U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/08/97 - 10/09/97 ** EVENT NUMBERS ** 33007 33041 33042 33043 33044 33045 33046 33047 33048 33049 33050 33051 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33007 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 09/29/97 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 18:56 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 09/29/97 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: COSEO |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |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 HPCI SYSTEM HAS BEEN DECLARED INOPERABLE DUE TO BACK LEAKAGE THROUGH | | ONE OF THE SYSTEM'S CHECK VALVES. | | | | DURING THE PERFORMANCE OF THE HPCI SYSTEM PUMP AND VALVE OPERABILITY TEST, | | THE HPCI BAROMETRIC CONDENSER CONDENSATE BOOSTER PUMP DISCHARGE CHECK | | VALVE EXHIBITED A SMALL AMOUNT OF BACK LEAKAGE DURING THE CHECK VALVE TEST | | (~1-2 MM DIAMETER STREAM). THE HPCI SYSTEM WAS CONSERVATIVELY DECLARED | | INOPERABLE, WHICH PLACED THE PLANT IN A 14-DAY LCO ACTION STATEMENT. | | HPCI, HOWEVER, IS CURRENTLY IN STANDBY MODE AND AVAILABLE. CORE SPRAY, | | LPCI, RCIC, AND ADS ARE CURRENTLY OPERABLE. THE AUXILIARY EMERGENCY DIESEL | | GENERATORS ARE ALSO OPERABLE. THIS EVENT IS BEING REPORTED AS A POTENTIAL | | EVENT THAT COULD PREVENT THE FULFILLMENT OF A SAFETY FUNCTION OF SYSTEMS | | REQUIRED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. THE EXTENT OF IMPACT | | OF THE CHECK VALVE LEAKAGE IS STILL BEING EVALUATED. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 10/08/97 @ 1137 FROM ARAB TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT NOTIFICATION FOR THE FOLLOWING REASON. FURTHER | | INVESTIGATION INTO THE ASME SECTION XI TESTING REQUIREMENTS FOR THE HPCI | | BAROMETRIC CONDENSER CONDENSATE PUMP DISCHARGE VALVE SHOWED THAT ZERO BACK | | LEAKAGE THROUGH THE CHECK VALVE WAS AN OVERLY RESTRICTIVE ACCEPTANCE | | CRITERIA AND THAT THE AMOUNT OF BACK LEAKAGE EXHIBITED DURING THE TEST WAS | | ACCEPTABLE. THE AS-FOUND BACK LEAKAGE WOULD NOT HAVE PREVENTED THE HPCI | | SYSTEM FROM PERFORMING ITS INTENDED FUNCTION; THEREFORE, THIS NOTIFICATION | | SHOULD NOT HAVE BEEN MADE. THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE | | LICENSEE. THE R3DO (CLAYTON) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33041 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/07/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 18:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/07/97 | +------------------------------------------------+EVENT TIME: 17:05[CDT]| |NRC NOTIFIED BY: DAN KLOPSTEIN |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |CREED IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN INDIVIDUAL'S FITNESS FOR DUTY WAS QUESTIONED DUE TO SLEEPING ON WATCH. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED. (REFER TO THE HOO LOG FOR ADDITIONAL DETAILS.) | | | | * * * UPDATE AT 1156 ON 10/8/97 FROM DAVID SCHOLD TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. AFTER CONSULTING WITH | | THE CORPORATE OFFICE, THE LICENSEE HAS DETERMINED THAT THIS EVENT IS | | LOGGABLE BECAUSE COMPENSATORY ACTIONS WERE TAKEN WITHIN 10 MINUTES OF | | DISCOVERY. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. THE NRC OPERATIONS | | CENTER NOTIFIED R3 IAT (CREED). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33042 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 10/07/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 10/07/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:25[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 10/08/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 0707001 |FREDERICK COMBS/NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CAGE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE ONE-HOUR REPORT | | | | DURING A DAILY WALKDOWN OF CLASSIFIED INFORMATION REPOSITORIES, FOUR | | REPOSITORIES WERE FOUND UNLOCKED. THE LICENSEE IS CURRENTLY CONTACTING THE | | CUSTODIANS OF THESE REPOSITORIES TO DETERMINE WHETHER ANY INFORMATION IS | | MISSING. THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | | ***UPDATE ON 10/08/97 @ 1000 TO GOULD*** THE CORRECT EVENT TIME IS 1525 | | CDT. THE NRC OPERATIONS CENTER NOTIFIED THE R3DO (CLAYTON) AND NMSS EO | | (COMBS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33043 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/08/97 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 01:51 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 01:15[EDT]| |NRC NOTIFIED BY: FIELDS |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 72-HOUR LCO ACTION STATEMENT AFTER DECLARING BOTH THE | | "2HVS-1A" AND "2HVS-1D" CONTAINMENT FAN COOLERS OUT OF SERVICE. | | | | WHILE TROUBLESHOOTING THE CAUSE OF THE LOW FLOW ANNUNCIATOR ALARM ON BOTH | | CONTAINMENT FAN COOLERS, IT WAS DETERMINED THE "2HVS-1D" CONTAINMENT FAN | | COOLER WAS WIRED INCORRECTLY FOR RUNNING AT SLOW SPEED. THE LICENSEE | | DISCOVERED THAT THE SLOW SPEED LEADS WERE REVERSED CAUSING THE FAN TO | | OPERATE IN THE OPPOSITE DIRECTION. THE FAN IS REQUIRED TO RUN AT SLOW | | SPEED DURING A DESIGN BASIS ACCIDENT. THE FAN COOLER WAS DECLARED OUT OF | | SERVICE FOR BEING INCORRECTLY WIRED, AND THE LICENSEE ENTERED A 72-HOUR LCO | | ACTION STATEMENT TO RETURN ONE COOLER TRAIN BACK TO SERVICE OR BE IN MODE 3 | | WITHIN THE NEXT 6 HOURS AND MODE 4 IN THE FOLLOWING 6 HOURS. THE SECOND | | FAN COOLER ("2HVS-1A") DOES NOT APPEAR TO BE WIRED INCORRECTLY, BUT IT ALSO | | WAS DECLARED OUT OF SERVICE DUE TO AN APPARENT LOW FLOW SWITCH PROBLEM. THE | | RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33044 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DEPARTMENT OF THE NAVY |NOTIFICATION DATE: 10/08/97 | | CITY: ARLINGTON REGION: 2 |NOTIFICATION TIME: 06:52 [ET]| | COUNTY: FAIRFAX STATE: VA |EVENT DATE: 09/14/97 | |LICENSE#: 45-23645-01NA AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 10/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK LESSER RDO | | |FREDERICK COMBS/NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: POMERVILLE | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DEPARTMENT OF THE NAVY REPORTED THE LOSS OF FOUR AMERICIUM-241 FOIL SOURCES | | USED IN LASER TARGET DESIGNATOR PODS INSTALLED ON TWO SEPARATE F/A-18 | | AIRCRAFT WHICH CRASHED ON 9/14/97 AND 9/15/97. | | | | THE FOLLOWING FACSIMILES WERE RECEIVED: | | | | "RADIOACTIVE MATERIAL LOSS REPORT OMAN [ENCLOSURE (1)] | | | | (1) THE EQUIPMENT INVOLVED A LASER TARGET DESIGNATOR (LTD) POD, SERIAL | | NUMBER SAZ-271, MOUNTED ON A F/A-18C AIRCRAFT. THE LTD POD CONTAINS TWO | | FOIL SOURCES. THEY ARE AMERSHAM MODEL AMM1001H SOURCES EACH CONTAINING | | 4.5æCi OF AM-241 TOTALING 9æCi OF AM-241 IN THE DEVICE. | | | | (2) THE F/A-18C AIRCRAFT FROM THE USS JOHN F. KENNEDY (CV 67) CRASHED IN | | THE COUNTRY OF OMAN ON 14 SEPTEMBER, 1997. THE AIRCRAFT WAS FLYING A LOW | | ALTITUDE TRAINING MISSION AND IMPACTED THE SIDE OF A BOX CANYON IN THE | | OMANIE DESERT. THE AIRCRAFT DEBRIS FIELD IS LOCATED AT 17 DEGREES 23 | | MINUTES 18 SECONDS NORTH LATITUDE AND 55 DEGREES 15 MINUTES 30 SECONDS EAST | | LONGITUDE. | | | | (3) THE AREA OF THE CRASH SITE IS IN A ROUGHED DESERT AREA OF OMAN, AND | | THE POTENTIAL FOR PERSONNEL EXPOSURE FROM THE DEVICE IS CONSIDERED LITTLE | | TO NONE. | | | | (4) A MISHAP INVESTIGATION IS ONGOING, BUT THE RECOVERY OF ALL AIRCRAFT | | COMPONENTS IS NOT PROBABLE DUE TO TERRAIN AND TIME CONSTRAINTS." | | | | "RADIOACTIVE MATERIAL LOSS REPORT CHERRY POINT [ENCLOSURE (2)] | | | | (1) THE EQUIPMENT INVOLVED WAS A LASER TARGET DESIGNATOR (LTD) POD, SERIAL | | NUMBER RLP-226, MOUNTED ON A F/A-18D AIRCRAFT. THE AMM1001H SOURCES EACH | | CONTAINING 4.5æCi OF AM-241 TOTALING 9æCi OF AM-241 IN THE DEVICE. | | | | (2) THE F/A-18D AIRCRAFT CRASHED IN A SWAMP ON 15 SEPTEMBER, 1997. THE | | AIRCRAFT WAS FLYING A NIGHT CLOSE SUPPORT TRAINING MISSION AND IMPACTED THE | | WATER 20 NAUTICAL MILES NORTHEAST OF MARINE CORPS AIR STATION, CHERRY | | POINT, NC. THE CRASH SITE IS LOCATED AT 35 DEGREES 4 MINUTES NORTH | | LATITUDE AND 76 DEGREES 26 MINUTES WEST LONGITUDE. | | | | (3) THE AREA OF THE CRASH SITE IS A SWAMP, AND THE DEBRIS IS LOCATED 12 | | FEET BENEATH THE SURFACE. THE POTENTIAL FOR PERSONNEL CONTACT IS | | CONSIDERED NONE. | | | | (4) A MISHAP INVESTIGATION IS ONGOING, BUT THE RECOVERY OF ALL AIRCRAFT | | COMPONENTS IS NOT PROBABLE DUE TO SWAMPY CONDITIONS AT THE SITE." | | | | THE LICENSEE INDICATED IN ITS FACSIMILE THAT A HARD COPY AND FACSIMILE OF | | THIS NOTIFICATION WOULD BE SENT TO NRC REGION 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33045 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 10/08/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 14:11 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 05:25[EDT]| |NRC NOTIFIED BY: PAUL FREEMAN |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A DEAD SEAL WAS DISCOVERED IN THE PLANT'S INTAKE BAY. | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "SEABROOK STATION IS MAKING A 24-HOUR NOTIFICATION IN ACCORDANCE WITH | | SECTION 4.1 OF THE ENVIRONMENTAL PROTECTION PLAN, APPENDIX B OF THE | | TECHNICAL SPECIFICATIONS, AS A RESULT OF A DEAD SEAL BEING OBSERVED IN OUR | | CIRCULATING WATER SYSTEM PUMP HOUSE FOREBAY. | | | | THE NATIONAL MARINE FISHERIES SERVICE IN GLOUCESTER, MASSACHUSETTS, HAS | | BEEN NOTIFIED UNDER THE MARINE MAMMAL PROTECTION ACT." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33046 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/08/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:14 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 14:54[EDT]| |NRC NOTIFIED BY: PAUL REED |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 +------------------------------------------------------------------------------+ | REACTOR BUILDING ROOF MAY NOT WITHSTAND SAFE SHUTDOWN EARTHQUAKE. | | | | DURING A DESIGN BASIS REVIEW, THE LICENSEE DETERMINED THAT THE CORRUGATED | | METAL ROOF OF THE REACTOR BUILDING MAY NOT WITHSTAND A DESIGN BASIS SAFE | | SHUTDOWN EARTHQUAKE. THE SAFE SHUTDOWN EARTHQUAKE CRITERION REQUIRES THAT | | THE ROOF WITHSTAND GROUND ACCELERATION OF 0.17g; HOWEVER, THE BUILDING WAS | | ANALYZED FOR THE OPERATIONAL BASIS EARTHQUAKE OF 0.07g WITH NO ADDITIONAL | | MARGIN ADDED. THEREFORE, THE LICENSEE CANNOT DEMONSTRATE THAT THE ROOF | | WOULD BE ABLE TO WITHSTAND A DESIGN BASIS EARTHQUAKE. FAILURE OF THE ROOF | | WOULD RESULT IN A LOSS OF SECONDARY CONTAINMENT INTEGRITY. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33047 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 10/08/97 | |UNIT: [ ] [ ] [3] STATE: AZ |NOTIFICATION TIME: 18:34 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 10/07/97 | +------------------------------------------------+EVENT TIME: 18:02[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE 24-HOUR REPORT DUE TO EXCEEDING LICENSED THERMAL POWER LIMIT | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | "AT APPROXIMATELY 1802 MST ON OCTOBER 7, 1997, PALO VERDE UNIT 3 | | EXPERIENCED A BRIEF NONRECURRING POWER INCREASE ASSOCIATED WITH AN | | EQUIPMENT FAILURE, PEAKING AT 102.1% RATED THERMAL POWER. UNIT 3 WAS | | OPERATING AT APPROXIMATELY 100% POWER PRIOR TO THE TRANSIENT. THE TIME | | ABOVE 100% WAS APPROXIMATELY 109 SECONDS. THE TIME ABOVE 102% WAS LESS THAN | | 7 SECONDS. THE SHIFTLY AVERAGE POWER LEVEL DID NOT EXCEED 100%. THE | | TRANSIENT VIOLATED THE UNIT 3 FACILITY OPERATING LICENSE, NPF-74, CONDITION | | 2.C(1) WHICH AUTHORIZES OPERATION TO 100% POWER (3876 MEGAWATTS THERMAL). | | LICENSE CONDITION 2.G REQUIRES REPORTING OF ANY VIOLATION OF THE | | REQUIREMENTS CONTAINED IN SECTION 2.C OF THE LICENSE. | | | | THE MINIMUM REACTOR COOLANT COLD LEG TEMPERATURE DURING THE TRANSIENT WAS | | APPROXIMATELY 551.7øF, REMAINING ABOVE THE TECHNICAL SPECIFICATION (TS) | | LIMIT FOR OPERATION (TS 3.2.6) AND THE MINIMUM TEMPERATURE FOR CRITICALITY | | (TS 3.1.1.4). MINIMUM PRESSURIZER PRESSURE DURING THE TRANSIENT WAS | | APPROXIMATELY 2224 PSIA, REMAINING WITHIN THE NORMAL OPERATING RANGE (TS | | 3.2.8). PRESSURIZER LEVEL REMAINED WITHIN TS LIMITS THROUGHOUT THE | | TRANSIENT (TS 3.4.3.1). SINCE REGULATING GROUP 5 CEAs WERE BELOW THE POWER | | DEPENDENT INSERTION LIMITS (PDIL, <108 INCHES WITHDRAWN) FROM 1821 TO 1830 | | MST, SHUTDOWN MARGIN WAS VERIFIED ADEQUATE TO COMPLY WITH SURVEILLANCE | | REQUIREMENT 4.1.1.2.1.b. | | | | THE CAUSE OF THE TRANSIENT WAS A FAILED BELLOWS IN 3JMTNPSL0513, A PRESSURE | | SWITCH THAT MONITORS PRESSURE IN CROSSAROUND PIPING FROM THE MOISTURE | | SEPARATOR REHEATER TO LOW PRESSURE TURBINE 'A'. THE SWITCH FAILURE CAUSED | | THE 2ND STAGE REHEATER DRAIN TANK HIGH LEVEL CONTROL VALVES TO OPEN. THE | | HIGH LEVEL CONTROL VALVES OPENING RESULTED IN STEAM DUMPING DIRECTLY TO THE | | CONDENSER, AN EXCESS STEAM DEMAND TRANSIENT. THE OPERATING CREW REDUCED | | TURBINE LOAD TO COMPENSATE FOR THE STEAM DEMAND, RETURNING REACTOR POWER | | BELOW 100% AND ISOLATED 2ND STAGE REHEAT. | | | | THIS EVENT IS CATEGORIZED AS AN EXCESS STEAM DEMAND EVENT. THIS IS AN | | ANTICIPATED OPERATIONAL OCCURRENCE (AOO), OR MODERATE FREQUENCY EVENT, AND | | IS BOUNDED BY THE ANALYSIS PRESENTED IN UFSAR 15.1.4, CASE 1 (INADVERTENT | | OPENING OF AN ATMOSPHERIC DUMP VALVE WITH NO SINGLE FAILURE). AN | | EXAMINATION OF THE DATA SHOWED THAT THE POWER EXCURSION, RCS PRESSURE AND | | TEMPERATURE TRENDS WERE NOT OF SUFFICIENT MAGNITUDE TO CHALLENGE THE DNBR | | OR LHR LIMITS, AND THAT NO OTHER SAFETY LIMITS (PRIMARY/SECONDARY PRESSURE | | LIMITS, SHUTDOWN MARGIN) APPEAR TO HAVE BEEN CHALLENGED. | | | | NO ESF OR REACTOR PROTECTION SYSTEM ACTUATIONS OCCURRED, AND NONE WERE | | REQUIRED. | | | | THE EVENT DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER | | OR RESULT IN ANY RELEASES OF RADIOACTIVE MATERIALS. THERE WERE NO ADVERSE | | SAFETY CONSEQUENCES OR IMPLICATIONS AS A RESULT OF THIS EVENT. THE EVENT | | DID NOT ADVERSELY AFFECT THE SAFE OPERATION OF THE PLANT OR HEALTH AND | | SAFETY OF THE PUBLIC." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33048 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/08/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 16:32[CDT]| |NRC NOTIFIED BY: MARK CARNAHAN |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE DUE TO FAILURE TO TEST LOAD | | SEQUENCE RELAYS. | | | | THE LICENSEE HAS DETERMINED THAT RELAYS IN UNIT 2 THAT BLOCK THE AUTOMATIC | | START OF COMPONENTS WHICH SEQUENCE ONTO THE ESF BUSES DURING UNDERVOLTAGE | | CONDITIONS HAVE NOT BEEN TESTED. AS A RESULT, THE UNIT 2 EMERGENCY DIESEL | | GENERATORS (EDG) HAVE BEEN DECLARED INOPERABLE, INCLUDING THE EDG SHARED | | WITH UNIT 1. THE LICENSEE BELIEVES THAT THIS PROBLEM ALSO EXISTS ON UNIT 1, | | AND HAS ALSO DECLARED THE UNIT 1 EDGs INOPERABLE. DUE TO THE INOPERABILITY | | OF ALL FIVE EDGs; THE SERVICE WATER, COMPONENT COOLING WATER, AND UNIT 2 | | RESIDUAL HEAT REMOVAL SYSTEMS ARE INOPERABLE. THE NRC RESIDENT INSPECTOR | | WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33049 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/08/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 21:22 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: JEFFREY SHIPE |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED ERROR IN APPENDIX R ANALYSIS | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "A REVIEW PERFORMED BY THE NUCLEAR ENGINEERING DEPARTMENT IDENTIFIED AN | | ERROR IN THE APPENDIX R FIRE ANALYSIS. | | | | ONE OF THE LETDOWN METHODS CREDITED IN THE APPENDIX R ANALYSIS IS TO | | MAINTAIN PRESSURIZER LEVEL BY SHRINK DURING COOLDOWN WHILE CHARGING INTO | | THE REACTOR COOLANT PUMP SEALS. HOWEVER, THE NATURAL CIRCULATION COOLDOWN | | METHOD REQUIRES A NINE-HOUR SOAK AT 350øF DURING WHICH TIME THERE WOULD BE | | NO SEAL INJECTION FLOW OR THE PRESSURIZER LEVEL WOULD INCREASE. WITHOUT | | SEAL INJECTION FLOW OR THERMAL BARRIER COOLING, THE RCP SEALS COULD BE | | DAMAGED. THIS IS THE ONLY LETDOWN METHOD AVAILABLE PER THE APPENDIX R | | ANALYSIS FOR A FIRE IN CONTAINMENT, AND THE CONTAINMENT EXEMPTION (CHAPTER | | 11.2 OF THE APPENDIX R REPORT) DOES NOT DIRECTLY ADDRESS THE LOSS OF | | LETDOWN OR THE PHYSICAL SEPARATION OF THE REDUNDANT REACTOR COOLANT GAS | | VENT SYSTEM VALVES AND ASSOCIATED CABLES WHICH ARE QUALIFIED AS LETDOWN | | PATHS FOR APPENDIX R FIRES IN OTHER PLANT AREAS. | | | | PROBABLE CAUSE: INADEQUATE ANALYSIS OF THE SAFE SHUTDOWN METHODOLOGY WHEN | | THE ORIGINAL SHUTDOWN ANALYSIS WAS DEVELOPED. THIS IS NOT APPLICABLE TO | | UNIT 2." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33050 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 10/08/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 21:22 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 10/08/97 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: JEFFREY SHIPE |LAST UPDATE DATE: 10/08/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 +------------------------------------------------------------------------------+ | VOLTAGE SUPPLIED BY SAFETY-RELATED INVERTERS COULD BE OUT OF RECOMMENDED | | RANGE | | | | THE FOLLOWING IS TEXT FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "A REVIEW PERFORMED BY THE NUCLEAR ENGINEERING DEPARTMENT HAS IDENTIFIED A | | POTENTIAL CONDITION (HIGH OR LOW VOLTAGE) WHERE THE VOLTAGE SUPPLIED FROM | | THE SAFETY-RELATED INVERTERS TO THE NUCLEAR INSTRUMENTATION SYSTEM WOULD BE | | OUTSIDE OF THE VENDOR REQUIREMENTS. THIS CONDITION HAS THE POTENTIAL TO | | AFFECT NIS PROTECTIVE ACTION FUNCTION. | | | | THE PLANT IS CURRENTLY IN MODE 6. VOLTAGES ON THE SOURCE RANGE | | INSTRUMENTATION WERE VERIFIED ACCEPTABLE. PERIODIC MONITORING OF THE | | VOLTAGES WILL CONTINUE UNTIL CORRECTIVE ACTIONS ARE COMPLETED. | | | | THE PROBABLE CAUSE OF THE CONDITION IS THE RETIREMENT OF THE SOLA | | REGULATING TRANSFORMERS FEEDING THE NIS INSTRUMENTATION RACKS PER E&DCR | | #9475 (DATED 4/13/75). ENGINEERING IS PURSUING CORRECTIVE ACTIONS TO BE | | COMPLETED PRIOR TO THE END OF THE CURRENT REFUELING OUTAGE." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33051 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 10/09/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 05:47 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/09/97 | +------------------------------------------------+EVENT TIME: 04:40[EDT]| |NRC NOTIFIED BY: STETSON |LAST UPDATE DATE: 10/09/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 | A N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECEIVED A FULL SCRAM SIGNAL WHILE THE UNIT WAS IN CONDITION 5. | | | | DURING THE RESTORATION FROM A SAFETY TAGOUT ON THE CONTROL ROD DRIVE | | HYDRAULIC SYSTEM, A FULL REACTOR SCRAM SIGNAL WAS RECEIVED. THE VALVES FOR | | THE HYDRAULIC SYSTEM WERE RESTORED PRIOR TO THE AIR AND THE CONTROL POWER | | RESULTING IN LEAKAGE PAST THE CONTROL ROD DRIVE SEALS FILLING THE SCRAM | | DISCHARGE VOLUME. THE TIME BETWEEN THE "INSTRUMENT VOLUME NOT DRAINED" | | ALARM TO THE RECEIPT OF THE FULL SCRAM WAS SEVEN MINUTES. NO CONTROL ROD | | MOTION OCCURRED, AND ALL RODS WERE FULLY INSERTED. ALL CONTROL ROD DRIVES | | ARE ISOLATED, AND THE ACCUMULATORS ARE DEPRESSURIZED. THE SCRAM AIR HEADER | | WAS ALSO DEPRESSURIZED PRIOR TO THE EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+