U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/30/98 - 07/01/98 ** EVENT NUMBERS ** 34135 34312 34314 34444 34451 34453 34454 34455 34456 34457 34458 34459 34460 34461 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34135 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/27/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:00 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/27/98 | +------------------------------------------------+EVENT TIME: 15:30[EDT]| |NRC NOTIFIED BY: WISNIEWSKI |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 +------------------------------------------------------------------------------+ | REFUEL FLOOR BLOWOUT PANELS WILL RELIEVE AT 0.47 psig VERSUS 0.25 psig AS | | STATED IN THE FSAR. | | | | AS A RESULT OF VERMONT YANKEE HIGH ENERGY LINE BREAK INVESTIGATION ANALYSIS | | BASED ON AN ENGINEERING REVIEW OF THE REFUEL FLOOR BLOWOUT PANEL RIVETS, | | THE LICENSEE DISCOVERED THAT THE PANELS WILL RELIEVE AT 0.47 psig INSTEAD | | OF 0.25 psig AS STATED IN THE FINAL SAFETY ANALYSIS REPORT (FSAR). THIS | | POTENTIALLY PLACES THE PLANT OUTSIDE OF ITS DESIGN BASIS CONDITION WITH | | REGARD TO FSAR SECTION 12.2.1. (LOADING CONSIDERATIONS FOR STRUCTURES, | | FOUNDATIONS, EQUIPMENT AND SYSTEMS). THE ONLY SAFETY DESIGN BASIS FOR THE | | REACTOR BUILDING IS TO MEET 10 CFR 100 RELEASE REQUIREMENTS BUT THE FSAR | | DESCRIPTION OF THE REACTOR BUILDING STATES IN SEVERAL PLACES THAT THE | | REFUEL FLOOR BLOWOUT PANELS WILL RELIEVE AT 7 INCHES OF WATER (0.25 psig). | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1635 ON 06/30/98 BY MIKE SORTWELL TO JOLLIFFE * * * | | | | UPON EVALUATING THIS EVENT, THE LICENSEE DETERMINED THAT THE 0.47 psig | | VALUE HAD NO FUNCTIONAL IMPACT ON ANY SAFETY RELATED SYSTEMS. THEREFORE, | | 0.47 psig IS CONSISTENT WITH THE DESIGN BASIS AS DESCRIBED IN THE UFSAR. | | THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R1DO JOHN KINNEMAN. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34312 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 05/31/98 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 11:52 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/31/98 | +------------------------------------------------+EVENT TIME: 10:40[EDT]| |NRC NOTIFIED BY: TONER |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED PINHOLE LEAKS IN PIPING UPSTREAM OF THE PRIMARY | | COOLANT SAMPLE LINE ISOLATION VALVE. | | | | THE LICENSEE IDENTIFIED PIN HOLE LEAKS IN 1/2" PIPING ADJACENT TO AND | | UPSTREAM OF THE PRIMARY COOLANT SYSTEM SAMPLE LINE CONTAINMENT ISOLATION | | VALVE (CV-1910) WHICH IS LOCATED OUTSIDE OF CONTAINMENT. THE PIPING IN | | QUESTION IS ASME CLASS 1 PIPING AND HAS, THEREFORE, BEEN DECLARED | | INOPERABLE. THE LEAK APPEARS TO BE AT A WELD JOINT. ALTHOUGH LEAKAGE IS | | VERY SMALL(LEAKAGE HAS NOT YET BEEN QUANTIFIED) AND ENGINEERING JUDGMENT | | INDICATES THAT CONTAINMENT LEAKAGE LIMITS WOULD NOT LIKELY BE EXCEEDED EVEN | | UNDER CONTAINMENT DESIGN PRESSURE CONDITIONS, THE PLANT ENTERED TS | | 4.5.2.C(1) LCO BASED ON PIPING BEING DECLARED INOPERABLE. THE LCO ACTION | | STATEMENT REQUIRES THAT THE PLANT BE IN COLD SHUTDOWN WITHIN 30 HOURS FROM | | 1040 EDT. WELD REPAIR PLANS HAVE BEEN DEVELOPED AND ARE BEING IMPLEMENTED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | (SEE EVENT #34314.) | | | | *** UPDATE ON 6/30/98 @ 1005 BY FLENNER TO SANDIN *** EVENT RETRACTION | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE IT WAS DETERMINED THAT THE | | LEAKAGE DID NOT VIOLATE ANY TECHNICAL SPECIFICATION REQUIREMENT AND THERE | | WAS NO CODE VIOLATION. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED | | THE REG 3 RDO(MCCORMICKBARGER) WAS NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34314 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 06/01/98 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 00:25 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/31/98 | +------------------------------------------------+EVENT TIME: 23:30[EDT]| |NRC NOTIFIED BY: D VANDEWALLE |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A SECOND SMALLER LEAK FOUND FURTHER UPSTREAM OF THE LEAK REPORTED BY THE | | LICENSEE IN EVENT #34312. | | | | A SECOND PIN HOLE LEAK IN THE 0.5" ASME 11 CLASS 1 PIPING ADJACENT TO AND | | UPSTREAM OF THE PRIMARY COOLANT SYSTEM SAMPLE LINE CONTAINMENT ISOLATION | | VALVE (CV-1910) WHICH IS OUTSIDE OF CONTAINMENT WAS DISCOVERED. THE LEAK IS | | FURTHER UPSTREAM ON THE SAME SECTION OF PIPING BUT COMING FROM A FURTHER | | UPSTREAM WELD AS THE LEAK REPORTED BY THE LICENSEE IN EVENT #34312. THE | | LEAK RATE IS LESS THAN ONE DROP EVERY 5 MINUTES. PRIMARY PLANT PRESSURE IS | | 2,260 psia, AND PRIMARY PLANT TEMPERATURE IS 532 DEGREES F. PRIMARY PLANT | | COOLANT ACTIVITY IS 5E-02 microcuries/ml. DURING THE REFUELING OUTAGE, THE | | LICENSEE REPLACED AN EXISTING SECTION OF PRIMARY COOLANT SYSTEM SAMPLE | | PIPING AND TWO OUTSIDE CONTAINMENT ISOLATION VALVES ASSOCIATED WITH THE | | PIPING (CV-1910 & 1911). WELD REPAIR PLANS HAVE BEEN DEVELOPED AND ARE | | BEING IMPLEMENTED. IN A COUPLE OF HOURS, THE LICENSEE WILL ISOLATE UPSTREAM | | MANUAL ISOLATION VALVES MV-PC-1045D (UPSTREAM ISOLATION VALVE FOR CV-1901, | | PRESSURIZER VAPOR PHASE VALVE ), MV-PC-1043C (UPSTREAM ISOLATION VALVE FOR | | CV-1902, PRESSURIZER LIQUID PHASE VALVE), AND MV-PC-1023C (UPSTREAM | | ISOLATION VALVE FOR CV-1903, PRIMARY COOLANT #2 HOT LEG VALVE) TO ISOLATE | | THE LEAKS REPORTED IN THIS EVENT AND IN EVENT #34312. THE LICENSEE WILL | | THEN REPAIR THE LEAKING WELDS, UNISOLATE THE REPAIRED WELDS AND THEN | | PERFORM A LEAK TEST INSPECTION OF THE NEWLY REPAIRED WELDS, FOR LEAKAGE. | | ALL THIS SHOULD BE ACCOMPLISHED BY MONDAY AFTERNOON. THE MANUAL ISOLATION | | VALVES MENTIONED ABOVE ARE LOCATED INSIDE CONTAINMENT. | | | | THE PLANT ENTERED TECHNICAL SPECIFICATION 4.5.2 c(1) BASED ON DECLARING THE | | PIPING INOPERABLE. THE PIPING WELD REPAIRS AND LEAKAGE TESTING SHOULD BE | | COMPLETED BEFORE TECHNICAL SPECIFICATION 4.5.2 c(1) 30-HOUR TIME LIMIT FOR | | ENTERING A COLD SHUTDOWN CONDITION HAS RUN OUT. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | | | *** UPDATE ON 6/30/98 @ 1005 BY FLENNER TO SANDIN *** EVENT RETRACTION | | | | THE LICENSEE IS RETRACTING THIS EVENT SINCE IT WAS DETERMINED THAT THE | | LEAKAGE DID NOT VIOLATE ANY TECHNICAL SPECIFICATION REQUIREMENT AND THERE | | WAS NO CODE VIOLATION. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED | | | | THE REG 3 RDO(MCCORMICKBARGER) WAS NOTIFIED | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34444 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 06/27/98 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 08:12 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/27/98 | +------------------------------------------------+EVENT TIME: 07:28[EDT]| |NRC NOTIFIED BY: MOSHER |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES OGLE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABLE SAFETY PARAMETER DISPLAY SYSTEM (SPDS). | | | | THE PLANT'S SPDS WAS INOPERABLE FOR MORE THAN 1 HOUR DUE TO A COMPUTER | | FAILURE. MAINTENANCE PERSONNEL ARE CURRENTLY WORKING ON THE SPDS | | COMPUTERS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | | | | * * * UPDATE AT 1807 ON 06/30/98 BY PHIL BRADLEY TO JOLLIFFE * * * | | | | AT 1727 ON 06/30/98, THE LICENSEE RESTORED THE SAFETY PARAMETER DISPLAY | | SYSTEM TO OPERABLE STATUS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO CHUCK OGLE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34451 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: CONAM INSPECTION COMPANY |NOTIFICATION DATE: 06/29/98 | | CITY: GLENDALE HEIGHT REGION: 3 |NOTIFICATION TIME: 13:21 [ET]| | COUNTY: STATE: IL |EVENT DATE: 06/29/98 | |LICENSE#: 12-16559-01 AGREEMENT: Y |EVENT TIME: 10:15[CDT]| | DOCKET: |LAST UPDATE DATE: 06/30/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |J MCCORMICKBARGER,R3 RDO | | |JOSE PICCONE, NMSS EO | +------------------------------------------------+CHARLES CAIN, R4 RDO | |NRC NOTIFIED BY: BOB SLACK |STUART RUBIN IRD | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNDAMAGED RADIOGRAPHY CAMERA LEFT UNATTENDED FOR APPROXIMATELY 2 HOURS - | | | | TWO RADIOGRAPHERS EMPLOYED BY CONAM INSPECTION COMPANY, GLENDALE HEIGHTS, | | IL, INADVERTENTLY LEFT A RADIOGRAPHY CAMERA WITH A 55 CURIE IRIDIUM-192 | | SOURCE UNATTENDED FROM 0830 HST TO 1050 HST ON 06/26/98 AT THE TESORO | | CORPORATION PETROLEUM REFINERY IN KAPOLEI, OAHU, HI. THE RETRIEVED CAMERA | | WAS LOCKED, HAD NOT BEEN OPENED OR TAMPERED WITH AND WAS NOT DAMAGED AND | | THE SOURCE WAS NOT EXPOSED. NO PERSONNEL HAD BEEN EXPOSED TO RADIATION | | FROM THE CAMERA. | | | | THE LICENSEE PLANS TO SUBMIT A WRITTEN REPORT TO NRC REGIONS 3 AND 4 | | WITHIN 30 DAYS. | | | | * * * UPDATE AT 1453 ON 06/30/98 FROM BOB SLACK TO S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS REPORT BASED ON A DISCUSSION WITH | | REGION 3 JAMNES CAMERON. THE NRC OPERATIONS OFFICER NOTIFIED THE | | R3DO JIM McCORMICK-BARGER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34453 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 06/29/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 20:56 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 06/29/98 | +------------------------------------------------+EVENT TIME: 19:08[CDT]| |NRC NOTIFIED BY: VERLE CASTLE |LAST UPDATE DATE: 07/01/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |LEDYARD (TAD) MARSH EO | | |GARY BELCHER FEMA | | |STUART RUBIN IRD | | |MARK RING REG3 | | |JIM CALDWELL REG3 | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - UE DECLARED DUE TO LOSS OF 3 OF 4 OFFSITE POWER SOURCES WHILE SHUTDOWN - | | | | AT 1908 CDT ON 06/29/98, WITH THE PLANT IN OPERATIONAL CONDITION 4 (COLD | | SHUTDOWN) IN A REFUELING OUTAGE SINCE SEPTEMBER, 1996, THE LICENSEE | | DECLARED AN UNUSUAL EVENT AT THE SHIFT SUPERVISOR'S DISCRETION DUE TO | | DAMAGED OFFSITE ELECTRICAL POWER LINES. | | | | SEVERE THUNDERSTORMS, TORNADOES, AND HIGH WINDS DEENERGIZED AND KNOCKED | | DOWN 2 OF 3 OFFSITE 345 KV POWER LINES AND 1 OF 1 OFFSITE 138 KV POWER LINE | | RENDERING THE SPENT FUEL POOL COOLING AND BUILDING VENTILATION SYSTEMS | | INOPERABLE. THE EMERGENCY RESERVE AUXILIARY TRANSFORMER FEED TO SAFETY | | BUSES WAS LOST AND TWO SAFETY BUSES AUTO TRANSFERRED TO THE REMAINING | | ALTERNATE OFFSITE 345 KV POWER SOURCE. | | | | ONE OF TWO SHUTDOWN COOLING PUMPS ('B' RHR PUMP) TRIPPED DUE TO THE BUS | | TRANSFER AND HAS SINCE BEEN RESTARTED. THE 'A' RHR PUMP IS OPERABLE. THE | | REACTOR WATER CLEANUP SYSTEM REMAINED IN SERVICE TO REMOVE DECAY HEAT | | THROUGHOUT THIS EVENT. REACTOR COOLING SYSTEM TEMPERATURE REMAINED STABLE | | AT 105øF AND REACTOR VESSEL WATER LEVEL REMAINS STABLE AT 95 INCHES (NORMAL | | LEVEL) THROUGHOUT THIS EVENT. | | | | DIVISIONS 1 AND 2 EMERGENCY CORE COOLING SYSTEMS AND DIVISIONS 1 AND 2 | | EMERGENCY DIESEL GENERATORS (EDGs) ARE OPERABLE. DIVISION 3 EDG AND HIGH | | PRESSURE CORE SPRAY SYSTEM ARE INOPERABLE DUE TO MAINTENANCE ACTIVITIES. | | | | NO OTHER SAFETY RELATED EQUIPMENT WAS LOST AND THERE WAS NO DAMAGE TO | | ONSITE PLANT EQUIPMENT AND NO PERSONNEL WERE INJURED. MINOR DAMAGE WAS | | SUSTAINED OUTSIDE THE SWITCHYARD. | | | | THE LICENSEE IS IN THE PROCESS OF RESTORING THE SPENT FUEL POOL COOLING | | SYSTEM AND IS INVESTIGATING THIS EVENT. | | | | THE PLANT IS STABLE IN OPERATIONAL CONDITION 4 (COLD SHUTDOWN). | | | | THE LICENSEE NOTIFIED THE NRC SENIOR RESIDENT INSPECTOR AND THE RESIDENT | | INSPECTOR AND THEY RESPONDED TO THE SITE. | | | | ***UPDATE ON 06/30/98 AT 2357 ET BY VOLKER TAKEN BY MACKINNON*** | | | | UNUSUAL EVENT TERMINATED AT 2020 CT ON 06/30/98 WHEN 3 OF THE 4 OFFSITE | | POWER SOURCES WERE RESTORED. ALL THREE 345KV OFFSITE POWER SOURCES ARE BACK | | IN SERVICE. THE ESTIMATED TIME THAT THE 138KV OFFSITE POWER SOURCE WILL BE | | RESTORED TO SERVICE IS IN 3 DAYS. R3DO (McCORMICK-BARGER), FEMA (DEPUY) NRR | | EO (CAPRA) NOTIFIED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE OF THE | | TERMINATION OF THE UNUSUAL EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34454 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/30/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 06:17 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/30/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/30/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JIM MCCORMICKBARGER RDO | | DOCKET: 0707002 |STEVE BAGGETT EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: NOEL | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A 4 HOUR REPORT FOR THE PLANT EXCEEDING ITS OPACITY LIMIT | | | | AT 0300 THE #2 PRECIPITATOR ON THE #2 BOILER AT THE X-600 STEAM PLANT | | FAILED. AT 0320 THE FACILITY EXCEEDED THEIR OPACITY LIMIT WHEN IT WENT | | ABOVE 21%. THE LIMIT IS ABOVE 21% BUT BELOW 60% FOR MORE THAN 6 MINUTES IN | | ONE HOUR. AT 0430 THE SECOND CRITERIA WAS EXCEEDED WHEN OPACITY WENT ABOVE | | 60%. PLANT PERSONNEL ATTEMPTED TO PUT THE PACKAGE BOILER ON LINE TO REDUCE | | OPACITY, BUT THERE WAS AN OPERATIONAL PROBLEM WITH IT. THE #2 BOILER | | REMAINS ON WITH THE FAILED PRECIPITATOR. PLANT PERSONNEL ARE | | TROUBLESHOOTING THE PROBLEM WITH THE PACKAGE BOILER, SO THAT IT CAN BE PUT | | ON LINE TO REDUCE THE OPACITY. WHEN THE PACKAGE BOILER IS ON LINE, THE #2 | | BOILER CAN BE SHUT DOWN FOR REPAIR OF THE PRECIPITATOR. | | | | THE PLANT NOTIFIED THE OHIO EPA AND THE NRC RESIDENT INSPECTOR. | | | | THEY WILL NOTIFY THE DOE SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34455 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US AIR FORCE |NOTIFICATION DATE: 06/30/98 | | CITY: ANDREWS AIR FOR REGION: 1 |NOTIFICATION TIME: 08:03 [ET]| | COUNTY: STATE: MD |EVENT DATE: 05/19/98 | |LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/30/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES CAIN RDO | | |SCOTT MOORE NMSS EO | +------------------------------------------------+FEMA, DOE, USDA, HHS FAX | |NRC NOTIFIED BY: JORDAN |EPA, DOT(VIA NRC) FAX | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. AIR FORCE AT BOLLING AIR FORCE BASE, D.C. REPORTED THAT THERE WAS | | A CHEMICAL AGENT MONITOR(CAM) MISSING FROM ANDREWS AIR FORCE BASE, MD. | | | | UPON TAKING A LATE 6 MONTH PHYSICAL INVENTORY AND ANNUAL SWIPE SAMPLES OF | | THE CAMs LOCATED AT THE BASE, IT WAS DETERMINED THAT THEY HAD MORE CAMS | | THAN THEY WERE ACCOUNTABLE FOR, BUT WERE SHORT ONE CAM THAT WAS LISTED ON | | THEIR INVENTORY RECORDS. THIS CAM(SERIAL # Z16-M-1745) CONTAINED 250 | | MICROCURIES OF AM-241. AT THIS TIME THEY HAVE NO IDEA OF WHERE THE CAM IS | | LOCATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34456 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 06/30/98 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 10:48 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 06/30/98 | +------------------------------------------------+EVENT TIME: 10:15[EDT]| |NRC NOTIFIED BY: NIX |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES OGLE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED THE "1A" REACTOR BUILDING SPRAY (RBS) PUMP INOPERABLE | | | | THE "1B" RBS PUMP WAS OUT OF SERVICE FOR MAINTENANCE WHEN IT WAS DISCOVERED | | THAT THE "1A" RBS PUMP OIL BUBBLER WAS EMPTY. UPON THE RESULTS OF AN | | ENGINEERING EVALUATION, THE "1A" RBS PUMP WAS DECLARED INOPERABLE AT 1015 | | AND THE PLANT ENTERED TECH SPEC LCO 3.0, WHICH REQUIRES THE PLANT TO BE IN | | HOT SHUTDOWN WITHIN 12 HOURS. | | | | SINCE THE RBS SYSTEM IS RELIED UPON TO MITIGATE THE CONSEQUENCES OF CERTAIN | | DESIGN BASIS ACCIDENTS, SUCH AS LOSS OF COOLANT ACCIDENT, THIS CONDITION IS | | BEING REPORTED AS AN EVENT OR CONDITION THAT ALONE COULD HAVE PREVENTED THE | | FULFILLMENT OF THE SAFETY FUNCTION OF STRUCTURES OR SYSTEMS THAT ARE NEEDED | | TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. MAINTENANCE AND ENGINEERING | | ARE CONTINUING TO INVESTIGATE THE CONDITION OF THE "1A" RBS PUMP AND | | EFFORTS ARE IN PROGRESS TO RESTORE THE "1B" RBS PUMP TO SERVICE. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | | | | * * * UPDATE AT 1717 BY MIKE HILL TO JOLLIFFE * * * | | | | AT 1523, THE LICENSEE RESTORED THE "1B" RBS PUMP TO OPERABLE STATUS AND | | EXITED TECH SPEC LCO 3.0. THE LICENSEE PLANS TO SUBMIT A WRITTEN LICENSEE | | EVENT REPORT TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R2DO CHUCK OGLE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34457 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 06/30/98 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/30/98 | +------------------------------------------------+EVENT TIME: 14:15[CDT]| |NRC NOTIFIED BY: PAUL HANSEN |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 +------------------------------------------------------------------------------+ | - IOWA STATE NOTIFIED OF LOW pH CIRC WATER DISCHARGE TO CEDAR RIVER - | | | | AT 1415 CDT, THE LICENSEE NOTIFIED THE IOWA DEPARTMENT OF NATURAL RESOURCES | | THAT A GRAB SAMPLE OF THE CIRCULATING WATER DISCHARGED TO THE CEDAR RIVER | | INDICATED A pH OF 2.92. THE LICENSEE NPDES ACCEPTABLE pH RANGE IS 6-9. | | THE LICENSEE STOPPED THE PLANT DISCHARGE, IS REPAIRING THE CIRCULATING | | WATER ACID pH CONTROLLER, AND IS DETERMINING THE TIME AND AMOUNT OF THE | | UNACCEPTABLE LOW pH PLANT DISCHARGE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34458 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/30/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:12 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/30/98 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: DON TORBITT |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN KINNEMAN 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 +------------------------------------------------------------------------------+ | -CONTROL ROOM VENTILATION SYSTEM DESIGN IS OUTSIDE THE PLANT DESIGN BASIS- | | | | DURING A RECENT LICENSEE ENGINEERING REVIEW OF THE VULNERABILITY OF A | | SINGLE FAILURE OF THE CONTROL ROOM VENTILATION (CRV) SYSTEM, THE LICENSEE | | IDENTIFIED THAT A DESIGN CHANGE IMPLEMENTED IN 1994 RESULTED IN A SINGLE | | POWER SUPPLY FOR THE CRV SYSTEM INLET AND OUTLET MOTOR OPERATED VALVES | | (MOVs). FOLLOWING THE DESIGN CHANGE IMPLEMENTATION, THE CRV SYSTEM HAD | | NOT BEEN ADEQUATELY TESTED IN A CONFIGURATION WHERE BOTH MOVs COULD FAIL | | OPEN AS A RESULT OF THE FAILURE OF THE SINGLE POWER SUPPLY. SUBSEQUENT | | TESTING HAS CONFIRMED THAT THE CONTROL ROOM PRESSURE BOUNDARY DESIGN | | REQUIREMENTS WOULD NOT HAVE BEEN MET WITH BOTH MOVs FAILED OPEN. | | | | THE LICENSEE DETERMINED THAT THIS CONDITION IS OUTSIDE THE DESIGN BASIS | | OF THE PLANT. | | | | AT THE TIME THE LICENSEE IDENTIFIED THIS CONDITION, THE CRV SYSTEM WAS | | OPERATING IN THE ISOLATE MODE. THE CRV SYSTEM IS OPERABLE IN THE ISOLATE | | MODE AND INOPERABLE (BUT FUNCTIONAL) IN THE NORMAL AND RECIRC MODES. | | | | THE LICENSEE IS DETERMINING ACTIONS TO CORRECT THIS CONDITION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34459 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US STEEL, FAIRFIELD, ALABAMA |NOTIFICATION DATE: 06/30/98 | | CITY: FAIRFIELD REGION: 2 |NOTIFICATION TIME: 17:21 [ET]| | COUNTY: STATE: AL |EVENT DATE: 06/23/98 | |LICENSE#: 145 AGREEMENT: Y |EVENT TIME: 12:50[CDT]| | DOCKET: |LAST UPDATE DATE: 06/30/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHARLES OGLE RDO | | |MICHAEL WEBER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: JIM McNEES, AL RAD CONTRL | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TWO MAINTENANCE WORKERS EXPOSED TO LOW LEVELS OF RADIATION - | | | | ON 06/25/98, THE ALABAMA OFFICE OF RADIATION CONTROL RECEIVED A FAX FROM | | NRC REGION II INDICATING THAT A REPRESENTATIVE OF THE US STEEL PLANT IN | | FAIRFIELD, AL, (ALABAMA RADIOACTIVE MATERIAL LICENSE #145) HAD CONTACTED | | NRC REGION II CONCERNING TWO MAINTENANCE WORKERS THAT HAD BEEN EXPOSED TO | | LOW LEVELS OF RADIATION. (THIS EVENT IS ALABAMA INCIDENT #98-11). | | | | ON 06/23/98, A SMALL METAL ROD CONTAINING A 3 mCi Cs-137 RADIOACTIVE SOURCE | | FELL OUT OF THE BOTTOM OF THE SOURCE ROD TUBE IN THE WELL OF A RONAN MODEL | | X-92 MOLD LEVEL GAUGE ONTO THE FLOOR WHEN TWO MAINTENANCE WORKERS MOVED | | THE GAUGE. ONE OF THE WORKERS PICKED THE ROD UP WITH A PAIR OF PLIERS AND | | PLACED IT BACK INTO THE WELL OF THE GAUGE. THE ROD HAD COME LOOSE DUE TO | | A BROKEN WELD THAT SHOULD HAVE HELD THE ROD INSIDE THE SOURCE ROD TUBE. | | | | THE WORKERS RECEIVED AN ESTIMATED DOSE OF 0.35 mREM. THIS DOSE IS | | APPROXIMATELY EQUAL TO ONE DAY'S EXPOSURE TO NATURAL BACKGROUND RADIATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34460 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WESTINGHOUSE ELECTRIC CORPORATION |NOTIFICATION DATE: 06/30/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 17:36 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 06/30/98 | | COMMERCIAL LWR FUEL |EVENT TIME: 03:00[EDT]| | |LAST UPDATE DATE: 06/30/98 | | CITY: COLUMBIA REGION: 2 +-----------------------------+ | COUNTY: RICHLAND STATE: SC |PERSON ORGANIZATION| |LICENSE#: SNM-1107 AGREEMENT: Y |CHARLES OGLE RDO | | DOCKET: 07001151 |MICHAEL WEBER, NMSS EO | +------------------------------------------------+FRANK CONGEL IRD | |NRC NOTIFIED BY: WILBER GOODWIN | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - NRC BULLETIN 91-01 (24 HOUR REPORT) - | | | | AT 0300 ON 06/30/98, THE LICENSEE DISCOVERED THAT APPROXIMATELY 40 KG OF | | U3O8 POWDER (CONTAINING LESS THAN 1WT% WATER, AT 3.80 wt% U-235) HAD | | SPILLED FROM THE FEED LINE (FAVORABLE GEOMETRY) ONTO THE MEZZANINE LEVEL | | FLOOR IN THE PELLETING MANUFACTURING AREA, LINE #3 (NON-MODERATION CONTROL | | AREA) IN THE WESTINGHOUSE COMMERCIAL FUEL FABRICATING FACILITY, COLUMBIA, | | SC. | | | | THE SPILL RESULTED FROM A FAILURE OF AN END CAP CLAMP ON A TWO INCH | | DIAMETER FEED LINE WHICH RATE FEEDS MATERIAL INTO THE MAIN POWDER STREAM AS | | PART OF THE POWER PREPARATION PROCESS. NO SPECIFIC CONTROLS WERE IN PLACE | | TO ENSURE THAT THE SPILLED MATERIAL WOULD REMAIN IN A FAVORABLE GEOMETRY; | | DOUBLE CONTINGENCY PROTECTION (FAVORABLE GEOMETRY AND MASS) OF THE AS-FOUND | | CONDITION COULD NOT BE DEMONSTRATED. | | | | UPON DISCOVERY, THE LICENSEE IMMEDIATELY SHUT THE PROCESS DOWN, CLEANED UP | | THE SPILL, AND REPLACED THE END CAP CLAMP AND THEN INSPECTED OTHER PELLET | | LINES TO ENSURE THAT THIS CONDITION DID NOT EXIST ELSEWHERE IN THE PLANT. | | | | HEALTH PHYSICS TECHNICIANS DETERMINED THAT AIRBORNE RADIATION LEVELS WERE | | NOT ELEVATED. NO PERSONNEL WERE EXPOSED TO RADIATION. | | | | AT NO TIME WAS CRITICALITY POSSIBLE BECAUSE THERE WAS INSUFFICIENT MASS AND | | NO MODERATOR PRESENT. NO SAFETY SYSTEMS WERE AFFECTED. | | | | THIS EVENT CONSTITUTES A NUCLEAR CRITICALITY SAFETY INCIDENT FOR WHICH LESS | | THAN DOUBLE CONTINGENCY PROTECTION REMAINS AND LESS THAN A SAFE MASS IS | | INVOLVED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34461 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 06/30/98 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 19:20 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 06/30/98 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: DAVE FIELDS |LAST UPDATE DATE: 06/30/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES OGLE 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - EDG OUTPUT BREAKERS MAY CLOSE DURING RESTORATION FROM A SBO CONDITION - | | | | LICENSEE SITE ENGINEERING PERSONNEL HAVE EVALUATED A SCENARIO UNDER | | WHICH THE EMERGENCY DIESEL GENERATOR (EDG) OUTPUT BREAKERS MAY CLOSE | | UNEXPECTEDLY, POTENTIALLY CAUSING DAMAGE TO THE EDGs. THIS SCENARIO | | ONLY APPLIES DURING THE RESTORATION PHASE FROM A STATION BLACKOUT (SBO) | | CONDITION. | | | | IN AN EVENT WHERE AN EDG FROM ONE UNIT IS POWERING THE OTHER UNIT VITAL | | BUS VIA THE STATION BLACKOUT CROSS TIE BREAKER, IF AN ASSOCIATED EDG | | STARTS ON THE BLACKED-OUT UNIT, THE OUTPUT BREAKER MAY CLOSE UNEXPECTEDLY, | | POTENTIALLY PLACING THE EDGs IN PARALLEL OPERATION. THE STATION BLACKOUT | | CROSS TIE BREAKER IS CONSIDERED OPERABLE. | | | | DUE TO SIMILARITY IN EDG CIRCUITRY, THIS CONDITION APPLIES TO BOTH UNITS. | | | | AS AN INTERIM MEASURE, PLANT OPERATORS HAVE BEEN ALERTED TO THE POTENTIAL | | FOR THIS CONDITION. THE LICENSEE PLANS TO REVISE APPROPRIATE PROCEDURES | | TO PREVENT THIS SCENARIO. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+