONSERVATIVE THAN THE TECH SPEC LIMITS. AN ENGINEERING EVALUATION HAS | | CONCLUDED THAT THE TECH SPEC LEAKAGE LIMIT OF 0.5% AT 27 PSIG (934 | | LB-MASS/24 HOURS) WAS NEVER EXCEEDED. THE TOTAL AS-FOUND MINIMUM PATHWAY | | LEAKAGE HAS BEEN CALCULATED TO BE 914 LB-MASS/24 HOURS. HOWEVER, THE | | ENGINEERING STAFF DID DISCOVER THAT THE APPENDIX 'J' ACCEPTANCE CRITERIA | | FOR THE COMBINED LEAKAGE RATE OF ALL PENETRATIONS AND VALVES SUBJECT TO | | TYPE 'B' AND 'C' TEST OF LESS THAN 0.6 La WAS EXCEEDED (642 LB-MASS/24 | | HOURS) ON 01/08/96. BIG ROCK TECH SPECS DO NOT INCLUDE THE 0.6 La, AND | | THEREFORE, THIS EXCESS IS NOT REPORTABLE. THE NRC RESIDENT INSPECTOR WILL | | BE INFORMED BY THE LICENSEE. THE NRC OPERATIONS CENTER NOTIFIED THE R3DO | | (BURDICK). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29944 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 02/06/96 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 12:54 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 01/09/96 | +------------------------------------------------+EVENT TIME: 14:35[MST]| |NRC NOTIFIED BY: EKLUND |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |ACHE 50.72(b)(1)(vi) CHEM HAZ(TOX GAS REL) | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT IT WAS OUTSIDE THE DESIGN BASIS DUE TO A | | RAILROAD CAR BEING OUTSIDE THE PROTECTED AREA WITH A LOAD OF SULFUR | | DIOXIDE. | | | | ON 1/9/96, A RAIL CAR CONTAINING 180,000 POUNDS OF SULFUR DIOXIDE WAS | | DELIVERED ONSITE BY SOUTHERN PACIFIC RAILROAD. ON 1/10/96, AT | | APPROXIMATELY 1645 MST, THE RAIL CAR WAS MOVED OFFSITE TOWARD THE MAIN LINE | | (APPROXIMATELY 4.5 MILES). ON 1/11/96, @ 0030 MST, THE RAIL CAR WAS | | REMOVED BY SOUTHERN PACIFIC. ON 2/6/96, THIS CONDITION WAS DETERMINED TO | | BE REPORTABLE BECAUSE THE DESIGN BASIS DOES NOT ALLOW THE QUANTITY OF | | SULFUR DIOXIDE THAT WAS LOADED ON THE RAIL CAR. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | | | | * * * UPDATE AT 1222 ON 03/08/96, FROM ROBERSON TO GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT. THE LICENSEE RE-EVALUATED THE | | CONDITION AND DETERMINED THAT THE SINGLE RAIL CAR NEITHER CONSTITUTED A | | CONDITION OUTSIDE THE DESIGN BASIS NOR POSED AN ACTUAL THREAT. THE | | ERRONEOUS DELIVERY OF TOXIC GAS TO THE OWNER CONTROLLED AREA WAS A | | TRANSITORY CONDITION AND DID NOT CONSTITUTE STORAGE OR USAGE OF TOXIC GASES | | AS PROHIBITED BY THE UFSAR. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. THE R4DO | | (SPITZBERG) WAS NOTIFIED BY THE OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29971 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BIG ROCK POINT REGION: 3 |NOTIFICATION DATE: 02/10/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 12:21 [ET]| |RX TYPE: [1] GE-1 |EVENT DATE: 02/10/96 | +------------------------------------------------+EVENT TIME: 03:17[EST]| |NRC NOTIFIED BY: BOURASSA |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTAINMENT OUTBOARD ISOLATION VALVE EXCEEDED THE 24-HOUR CONTAINMENT | | INTEGRATED LEAK RATE TECHNICAL SPECIFICATION LIMIT BY 16%. | | | | CONTAINMENT LEAK RATE SURVEILLANCE TEST TR-39E, CLEAN AND DIRTY SUMP | | ISOLATION VALVE LEAK RATE TEST, WAS PERFORMED WITH THE FOLLOWING RESULTS: | | THE CLEAN SUMP ISOLATION VALVES PASSED THE ACCEPTANCE CRITERIA OF THE PLANT | | PROCEDURE. THE DIRTY SUMP ISOLATION VALVE CV-4025 (INSIDE CONTAINMENT | | ISOLATION VALVE) LEAKAGE WAS 24.4 psi/24 hours; AND CV-4103 (OUTBOARD | | CONTAINMENT ISOLATION VALVE) WAS 207 psi/24 hours. THE PLANT | | ADMINISTRATIVE ACCEPTANCE CRITERIA IS ó 24 psi/24 hours. | | | | TOTAL INTEGRATED CONTAINMENT LEAKAGE IS CALCULATED BY CONSERVATIVELY | | APPLYING THE VALVE WITH THE MOST LEAKAGE INTO THE CALCULATION (CV-4103; 207 | | psi/24 hours). THE TECHNICAL SPECIFICATION FRACTION AUTHORIZED LEAKAGE | | RATE WAS CALCULATED, AND THE LEAKAGE RATE EXCEEDED THE TECHNICAL | | SPECIFICATION LIMIT BY 16%. SINCE THE PLANT IS IN ITS 36TH DAY OF | | REFUELING AND SINCE THERE IS NO FUEL IN THE CORE, CONTAINMENT INTEGRITY IS | | NOT REQUIRED AT THIS TIME. | | | | THIS CONDITION WAS DISCOVERED ON 02/10/96 AT 0317 CST. AN ENS REPORT WAS | | NOT BELIEVED TO BE REQUIRED. FOLLOWING FURTHER REVIEW, THE BIG ROCK STAFF | | HAS CONCLUDED THAT THIS EVENT IS REPORTABLE. | | | | PRIOR TO PERFORMING ANY WORK REQUIRING CONTAINMENT INTEGRITY, THE LICENSEE | | WILL ASSURE THAT THE TECHNICAL SPECIFICATION REQUIREMENT DESCRIBED ABOVE | | SHALL BE MET. VALVE REPAIRS AND LEAKAGE TESTS ARE PLANNED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1623 ON 03/08/96, FROM BOURASSA TO GOULD * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE ADMINISTRATIVE LIMITS WERE USED | | FOR DETERMINING REPORTABILITY, AND THEY WERE MORE RESTRICTIVE AND | | CONSERVATIVE THAN THE TECHNICAL SPECIFICATION LIMITS. AN ENGINEERING | | EVALUATION HAS CONCLUDED THAT THE TECHNICAL SPECIFICATION LEAKAGE LIMIT OF | | 0.5% AT 27 PSIG (934 LB-MASS/24 HOURS) WAS NEVER EXCEEDED. THE TOTAL | | AS-FOUND MINIMUM PATHWAY LEAKAGE HAS BEEN CALCULATED TO BE 914 LB-MASS/24 | | HOURS. HOWEVER, THE ENGINEERING STAFF DID DISCOVER THAT THE APPENDIX 'J' | | ACCEPTANCE CRITERIA FOR THE COMBINED LEAKAGE RATE OF ALL PENETRATIONS AND | | VALVES SUBJECT TO TYPE 'B' AND 'C' TEST OF LESS THAN 0.6 La WAS EXCEEDED | | (642 LB-MASS/24 HOURS) ON 01/08/96. BIG ROCK TECHNICAL SPECIFICATIONS DO | | NOT INCLUDE THE 0.6 La, AND THEREFORE, THIS EXCESS IS NOT REPORTABLE. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE NRC | | OPERATIONS CENTER NOTIFIED THE R3DO (BURDICK). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29984 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 02/16/96 | |UNIT: [ ] [2] [3] STATE: AL |NOTIFICATION TIME: 13:06 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 02/16/96 | +------------------------------------------------+EVENT TIME: 11:30[CST]| |NRC NOTIFIED BY: MIKE MORROW |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN POTTER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |ACNC 50.72(b)(1)(ii)(C) COND OUTSIDE EOPS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 94 POWER OPERATION | 94 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -CABLE RUNS POSSIBLY AFFECTED BY APPENDIX R FIRE NOT PREVIOUSLY IDENTIFIED- | | | | AT 1130 (CST), THE LICENSEE DETERMINED THAT FIRE AREAS IN WHICH SEVERAL | | CABLE RUNS COULD BE AFFECTED BY A 10 CFR PART 50, APPENDIX 'R', FIRE EVENT | | ARE NOT IDENTIFIED IN THE BROWNS FERRY SAFE SHUTDOWN PROGRAM (10 CFR PART | | 50, APPENDIX 'R') FOR UNITS 2 AND 3. THESE CABLE RUNS SUPPLY POWER TO | | INSTRUMENTATION REQUIRED FOR THE PERFORMANCE OF SAFE SHUTDOWN INSTRUCTIONS | | (SSI) FOR 10 CFR PART 50, APPENDIX 'R', FIRES IN THE FIRE AFFECTED AREAS. | | | | THE FOLLOWING INSTRUMENTS ARE REQUIRED FOR THE PERFORMANCE OF THE SSIs | | ASSOCIATED WITH FIRE AFFECTED AREAS: | | - UNIT 2 SUPPRESSION POOL WATER LEVEL INSTRUMENTS (#2-LI-64-159A AND | | #2-XR-64-159) AND DRYWELL PRESSURE INSTRUMENT (#2-PI-64-160A) ARE | | DETERMINED TO BE AFFECTED BY CABLE RUNS IN 7 FIRE AREAS NOT PREVIOUSLY | | IDENTIFIED. | | - UNIT 3 SUPPRESSION POOL WATER LEVEL INSTRUMENT (#3-LI-64-159A) AND | | DRYWELL PRESSURE INSTRUMENT (#3-PI-64-161A) ARE DETERMINED TO BE AFFECTED | | BY CABLE RUNS IN 4 FIRE AREAS NOT PREVIOUSLY IDENTIFIED. | | | | THUS, IF AN SSI WERE BEING PERFORMED FOR ONE OF THE IDENTIFIED FIRE AREAS, | | THE CONTROL ROOM OPERATOR MAY FIND THAT INSTRUMENTS ASSUMED TO BE OPERABLE | | ARE RENDERED INOPERABLE BY THE FIRE. | | | | THE LICENSEE HAS POSTED ROVING FIRE WATCHES IN THE AFFECTED AREAS AND IS | | REVISING THE AFFECTED SSIs TO USE OTHER AVAILABLE INSTRUMENTS THAT INDICATE | | THE REQUIRED PARAMETERS. THE COMPENSATORY FIRE WATCHES WILL REMAIN IN | | PLACE UNTIL THE AFFECTED SSIs ARE REVISED. | | | | THE LICENSEE WILL SUBMIT AN LER ON THIS EVENT TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | *** UPDATED AT 1116 EST ON 03/08/96, FROM TIM GOLDEN TAKEN BY MACKINNON*** | | | | THIS IS SUPPLEMENTAL INFORMATION FROM AN ONGOING RE-ANALYSIS OF UNIT 2 SAFE | | SHUTDOWN (APPENDIX 'R') PROGRAM. THIS ONGOING PROGRAM IS EXPECTED TO BE | | COMPLETED BY 03/18/96. | | | | CABLES FOR INSTRUMENT LOOPS FOR REACTOR LEVEL (#2-LI-003-0058A), REACTOR | | PRESSURE (# 2-PI-003-0074A), AND TORUS TEMPERATURE (#2-LI-003-0058A) ARE | | ROUTED IN FIRE ZONE 2-3 AND YET ARE REQUIRED TO BE AVAILABLE FOR FIRE IN | | FIRE ZONE 2-3. THEREFORE, THESE INSTRUMENT LOOPS ARE UNABLE TO PERFORM | | THEIR APPENDIX 'R' FUNCTIONS FOR A FIRE IN FIRE ZONE 2-3. COMPENSATORY | | FIRE WATCHES HAVE BEEN INSTITUTED IN THE ABOVE AFFECTED FIRE ZONE 2-3. A | | LONG-TERM DESIGN CHANGE TO RESOLVE THESE ISSUES IS IN PLANNING. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. THE R2DO | | (KERRY LANDIS) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30079 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 03/07/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 21:50 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 03/07/96 | +------------------------------------------------+EVENT TIME: 18:19[EST]| |NRC NOTIFIED BY: SENSENBACH |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 97 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN FEEDWATER ISOLATION AND MANUAL REACTOR TRIP FROM 97% POWER DUE TO A | | CIRCULATING WATER PUMP TRIP | | | | AT 1815, THE "B" CIRCULATING WATER PUMP TRIPPED ON HIGH CURRENT POWER | | FACTOR. AT 1819, DURING THE RESULTANT SECONDARY SYSTEM TRANSIENT, | | FEEDWATER ISOLATION OCCURRED ON THE "A" AND "B" STEAM GENERATORS AT 2 OUT | | OF 3 67% LEVEL. AT 1823, A MANUAL REACTOR TRIP WAS ACTUATED BASED ON | | TURBINE BACK PRESSURE/CONDENSER VACUUM. ALL CONTROL RODS FULLY INSERTED ON | | THE TRIP, AND NO RELIEF VALVES LIFTED. THE PLANT IS IN MODE 3, AND RCS | | PRESSURE AND TEMPERATURE IS 2235 PSIG AND 547 DEGREES. LETDOWN ISOLATION | | OCCURRED WHEN PRESSURIZER LEVEL DECREASED TO A MINIMUM LEVEL OF 8%. | | PRESSURIZER LEVEL WAS RESTORED TO GREATER THAN 13% WITHIN 4 MINUTES. IN | | ADDITION, SOURCE RANGE DETECTOR N-31 FAILED LOW ON ENERGIZATION AND WAS | | DECLARED INOPERABLE. THE LICENSEE IS STILL INVESTIGATING THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | | | | * * * UPDATE AT 1636 ON 03/08/96, FROM WHITE TO GOULD * * * | | | | THE LICENSEE NEGLECTED TO REPORT THAT THERE ALSO WAS AN AUTOMATIC START OF | | THE AUXILIARY FEEDWATER SYSTEM AND THAT THE REACTOR POWER WAS RAMPED DOWN | | TO APPROXIMATELY 50% PRIOR TO THE TRIP. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. THE R1D0 | | (DOERFLEIN) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30080 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 03/08/96 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 08:59 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/08/96 | +------------------------------------------------+EVENT TIME: 07:25[CST]| |NRC NOTIFIED BY: JIM CHRISTIAN |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |EUGENE MCPEEK (NRR) IAT | | |YARDUMIAN (NMSS) IAT | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ATTEMPTED INTRODUCTION OF A WEAPON INTO THE PROTECTED AREA BY AN I&C | | TECHNICIAN (PLANT EMPLOYEE). IMMEDIATE COMPENSATORY MEASURES WERE TAKEN | | UPON DISCOVERY. SECURITY DOES NOT BELIEVE THIS TO BE A CREDIBLE THREAT. | | THE LICENSEE NOTIFIED REGION 4 (TOM DEXTER) OF THIS EVENT. THE LICENSEE | | WILL ALSO NOTIFY THE NRC RESIDENT INSPECTOR OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30081 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LANE CONSTRUCTION CORP, MERIDEN, CT |NOTIFICATION DATE: 03/08/96 | | CITY: MERIDEN REGION: 1 |NOTIFICATION TIME: 09:37 [ET]| | COUNTY: STATE: CT |EVENT DATE: 03/08/96 | |LICENSE#: 06-06284-02 AGREEMENT: N |EVENT TIME: 09:00[EST]| | DOCKET: |LAST UPDATE DATE: 03/08/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JAY CRUICKSHANK | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STOLEN TROXLER SOIL MOISTURE DENSITY GAUGE WITH SOURCE INTACT - | | | | BETWEEN 1730 ON 03/07/96, AND 0900 ON 03/08/96, A TROXLER SOIL MOISTURE | | DENSITY GAUGE INSIDE ITS STORAGE CASE WAS STOLEN FROM A LOCKED CABINET | | INSIDE A LOCKED STORAGE AREA AT THE LANE CONSTRUCTION CORPORATION CORPORATE | | OFFICE IN MERIDEN, CT. THE CORRECT NUCLEAR SYMBOL WAS ON THE GAUGE AND | | ITS CASE. THE RADIOACTIVE SOURCE IS 8 MILLICURIES OF CESIUM-137 AND | | 40 MILLICURIES OF AMERICIUM-241. THE COST OF THE GAUGE IS APPROXIMATELY | | $5,500. THE LICENSEE NOTIFIED THE LOCAL POLICE AND WILL SUBMIT A WRITTEN | | REPORT TO THE NRC WITHIN 30 DAYS. | | | | NOTE: SEE HOO LOG FOR LICENSEE TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30082 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/08/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 10:39 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/08/96 | +------------------------------------------------+EVENT TIME: 09:20[CST]| |NRC NOTIFIED BY: GARY DUDEK |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK 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 | 89 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNIT 1 SHUTTING DOWN DUE TO 1 OF 2 125-VDC ESF BATTERIES INOPERABLE - | | | | ON 03/07/96, 1 OF 58 CELLS (#32) OF 1 OF 2 125-VDC ESF BATTERIES (#112) | | FAILED A SINGLE CELL DISCHARGE TEST, AND THE LICENSEE REPLACED THE CELL | | WITH A NEW CELL. AT 0820 (CST) ON 03/08/96, A SECOND CELL (#7) OF THE SAME | | BATTERY FAILED THE SINGLE CELL DISCHARGE TEST, AND THE LICENSEE DECLARED | | BATTERY #112 INOPERABLE. TECH SPEC LCO A/S 3.8.2.1, ACTION 'd', REQUIRES | | THE LICENSEE TO PLACE UNIT 1 IN HOT STANDBY MODE WITHIN 8 HOURS AND COLD | | SHUTDOWN MODE WITHIN THE FOLLOWING 30 HOURS WITH 1 OF 2 125-VDC ESF | | BATTERIES INOPERABLE. | | | | THE LICENSEE BEGAN SHUTTING UNIT 1 DOWN, AND THE UNIT WAS AT 89% POWER AT | | THE TIME OF THE NOTIFICATION. THE LICENSEE EXPECTS UNIT 1 TO BE IN HOT | | STANDBY MODE BY 1400 (CST) ON 03/08/96. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30083 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/08/96 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 12:55 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 03/08/96 | +------------------------------------------------+EVENT TIME: 09:00[PST]| |NRC NOTIFIED BY: GIVIN |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SECURITY WAS NOTIFIED OF AN UNDETECTED ENTRY INTO THE PROTECTED AREA. | | IMMEDIATE COMPENSATORY WERE NOT TAKEN UPON DISCOVERY BUT WERE LATER FULLY | | IMPLEMENTED. (REFER TO THE HOO LOG FOR DETAILS.) | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30084 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 03/08/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 16:30 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/08/96 | +------------------------------------------------+EVENT TIME: 14:20[CST]| |NRC NOTIFIED BY: NADEN |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK 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 +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE ILLINOIS EPA OF RAW SEWAGE DISCHARGE FROM THE | | SITE STORM DRAIN TO THE CLINTON LAKE. | | | | THE CAUSE OF THE SEWAGE DISCHARGE WAS DUE TO A SEWER LINE BLOCKAGE WHICH | | RESULTED IN AN OVERFLOW FROM A SEWER MANHOLE ONTO THE GROUND. THE OVERFLOW | | THEN REACHED THE STORM DRAIN THAT EMPTIES INTO THE LAKE. THE AMOUNT OF | | DISCHARGE TO THE LAKE WAS APPROXIMATELY 5 TO 25 GALS. THIS IS NOT | | CONSIDERED TO BE A HAZARDOUS MATERIAL OR AN AMOUNT GREATER THAN A | | REPORTABLE QUANTITY. THE SEWER MANHOLE HAS BEEN PUMPED DOWN, AND THE | | LICENSEE IS ATTEMPTING TO IDENTIFY THE LINE BLOCKAGE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR ALONG WITH OTHER | | GOVERNMENT AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30085 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/08/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:59 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/08/96 | +------------------------------------------------+EVENT TIME: 18:47[EST]| |NRC NOTIFIED BY: LATZ |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT THERE HAVE BEEN INSTANCES WHERE NEITHER OF | | THE TWO EMERGENCY POWER SUPPLIES WERE OPERABLE. | | | | A REVIEW OF HISTORICAL DATA SHOWS THAT THERE WERE INSTANCES WHERE THE GAS | | TURBINE MAY HAVE BEEN OUT OF SERVICE FOR MAINTENANCE AND WHERE THE DIESEL | | MAY NOT HAVE BEEN AVAILABLE DUE TO AN UNUSABLE VOLUME IN THE FUEL OIL | | STORAGE TANK. THIS CONDITION ARISES WHEN THE FUEL LEVEL IN THE TANK GETS | | TO A POINT WHERE THE PUMPS LOSE SUCTION. IT TURNED OUT THAT THE UNUSABLE | | VOLUME IN THE TANK WAS MORE THAN THE LICENSEE INITIALLY THOUGHT. THIS | | RESULTED IN LESS USABLE FUEL BEING AVAILABLE FOR THE DIESEL. THE LICENSEE | | IS FURTHER INVESTIGATING THIS CONDITION. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30086 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 03/08/96 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 19:37 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 03/08/96 | +------------------------------------------------+EVENT TIME: 16:00[CST]| |NRC NOTIFIED BY: RHODES |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK 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 83 POWER OPERATION | 83 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A FASTENER FOR ELECTRICAL CONNECTIONS TO THE | | VOLTAGE REGULATOR WAS MISSING. | | | | DURING A SYSTEM ENGINEERING INSPECTION OF THE 12 EMERGENCY DIESEL GENERATOR | | ELECTRICAL CONTROL CABINET (C-92), IT WAS NOTED THAT A NUT AND BOLT WERE | | MISSING TO FASTEN ONE INPUT PHASE TO A RECTIFIER FOR SENSING GENERATOR | | OUTPUT. THE LEAD AND LUG, HOWEVER, WERE STILL IN CONTACT. THE VOLTAGE | | REGULATOR FUNCTIONED CORRECTLY, BUT THE OPERABILITY DURING AND AFTER A | | POSTULATED SEISMIC EVENT COULD NOT BE DETERMINED. THE LICENSEE HAS SINCE | | CORRECTED THE PROBLEM AND IS OPERATING THE DIESEL TO ASSURE OPERABILITY. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30087 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/08/96 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 21:06 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/08/96 | +------------------------------------------------+EVENT TIME: 17:30[EST]| |NRC NOTIFIED BY: LONG |LAST UPDATE DATE: 03/08/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT UNDER CERTAIN CONDITIONS THE PLANT MAY | | HAVE OPERATED OUTSIDE ITS DESIGN BASIS. | | | | PLANT TECHNICAL SPECIFICATIONS REQUIRE THAT IF ONE SAFETY INJECTION | | ACCUMULATOR LEVEL OR PRESSURE TRANSMITTER IS DECLARED INOPERABLE, THE | | REMAINING LEVEL OR PRESSURE CHANNEL MUST BE VERIFIED OPERABLE BY | | INTERCONNECTING AND EQUALIZING A MINIMUM OF TWO ACCUMULATORS AND | | CROSS-CHECKING THE INSTRUMENTS. IN ADDITION, PLANT PROCEDURES ALLOW | | TRANSFER OF NITROGEN OR WATER THROUGH COMMON FILL LINES FROM ONE | | ACCUMULATOR TO ANOTHER. IN BOTH CONDITIONS, NO RESTRICTIONS ARE PLACED ON | | PLANT OPERATING MODES. THE PLANT ACCIDENT ANALYSIS, HOWEVER, DOES NOT | | CONSIDER HAVING TWO OR MORE ACCUMULATORS CROSS-TIED DURING A POSTULATED | | LOSS OF COOLANT ACCIDENT (LOCA). AN EVALUATION BY THE LICENSEE'S | | ENGINEERING STAFF (CONFIRMED BY WESTINGHOUSE) SHOWS THAT THE PLANT MAY NOT | | BE PROTECTED DURING SOME LOCAs WITH THE ACCUMULATORS CROSS-TIED. AS SUCH, | | THE PLANT HAS OPERATED OUTSIDE ITS DESIGN BASIS. AN INVESTIGATION INTO | | THIS CONDITION AND ITS EFFECT ON THE ACCIDENT ANALYSIS IS CONTINUING. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30088 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 03/09/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 02:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/09/96 | +------------------------------------------------+EVENT TIME: 00:00[CST]| |NRC NOTIFIED BY: MARK STODDARD |LAST UPDATE DATE: 03/09/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS BURDICK 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 +------------------------------------------------------------------------------+ | FROZEN SAFETY INJECTION PUMP RECIRCULATION LINE WHILE THE UNIT WAS IN COLD | | SHUTDOWN | | | | WHILE UNIT 1 WAS IN COLD SHUTDOWN, THE SAFETY INJECTION PUMP SUCTION HEADER | | WAS FOUND TO BE PRESSURIZED TO APPROXIMATELY 180 PSIG. THROUGH | | TROUBLESHOOTING EFFORTS FOR THE POSSIBLE CAUSE OF THE PRESSURIZATION, IT | | WAS FOUND THAT A PORTION OF THE SAFETY INJECTION PUMP RECIRCULATION LINE | | THAT RUNS THROUGH A PURGE DUCT TO CONTAINMENT AND RETURNS FLOW BACK TO THE | | REFUELING WATER STORAGE TANK HAD BECOME FROZEN DUE TO LOW OUTSIDE AIR | | TEMPERATURE. THIS PORTION OF THE LINE IS COMMON TO BOTH THE 'A' AND 'B' | | SAFETY INJECTION TRAINS. IT WAS DETERMINED THAT IF UNIT 1 HAD BEEN | | OPERATING IN MODE 1, THIS WOULD HAVE RENDERED BOTH TRAINS OF SAFETY | | INJECTION INOPERABLE RESULTING IN A SAFETY SYSTEM BEING SERIOUSLY DEGRADED. | | THIS EVENT IS BEING REPORTED AS A DEGRADED CONDITION WHILE SHUTDOWN. | | | | THE LICENSEE WALKED DOWN THE UNIT 2 SAFETY INJECTION PUMP RECIRCULATION | | LINE AND VERIFIED IT TO BE WARM AND UNAFFECTED BY LOW AIR TEMPERATURES. THE | | REMAINING EMERGENCY CORE COOLING SYSTEMS ARE ALSO UNAFFECTED. THE UNIT 1 | | SAFETY INJECTION PUMP RECIRCULATION LINE IS THE ONLY LINE THAT APPEARS TO | | RUN THROUGH THE PURGE DUCT WHICH CAN TAKE OUTSIDE AIR AND PURGE THE UNIT 1 | | CONTAINMENT. THE LICENSEE HAS BEEN PURGING THE UNIT 1 CONTAINMENT TO | | SUPPORT OUTAGE WORK INSIDE THE CONTAINMENT. THE UNIT 2 PURGE SYSTEM HAS | | NOT BEEN RUNNING BECAUSE UNIT 2 IS CURRENTLY OPERATING AT 50% REACTOR | | POWER. THE LICENSEE PLANS TO THAW THE FROZEN LINE TONIGHT. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30089 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/09/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 16:36 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/09/96 | +------------------------------------------------+EVENT TIME: 14:56[EST]| |NRC NOTIFIED BY: BUTLER |LAST UPDATE DATE: 03/09/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 81 POWER OPERATION | 81 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECEIVED AN OUTBOARD GROUP-2 PRIMARY CONTAINMENT ISOLATION SYSTEM | | (PCIS) ISOLATION DUE TO A BLOWN FUSE. | | | | AN OPERATOR NOTICED A BURNING SMELL COMING FROM THE PCIS OUTBOARD PANEL, | | AND WHILE INVESTIGATING THE PROBLEM, THE LICENSEE FOUND THAT A FUSE | | (A71BF22) IN THE PANEL HAD BLOWN. WHEN THIS FUSE BLEW, A GROUP-2 ISOLATION | | WAS RECEIVED ON THE OUTBOARD VALVES THAT WERE OPEN. THE LICENSEE HAS | | NARROWED THE PROBLEM DOWN TO TEN RELAYS AND IS NOW TROUBLESHOOTING TO | | DETERMINE THE FAULT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | (REFER TO EVENT #30090 FOR ADDITIONAL INFORMATION.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30090 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 03/09/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 16:44 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/09/96 | +------------------------------------------------+EVENT TIME: 15:54[EST]| |NRC NOTIFIED BY: BUTLER |LAST UPDATE DATE: 03/09/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 81 POWER OPERATION | 77 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED TS 3.0.3 AND IS SHUTTING DOWN DUE TO BOTH LEAKAGE | | DETECTION SYSTEMS BEING INOPERABLE. | | | | THE CLOSURE OF THE OUTBOARD LEAKAGE DETECTION SYSTEM VALVES DURING THE | | GROUP-2 ISOLATION (REFER TO EVENT #30089) MADE THE LEAKAGE DETECTION | | SYSTEMS INOPERABLE. THE TWO SYSTEMS THAT BECAME INOPERABLE WERE THE | | DRYWELL FLOOR DRAIN MONITOR AND THE PRIMARY CONTAINMENT ATMOSPHERIC | | PARTICULATE OR ATMOSPHERIC GASEOUS MONITOR. THE LICENSEE'S TECHNICAL | | SPECIFICATIONS STATE THAT IF ALL LEAKAGE DETECTION SYSTEMS ARE INOPERABLE, | | THE LICENSEE MUST ENTER TECHNICAL SPECIFICATION 3.0.3. THE LICENSEE HAS | | COMMENCED REDUCING POWER AT A RATE OF 10% PER HOUR. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1703 ON 03/09/96, FROM BUTLER TO GOULD * * * | | | | THE LICENSEE DETERMINED THAT RELAY A71K57 WHICH SERVES VALVES B21F019 (MAIN | | STEAM LINE DRAIN VALVE - NORMALLY CLOSED VALVE) AND B31F020 (RECIRCULATION | | SAMPLE VALVE - NORMALLY OPEN VALVE) WAS FAULTY. OPERATORS ISOLATED THIS | | RELAY, REPLACED THE FUSE, AND RESET THE VALVES. THE LEAKAGE DETECTION | | SYSTEM WAS RESTORED AT 1644 AND POWER REDUCTION WAS HALTED AT 77%. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. THE R2DO (LANDIS) WAS | | INFORMED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30091 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 03/09/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 23:19 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 03/09/96 | +------------------------------------------------+EVENT TIME: 21:21[EST]| |NRC NOTIFIED BY: PETERSON |LAST UPDATE DATE: 03/09/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN AUTOMATIC START OF THE "B" AUXILIARY FEEDWATER PUMP DUE TO | | LOW LEVEL IN THE "A" STEAM GENERATOR. | | | | AT 2120, OPERATORS IN THE CONTROL ROOM ATTEMPTED TO OPEN THE "A" MAIN STEAM | | ISOLATION VALVE BY LOWERING THE AUTOMATIC SETPOINT OF THE STEAM GENERATOR | | ATMOSPHERIC RELIEF VALVE (AOV-3411) FROM 1,050 PSIG TO 1,000 PSIG. THE | | ATMOSPHERIC RELIEF VALVE WENT OPEN WITH DEMAND POSITION ON CONTROLLER, BUT | | THEN IT STAYED OPEN AFTER DEMAND WENT TO ZERO. THE MAIN CONTROL BOARD | | INDICATING LIGHTS SHOWED INTERMEDIATE POSITION (RED AND GREEN LIGHTS). | | REACTOR COOLANT SYSTEM (RCS) AVERAGE TEMPERATURE STARTED TO DECREASE ALONG | | WITH RCS PRESSURE. THE OPERATOR REPORTED THAT HE DID NOT HAVE CONTROL OF | | VALVE AOV-3411. THE CONTROL ROOM FOREMAN ORDERED THE AUXILIARY OPERATOR TO | | MANUALLY CLOSE THE ISOLATION VALVE FOR VALVE AOV-3411. AT 2127, THE | | ATMOSPHERIC RELIEF VALVE WAS REPORTED TO BE MANUALLY ISOLATED. DURING THE | | TRANSIENT, THE "A" STEAM GENERATOR DECREASED TO <16%, AND THE "B" AUXILIARY | | FEEDWATER PUMP STARTED DUE TO LOW "A" STEAM GENERATOR LEVEL. THE "A" STEAM | | GENERATOR LEVEL WAS RESTORED TO >16% AT 2141. RCS PRESSURE ALSO DROPPED TO | | 2,117 PSIG, AND RCS AVERAGE TEMPERATURE DROPPED TO 536.8øF. THE LICENSEE | | DISCOVERED THAT THE PROBLEM WAS A FAILED BOOSTER ON THE ACTUATOR FOR VALVE | | AOV-3411. THE LICENSEE IS CONTINUING ITS INVESTIGATING. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+