U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/22/97 - 04/23/97 ** EVENT NUMBERS ** 32191 32193 32194 32195 32196 32197 32198 32199 32200 32201 32202 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32191 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/21/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:03 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/21/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 12:45[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/22/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |MONTE PHILLIPS RDO | | DOCKET: 0707001 |CHARLEY HAUGHNEY EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: CARVER | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PRIMARY CONDENSATE ALARM DUE TO A FAULTY CONDUCTIVITY CELL PROBE | | | | AT 1250 CDT ON 04/21/97, THE WATER INVENTORY CONTROL SYSTEM (PRIMARY | | CONDENSATE LEVEL) ACTUATED ON THE #1 SOUTH AUTOCLAVE IN THE C-333-A FEED | | VAPORIZATION FACILITY. THE PRIMARY CONDENSATE ALARM OCCURRED APPROXIMATELY | | 40 MINUTES INTO A URANIUM HEXAFLUORIDE CYLINDER HEATING CYCLE IN | | PREPARATION FOR URANIUM HEXAFLUORIDE REMOVAL. THIS ALARM WAS THE RESULT OF | | AN ACTUATION OF THE CONDUCTIVITY CELL INSTRUMENTATION WHICH OCCURRED AT | | 1245 CDT. THE CONDUCTIVITY CELL PROBE ACTUATION AUTOMATICALLY CLOSES STEAM | | SUPPLY VALVES AND OPERATES AN INTERLOCK SYSTEM TO ISOLATE THE AUTOCLAVE. | | THIS CAUSED THE PRIMARY CONDENSATE ALARM TO ACTUATE AFTER DETECTING | | STANDING WATER IN THE CONDENSATE DRAIN LINE AS DESIGNED. AT THE TIME OF | | THE PRIMARY CONDENSATE LEVEL ALARM, THE ALARM RESPONSE PROCEDURE WAS | | FOLLOWED, AND RESULTS INDICATED THAT NO URANIUM HEXAFLUORIDE RELEASE HAD | | OCCURRED. THE DEFECTIVE CONDUCTIVITY CELL PROBE WAS REPLACED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 04/22/97, AT 1445 FROM BOREN TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT NOTIFICATION FOLLOWING A REVIEW WHICH CONCLUDED THAT | | THE WATER INVENTORY CONTROL SYSTEM (WICS) ACTUATION WAS NOT REPORTABLE. THE | | LICENSEE DETERMINED THAT AT THE TIME OF THE WICS ALARM, THE AUTOCLAVE HAD | | ALREADY BEEN ISOLATED BY THE CONDUCTIVITY CELL ISOLATION SYSTEM, THEREBY, | | COMPLETING THE REQUIRED SAFETY FUNCTION. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. THE R3DO | | (PHILLIPS) AND NMSS EO (COMBS) WERE NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32193 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/21/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 22:39 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/21/97 | +------------------------------------------------+EVENT TIME: 20:45[CDT]| |NRC NOTIFIED BY: DRAHOTA |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN ZWOLINSKI, NRR EO | | |CARR FEMA | | |STUART RUBIN IRD | | |BILL JOHNSON REG4 | | |PAT GWYNN REG4 | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT AND MANUAL REACTOR TRIP DUE TO A MAJOR STEAM LINE BREAK IN | | THE TURBINE BUILDING (REFER TO EVENT #32198 FOR ADDITIONAL INFORMATION.) | | | | THERE WAS A MAJOR FISH-MOUTH BREAK AT THE ELBOW OF THE 12" MAIN STEAM | | EXTRACTION LINE TO THE #5 HEATER. AT 2025 CDT, THE REACTOR WAS MANUALLY | | TRIPPED FROM 100% DUE TO THIS BREAK. ALL CONTROL RODS FULLY INSERTED, | | EMERGENCY BORATION WAS INITIATED, AND ADEQUATE SHUTDOWN MARGIN WAS | | VERIFIED. THERE WAS NO INJECTION AND NO RELIEF VALVES LIFTED. THE | | CONDENSER IS THE HEAT SINK VIA THE STEAM DUMP VALVES. THE PLANT IS STABLE | | AT THIS TIME AND WILL REMAIN IN MODE 3. ALL FOUR REACTOR COOLANT PUMPS ARE | | RUNNING, AND ALL SAFETY-RELATED EQUIPMENT IS OPERABLE. THE FIRE PUMPS HAVE | | BEEN TAKEN TO PULLOUT TO ISOLATE SPRAYS ON TURBINE ELECTRICAL EQUIPMENT. | | THE PLANT RECEIVED A GROUND ON DC BUS #1 DUE TO STEAM SPRAY. THERE WERE NO | | PERSONNEL INJURIES AND THE LICENSEE IS CHECKING FOR DAMAGE. | | | | THE NRC RESIDENT INSPECTOR ALONG WITH STATE AND LOCAL AGENCIES WERE | | INFORMED BY THE LICENSEE. | | | | * * * UPDATE ON 04/22/97, AT 0044 EDT FROM DRAHOTA TAKEN BY MACKINNON * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 2345 CDT ON 04/21/97 DUE TO THE PLANT | | BEING IN A STABLE CONDITION. DURING THE EVENT, THE PLANT HAD INTERMITTENT | | ELECTRICAL GROUNDS ON VITAL BUS 1B4C BUT THE GROUNDS CLEARED. THE LICENSEE | | IS IN THE PROCESS OF PLACING THE FIRE SUPPRESSION SYSTEM BACK IN SERVICE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY STATE | | AND LOCAL OFFICIALS. THE NRC OPERATIONS CENTER NOTIFIED THE R4DO | | (HARRELL), NRR EO (ZWOLINSKI), AEOD IRD (RUBIN), AND FEMA (BELECHER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32194 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/22/97 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 04:26 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/22/97 | +------------------------------------------------+EVENT TIME: 03:52[EDT]| |NRC NOTIFIED BY: FRED OWENS |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KEN BARR RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOHN ZWOLINSKI, NRR EO | | |STU RUBIN, AEOD IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMMENCEMENT OF A UNIT 2 REACTOR SHUTDOWN DUE TO UNIDENTIFIED REACTOR | | COOLANT SYSTEM PRESSURE BOUNDARY LEAK GREATER THAN 1 GPM (REFER TO EVENT | | #32197 FOR ADDITIONAL INFORMATION.) | | | | AT 2245 EDT ON 04/21/97, UNIT 2 DEVELOPED A LEAK IN THE REACTOR COOLANT | | SYSTEM. THE CONTAINMENT RADIATION MONITOR SLOWLY INCREASED INTO ALARM | | STATE, AND A MISMATCH DEVELOPED IN THE CHARGING/LETDOWN FLOWS. THE | | COMPUTER CALCULATED LEAK RATE AT 2.36 GPM. PER TECHNICAL SPECIFICATION | | 3.1.6 (UNIDENTIFIED REACTOR COOLANT SYSTEM LEAK RATE GREATER THAN 1 GPM), | | AN INVESTIGATION OF THE LEAKAGE SOURCE WAS INITIATED. A CONTAINMENT ENTRY | | WAS MADE, AND THE LEAK WAS OBSERVED TO BE IN THE AREA OF THE #2A1 REACTOR | | COOLANT PUMP. DUE TO THE LOCATION AND NATURE OF THE LEAK AND THE DOSE | | RATES, THE LICENSEE COULD NOT POSITIVELY IDENTIFY THE LEAKING COMPONENT. | | AT 0352 EDT ON 04/22/97, THE LICENSEE BEGAN REDUCING REACTOR POWER TO 15% | | TO EVALUATE THE LEAK. (THE LICENSEE PLANS TO TAKE 4 TO 6 HOURS TO REDUCE | | REACTOR POWER TO 15%.) THE LATEST LEAK RATE CALCULATION WAS 3.41 GPM. | | ALL SYSTEMS (INCLUDING EMERGENCY CORE COOLING AND EMERGENCY POWER SYSTEMS) | | ARE FULLY OPERABLE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED BY THE LICENSEE AND IS NOW IN | | THE CONTROL ROOM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32195 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 04/22/97 | |UNIT: [ ] [2] [ ] STATE: TX |NOTIFICATION TIME: 09:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/21/97 | +------------------------------------------------+EVENT TIME: 11:02[CDT]| |NRC NOTIFIED BY: JOHN CRAIN |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |ADEV 50.72(b)(1)(i)(B) DEVIATION FROM T SPEC | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -TWO UNIT 2 MAIN STEAM SAFETY VALVES TESTED ABOVE TECH SPEC SETPOINT LIMIT- | | | | THE LICENSEE TESTED THE UNIT 2 MAIN STEAM SAFETY VALVES IN ACCORDANCE WITH | | TECHNICAL SPECIFICATION 3.7.1.1. THE RESULTS INDICATED THAT 18 OF 20 MAIN | | STEAM SAFETY VALVE LIFT SETPOINTS WERE WITHIN 3% TOLERANCE IN ACCORDANCE | | WITH TECHNICAL SPECIFICATION 3.7.1.1. THE FOLLOWING MAIN STEAM SAFETY | | VALVES WERE FOUND TO BE OUTSIDE THE TECHNICAL SPECIFICATION ALLOWED 3% LIFT | | SETPOINT TOLERANCE: | | | | MS-PV-7440 REQUIRED SETPOINT: 1285 PSIG, AS-FOUND LIFT SETPOINT: 1340 PSIG | | MS-PV-7430A REQUIRED SETPOINT: 1295 PSIG, AS-FOUND LIFT SETPOINT: 1378 PSIG | | | | ALL VALVES WERE ADJUSTED AND INDIVIDUALLY TESTED TO WITHIN THE REQUIRED | | LIFT SETPOINT TOLERANCE OF 1% AS SPECIFIED IN TECHNICAL SPECIFICATION | | 3.7.1.1. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32196 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/22/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 12:06 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/22/97 | +------------------------------------------------+EVENT TIME: 11:16[EDT]| |NRC NOTIFIED BY: HUTTON |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |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 | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PLANT SHUTDOWN DUE TO TECHNICAL SPECIFICATION 3.0.A LIMITING CONDITION FOR | | OPERATION (LCO) ACTION STATEMENT ENTRY BECAUSE OF SLOW ROD INSERTION TIMES | | | | AS A RESULT OF FURTHER EVALUATION OF SCRAM TIME TESTING DATA FROM A POWER | | REDUCTION PERFORMED LAST WEEKEND, THE LICENSEE DETERMINED THAT THE | | INSERTION TIMES OF THE 5% REFERENCE SAMPLE (7 CONTROL RODS OUT OF 137) | | WERE ABOVE THE ALLOWABLE TECHNICAL SPECIFICATION CRITERIA. THIS MEANS | | THAT THE CONTROL RODS INSERTED TOO SLOWLY FOR THE FIRST 5% OF ROD | | INSERTION. (THE REFERENCE SAMPLE AVERAGE WAS 0.404 SECONDS.) THE TECHNICAL | | SPECIFICATION REQUIRED 5% INSERTION TIME IS 0.375 SECONDS. THE ASSUMPTION | | IS THAT THE WHOLE CORE HAS THE SAME AVERAGE SCRAM TIME AS THE REFERENCE | | SAMPLE. THE CORE IS BEING EVALUATED, AND NO CORRECTIVE ACTION PLAN HAS | | YET BEEN DETERMINED. TECHNICAL SPECIFICATION 3.0.A LCO ACTION STATEMENT | | REQUIRES THE PLANT TO BE IN COLD SHUTDOWN CONDITION WITHIN 30 HOURS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED BY THE LICENSEE, AND THE | | LICENSEE PLANS TO NOTIFY STATE AND LOCAL OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32197 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/22/97 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 16:28 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/22/97 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: REPKO |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |AL CHAFFEE, NRR EO | | |CIBOCH FEMA | | |STUART RUBIN, AEOD IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 DECLARED AN UNUSUAL EVENT DUE TO A REACTOR COOLANT SYSTEM PRESSURE | | BOUNDARY LEAK GREATER THAN 10 GPM. (REFER TO EVENT #32194 FOR ADDITIONAL | | INFORMATION.) | | | | THE LICENSEE HAS CALCULATED A REACTOR COOLANT SYSTEM PRESSURE BOUNDARY LEAK | | RATE OF GREATER THAN 10 GPM. (THE MAXIMUM CALCULATED VALUE IS | | 11 GPM.) THE LEAKAGE APPEARS TO BE ASSOCIATED WITH THE HIGH PRESSURE | | INJECTION CHARGING LINE, BUT THE LICENSEE CANNOT POSITIVELY IDENTIFY | | THE SOURCE OF THE LEAK DUE TO THE AMOUNT OF STEAM AND SPRAY IN THE AREA. | | THE LEAK IS, HOWEVER, IN THE PROXIMITY OF A VALVE, BUT ITS SOURCE CANNOT | | BE IDENTIFIED. THE LICENSEE PERFORMED A CONTROLLED PLANT SHUTDOWN, AND | | UNIT 2 IS NOW IN THE HOT SHUTDOWN MODE WITH THE MAIN CONDENSER AS THE HEAT | | SINK. THE LICENSEE PLANS TO REDUCE PRESSURE TO 1000 PSIG BY 04/23/97. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | | | | *** UPDATE AT 2044 FROM GREWE TO GOULD*** | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 2032 WHEN TWO CONSECUTIVE | | REACTOR COOLANT SYSTEM LEAK RATES (8.645 GPM AND 6.93 GPM) WERE MEASURED AT | | LESS THAN 10 GPM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (BELISLE), NRR EOs (CHAFFEE AND VARGA), FEMA | | (CIBOCH), AND AEOD IRD (RUBIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32198 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/22/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 17:20 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/22/97 | +------------------------------------------------+EVENT TIME: 13:49[CDT]| |NRC NOTIFIED BY: BANNISTER |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE NEBRASKA DEPARTMENT OF ENVIRONMENTAL QUALITY AND | | PLANS TO NOTIFY THE NATIONAL RESPONSE CENTER OF A RELEASE OF ASBESTOS TO | | THE ENVIRONMENT. (REFER TO EVENT #32193 FOR ADDITIONAL INFORMATION.) | | | | THIS OCCURRED AS A RESULT OF THE EXTRACTION STEAM LINE RUPTURE IN THE | | TURBINE BUILDING (EVENT #32193). THE ASBESTOS PARTICLES IN THE TURBINE | | BUILDING WERE RELEASED TO THE ATMOSPHERE VIA THE TURBINE BUILDING ROOF | | FANS, AND THE ASBESTOS PARTICLES WERE CARRIED TO THE RIVER VIA THE FIRE | | PROTECTION WATER BY THE TURBINE BUILDING SUMP PUMPS. THE LICENSEE HAS | | TAKEN 20 SAMPLES, AND 2 OF 8 SAMPLES TESTED SO FAR CONTAIN TRACES OF | | ASBESTOS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32199 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: STEELASTIC CO LLC, AKRON, OHIO |NOTIFICATION DATE: 04/22/97 | | CITY: AKRON REGION: 3 |NOTIFICATION TIME: 17:33 [ET]| | COUNTY: STATE: OH |EVENT DATE: 04/22/97 | |LICENSE#: 1933-70 AGREEMENT: N |EVENT TIME: 12:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/22/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MONTE PHILLIPS RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+STUART RUBIN, AEOD FEMA | |NRC NOTIFIED BY: BLEIWEISS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A MISSING GAUGE CONTAINING 150 MILLICURIES OF | | AMERICIUM-241. THIS GAUGE HAS NOT BEEN IN SERVICE SINCE 01/95. THE GAUGE | | WAS DETERMINED TO BE MISSING DURING AN INVENTORY CHECK. THE TYPE OF GAUGE | | WAS UNKNOWN BUT IT WAS EITHER MANUFACTURED OR SUPPLIED BY NDC SYSTEMS. | | | | REFER TO THE HOO LOG FOR A CONTACT TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32200 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ACALA, ROCK ISLAND, ILLINOIS |NOTIFICATION DATE: 04/22/97 | | CITY: ROCK ISLAND REGION: 3 |NOTIFICATION TIME: 17:41 [ET]| | COUNTY: STATE: IL |EVENT DATE: 04/22/97 | |LICENSE#: 1200722-13&14 AGREEMENT: Y |EVENT TIME: 15:13[CDT]| | DOCKET: |LAST UPDATE DATE: 04/22/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MONTE PHILLIPS RDO | | |CHARLEY HAUGHNEY EO | +------------------------------------------------+STUART RUBIN, AEOD FEMA | |NRC NOTIFIED BY: MOHS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. ARMY EUROPE (USAREUR), ROCK ISLAND, ILLINOIS, REPORTED THAT | | SEVERAL THOUSAND (2,184) M43A1 CHEMICAL AGENT DETECTORS (CADs), AM-241, | | 250 MICROCURIES EACH AND 319 CHEMICAL AGENT MONITORS (CAMs), Ni-63, | | 10 MILLICURIES EACH ARE MISSING IN EUROPE. THE M43A1 CADs WITH | | 250 MICROCURIES EACH OF AM-241 ARE GREATER THAN THE LIMITS FOR REPORTING | | (1,000 TIMES APPENDIX C WHICH IS EQUIVALENT TO 1 MICROCURIE). THE 365 CAMs | | WITH 10 MILLICURIES EACH OF Ni-63 ARE GREATER THAN THE LIMITS FOR REPORTING | | (1,000 TIMES APPENDIX C WHICH IS EQUIVALENT TO 0.1 CURIE). THESE ARE | | APPARENT LOSSES (SINCE 1989) BECAUSE THE LICENSEE IS STILL WORKING ON | | IMPROVEMENTS OF THE ACCOUNTABILITY FOR THESE ITEMS. | | | | REFER TO THE HOO LOG FOR A CONTACT TELEPHONE NUMBER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32201 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/22/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 19:48 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/22/97 | +------------------------------------------------+EVENT TIME: 19:06[EDT]| |NRC NOTIFIED BY: MUSGROVE |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 55 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 2 REACTOR SCRAM AND EMERGENCY CORE COOLING SYSTEM INJECTION FOLLOWING | | A MAIN TURBINE TRIP. | | | | UNIT 2 HAD A TURBINE TRIP DUE TO LOW CONDENSER VACUUM WHICH WAS THE RESULT | | OF A MALFUNCTION OF THE "B" AIR EJECTOR. THE TURBINE TRIP CAUSED THE | | REACTOR SCRAM FROM 55% POWER. DURING THE SCRAM, THE "A" REACTOR FEEDWATER | | PUMP ALSO TRIPPED ON LOW CONDENSER VACUUM AND REACTOR WATER LEVEL DECREASED | | TO -45 INCHES. THE HIGH PRESSURE COOLANT INJECTION (HPCI) AND REACTOR CORE | | ISOLATION COOLING (RCIC) SYSTEMS AUTOMATICALLY STARTED. THERE ARE | | INDICATIONS THAT HPCI INJECTED INTO THE REACTOR VESSEL, BUT THE AMOUNT OF | | INJECTION IS UNKNOWN AT THIS TIME. THE HPCI AND RCIC SYSTEMS WERE SECURED | | WITHIN APPROXIMATELY 2 TO 3 MINUTES, AND THE "B" REACTOR FEEDWATER PUMP WAS | | USED TO RECOVER WATER LEVEL TO +60 INCHES. (NORMAL LEVEL IS +32 TO +42 | | INCHES.) ALL CONTROL RODS FULLY INSERTED, BUT ONE CONTROL ROD (#30-35) | | BOUNCED AND CAME TO REST AT POSITION "02". NONE OF THE SAFETY/ RELIEF | | VALVES OPENED. EMERGENCY OPERATING PROCEDURES WERE ENTERED FOR SEVERAL | | MINUTES (BASED ON LOW REACTOR VESSEL WATER LEVEL) UNTIL LEVEL WAS BACK TO | | NORMAL. THERE WERE NO OTHER ABNORMAL CONDITIONS NOTED. GROUP 2 AND GROUP | | 5 ISOLATIONS ALSO OCCURRED. ALL SAFETY SYSTEMS ARE OPERABLE. THE LICENSEE | | IS STILL INVESTIGATING THE ROOT CAUSE OF THE EVENT. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 04/22/97 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 20:22 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 04/22/97 | +------------------------------------------------+EVENT TIME: 16:54[EDT]| |NRC NOTIFIED BY: PROPER |LAST UPDATE DATE: 04/22/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FROM 100% POWER IN ANTICIPATION OF A MAIN TURBINE TRIP | | DUE TO AN ELECTROHYDRAULIC CONTROL (EHC) SYSTEM OIL LEAK | | | | THE MANUAL REACTOR TRIP WAS INITIATED IN ANTICIPATION OF A MAIN TURBINE | | TRIP DUE TO AN EHC SYSTEM OIL LEAK. THE OIL LEAK APPEARED TO BE COMING | | FROM A BLOWN O-RING ON THE SHUTDOWN SERVO MECHANISM TO THE MAIN TURBINE | | INTERCEPT VALVES. ALL CONTROL RODS FULLY INSERTED, NO POWER-OPERATED RELIEF | | VALVES OR CODE SAFETY VALVES LIFTED, AND NO EMERGENCY CORE COOLING SYSTEM | | INJECTIONS OCCURRED. THERE WAS, HOWEVER, A PROBLEM WITH TWO OF THREE MAIN | | FEEDWATER REGULATING VALVES NOT FULLY CLOSING AND WITH THE "B" AND "C" MAIN | | FEEDWATER PUMPS NOT TRIPPING. THE PUMPS WERE MANUALLY TRIPPED. THE | | LICENSEE PLANS TO INVESTIGATE THE CAUSE OF THESE TWO MALFUNCTIONS. | | | | THE LICENSEE NOTIFIED STATE OFFICIALS AND THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+