U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/07/97 - 04/08/97 ** EVENT NUMBERS ** 31943 31947 32092 32093 32094 32095 32096 32097 32098 32099 32100 32101 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31943 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/12/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:23 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/12/97 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: JAMES BAUER |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GRATINGS IN THE EMERGENCY GAS TURBINE GENERATOR ENGINE CUBICLE ARE NOT | | SEISMICALLY RESTRAINED AND COULD CAUSE ENGINE FAILURE. THE GRATINGS HAVE | | BEEN REMOVED. | | | | THE LICENSEE INFORMED THE STATE AND LOCAL GOVERNMENTS AND THE NRC RESIDENT | | INSPECTOR. | | | | * * * 1554 APRIL 7, 1997, UPDATE FROM STARR RECEIVED BY JOLLIFFE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED UPON A MORE | | DETAILED REVIEW OF THE AS-FOUND CONDITION. TECHNICAL SPECIFICATION 3.5.F, | | MINIMUM CORE AND CONTAINMENT COOLING SYSTEM AVAILABILITY, PRESCRIBES | | LIMITED CONDITIONS OF PLANT OPERATION WHEN THE GAS TURBINE (ONE OF THE | | SOURCES OF EMERGENCY POWER) IS PERMITTED TO BE INOPERABLE. ANALYSIS | | INDICATES THAT THE APPLIED FORCE RESULTS IN A TENSILE STRESS LESS THAN THE | | ALLOWABLE STRESS. AS A RESULT, THE LICENSEE BELIEVES THAT THE POSTULATED | | FAILURE OF THE WIRE AND THE CONSEQUENTIAL DISPLACEMENT OF THE GRATING INTO | | THE INSTRUMENT COULD NOT HAVE OCCURRED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE R1DO (NOGGLE) WAS | | NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31947 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/13/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/13/97 | +------------------------------------------------+EVENT TIME: 14:55[EST]| |NRC NOTIFIED BY: JAMES BAUER |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A REACTOR BUILDING VENTILATION ISOLATION DUE TO LOSS OF | | THE 'B' REACTOR PROTECTION SYSTEM (RPS) MOTOR-GENERATOR (MG) SET. | | | | THE CONTROL ROOM RECEIVED NUMEROUS ALARMS WHICH, UPON INVESTIGATION, | | REVEALED THAT THE 'B' RPS MG SET HAD TRIPPED. OPERATORS REPORTED THAT THE | | ELECTRICAL PROTECTION ASSEMBLIES ASSOCIATED WITH THE RPS MG SET WERE | | TRIPPED. THESE DEVICES REMOVED THE 'B' RPS MG SET FROM ITS ASSOCIATED BUS; | | HOWEVER, THE MG SET OUTPUT BREAKER HAD FAILED TO TRIP AS DESIGNED. | | OPERATORS DEENERGIZED THE 'B' RPS MG SET BY OPENING THE SUPPLY BREAKER AND | | THEN THE OUTPUT BREAKER. AN ACRID ODOR WAS NOTICED AROUND THE VICINITY OF | | THE MG SET. THE 'B' RPS MG SET IS CURRENTLY TAGGED OUT WITH EFFORTS | | UNDERWAY TO RESTORE THE ALTERNATE POWER SOURCE, i.e., INSTRUMENT AND | | REACTOR PROTECTION TRANSFORMER, WHICH WAS REMOVED FROM SERVICE FOR | | MAINTENANCE. THE LICENSEE DOES NOT PLAN TO RESTORE POWER TO THE 'B' RPS | | BUS UNTIL TROUBLESHOOTING IS COMPLETED. LOSS OF THE 'B' RPS BUS RESULTS IN | | AN ACTUATION OF THE STANDBY GAS TREATMENT SYSTEM (SBGTS), REACTOR BUILDING | | VENTILATION ISOLATION, AND DEENERGIZATION OF VARIOUS INSTRUMENTS INCLUDING | | THE 'B' POWER RANGE NEUTRON MONITORING SYSTEM. AT THE TIME OF THE EVENT, | | THE SBGTS WAS REMOVED FROM SERVICE AND NOT REQUIRED. THE REACTOR BUILDING | | VENTILATION SYSTEM DID ISOLATE AS REQUIRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND SENT A RADIO PAGE TO | | INFORM BOTH STATE AND LOCAL AGENCIES. | | | | * * * 1556 APRIL 7, 1997, UPDATE FROM SEMANCIK RECEIVED BY JOLLIFFE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION FOR THE FOLLOWING | | REASONS. THE LICENSEE DETERMINED THAT THE REPORTED ACTUATION RESULTED FROM | | AN INVALID SIGNAL. THE LICENSEE ALSO DETERMINED THAT THE STEAM TUNNEL | | VENTILATION CONSTITUTES AN EQUIVALENT SYSTEM TO THE REACTOR BUILDING | | VENTILATION SYSTEM. THEREFORE, ONLY THE REACTOR BUILDING VENTILATION | | SYSTEM WAS INVOLVED IN THE EVENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE R1DO (NOGGLE) WAS | | NOTIFIED BY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32092 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:32 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 03:39[CDT]| |NRC NOTIFIED BY: YURKOVICH |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO IMPLEMENT COMPENSATORY MEASURES WITHIN TEN MINUTES FOR A | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO ALARM FUNCTIONS | | | | AT 0339 CDT, THE LICENSEE DISCOVERED THAT COMPENSATORY MEASURES FOR A | | SAFEGUARDS SYSTEM DEGRADATION RELATED TO ALARM FUNCTIONS HAD NOT BEEN | | IMPLEMENTED WITHIN TEN MINUTES AS REQUIRED BY THE STATION SECURITY PLAN. | | COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE'S | | INVESTIGATION IS ONGOING. (REFER TO THE HOO LOG FOR ADDITIONAL | | INFORMATION.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32093 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 12:14 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 11:25[EDT]| |NRC NOTIFIED BY: DICK CZARNECKI |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - DISCOVERY OF SUSPECTED CONTRABAND INSIDE PROTECTED AREA - | | | | A SUSPECTED DRUG SMOKING DEVICE WAS FOUND IN A PORTABLE TOILET INSIDE THE | | PROTECTED AREA. THE LICENSEE HAS TAKEN COMPENSATORY MEASURES AND IS | | CONTINUING ITS INVESTIGATION. (REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32094 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 04/07/97 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 13:32 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 10:35[CDT]| |NRC NOTIFIED BY: BOB BROWN |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FITNESS-FOR-DUTY EVENT - | | | | THE ODOR OF ALCOHOL WAS DETECTED ON THE BREATH OF A CONTRACTOR SUPERVISOR | | BY A LICENSEE RADIATION PROTECTION SUPERVISOR. THE CONTRACTOR SUPERVISOR | | TESTED POSITIVE FOR ALCOHOL DURING A SUBSEQUENT FOR-CAUSE TEST. THE | | LICENSEE WITHDREW THE CONTRACTOR SUPERVISOR'S UNESCORTED PLANT ACCESS | | AUTHORIZATION AND REFERRED THE CONTRACTOR SUPERVISOR TO HIS COMPANY FOR | | FURTHER DISPOSITION. THE LICENSEE IS REVIEWING THE CONTRACTOR SUPERVISOR'S | | RECENT WORK ACTIVITIES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32095 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: HEWLETT PACKARD CO, WILMINGTON, DE |NOTIFICATION DATE: 04/07/97 | | CITY: WILMINGTON REGION: 1 |NOTIFICATION TIME: 14:54 [ET]| | COUNTY: STATE: DE |EVENT DATE: 03/24/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 10:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/07/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES NOGGLE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ALAN KAMYAB, RSO | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISSING 15-MILLICURIE NI-63 SOURCE FROM HEWLETT PACKARD COMPANY LOCATED IN | | WILMINGTON, DELAWARE | | | | AT 1000 ON 03/24/97, ALAN KAMYAB, RADIATION SAFETY OFFICER, DISCOVERED | | THAT A 15-MILLICURIE NI-63 RADIOACTIVE SOURCE (SERIAL #K4022), WHICH WAS | | SEALED IN A PLASTIC CONTAINER (1.25 INCHES BY 1 INCH BY 0.75 INCH) AND USED | | IN AN ELECTRON CAPTURE DETECTOR, WAS MISSING FROM A SAFE AT THE HEWLETT | | PACKARD COMPANY FACILITY IN WILMINGTON, DELAWARE. THIS FACILITY | | MANUFACTURES GAS CHROMATOGRAPHS WHICH ARE USED TO CHEMICALLY ANALYZE | | COMPOUNDS. HEWLETT PACKARD RECORDS INDICATE THAT THE SOURCE HAD BEEN | | RECEIVED FROM AMERSHAM IN GREAT BRITAIN ON 03/05/97. THE LICENSEE HAS | | INTERVIEWED ALL APPROPRIATE COMPANY PERSONNEL. THE LICENSEE HAS ALSO | | SEARCHED THE FACILITY BUT HAS NOT FOUND THE MISSING SOURCE. | | | | THE LICENSEE IS CONTINUING ITS INVESTIGATION OF THIS MISSING SOURCE. | | | | THE LICENSEE PLANS TO SUBMIT A WRITTEN REPORT TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE HAS NOTIFIED THE NRC REGION 1 OFFICE (JOHN McGRATH) AND THE | | STATE OF DELAWARE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32096 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 16:13 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 15:50[EDT]| |NRC NOTIFIED BY: PAUL FREEMAN |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE 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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION INVOLVING THE POTENTIAL FOR A FUEL | | HANDLING ACCIDENT INSIDE CONTAINMENT WITH RADIOLOGICAL CONSEQUENCES TO | | CONTROL ROOM PERSONNEL MORE SEVERE THAN CURRENTLY DESCRIBED IN THE UPDATED | | FINAL SAFETY ANALYSIS REPORT (UFSAR). | | | | THE FUEL HANDLING ACCIDENT ANALYSIS DESCRIBED IN UFSAR SECTION 15.7.4 | | DESCRIBES THE MOST LIMITING FUEL HANDLING ACCIDENT AS THE DROP OF A SPENT | | FUEL ASSEMBLY INSIDE CONTAINMENT RESULTING IN THE RUPTURE OF ALL CLADDING | | OF ALL FUEL RODS IN THE ASSEMBLY. THE CONTAINMENT PERSONNEL AIR LOCK DOORS | | AND A STEAM GENERATOR SLUDGE LANCE PENETRATION ARE ASSUMED TO BE OPEN | | DURING THIS ACCIDENT WITH ALL RADIOACTIVITY FROM THE RUPTURED FUEL ASSEMBLY | | BEING RELEASED OVER A 2-HOUR PERIOD. | | | | THE CURRENT UFSAR ASSUMPTION IS THAT THE ASSEMBLY IS DROPPED 10 FEET FROM | | THE CONTAINMENT AIR PURGE (CAP) SYSTEM EXHAUST DUCT. THE TRANSPORT TIME | | FOR THE ACTIVITY RELEASED IS GREATER THAN THE TIME REQUIRED FOR ISOLATION | | OF THE 36-INCH BUTTERFLY VALVES IN THE SYSTEM; THEREFORE, NO RADIOACTIVITY | | IS ASSUMED TO BE RELEASED BY THIS MECHANISM. | | | | THE LICENSEE RECENTLY IDENTIFIED THE POTENTIAL FOR A DROPPED FUEL ASSEMBLY | | IN A REFUELING CAVITY LOCATION ADJACENT TO A CAP SYSTEM EXHAUST DUCT THAT | | MAY YIELD MORE SEVERE CONSEQUENCES THAN THE DROP OF AN ASSEMBLY IN THE | | CENTER OF THE REFUELING CAVITY APPROXIMATELY 10 FEET FROM THE CAP EXHAUST | | DUCT. A DROPPED FUEL ASSEMBLY ADJACENT TO THE CAP SYSTEM EXHAUST DUCT AND | | OPERATING EXHAUST FAN WOULD ESSENTIALLY RESULT IN THE RADIOACTIVITY BEING | | RELEASED PRIOR TO THE AUTOMATIC ISOLATION OF THE 36-INCH BUTTERFLY VALVES. | | | | THE LICENSEE HAS CONCLUDED THAT THE RADIOLOGICAL CONSEQUENCES TO CONTROL | | ROOM PERSONNEL ARE MORE SEVERE THAN CURRENTLY ANALYZED IN UFSAR SECTION | | 15.7.4. THE UFSAR CURRENTLY SPECIFIES THE CONTAINMENT FUEL HANDLING | | ACCIDENT CONTROL ROOM THYROID DOSE AS 6.7 REM AND THE WHOLE BODY DOSE AS | | 0.3 REM. LICENSEE ENGINEERING PERSONNEL ESTIMATE THAT UNDER THE NEW | | SCENARIO, THE CONTROL ROOM THYROID DOSE WOULD APPROACH 100 REM AND THAT THE | | WHOLE BODY DOSE WOULD APPROACH THE GENERAL DESIGN CRITERION 19 LIMIT OF 5 | | REM. THE EXCLUSION AREA BOUNDARY THYROID AND WHOLE BODY DOSES ARE | | ESTIMATED TO INCREASE SLIGHTLY BUT WOULD STILL REMAIN WELL WITHIN 10 CFR | | PART 100 LIMITS. | | | | THE LICENSEE IS EVALUATING A DESIGN CHANGE TO BE USED DURING THE UPCOMING | | REFUELING OUTAGE THAT WOULD RELOCATE THE CAP SYSTEM EXHAUST DUCT INLET | | LOCATION SUCH THAT DURING A POSTULATED FUEL ASSEMBLY DROP ACCIDENT, THE CAP | | SYSTEM BUTTERFLY VALVES WOULD AUTOMATICALLY ISOLATE THE SYSTEM PRIOR TO THE | | RELEASE OF RADIOACTIVITY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32097 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/07/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:35 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/07/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:50[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/07/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN MADERA RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+BILL BRACH NMSS | |NRC NOTIFIED BY: STEVE MAY |STUART RUBIN, IRD AEOD | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE TOP ENRICHMENT IN THE CASCADE EXCEEDED THE AUTHORIZED | | MAXIMUM WEIGHT PERCENT U-235 | | | | AFTER REVIEWING THE CALCULATIONS FROM THE MONITORING OF GASEOUS DIFFUSION | | CASCADE OPERATIONS OF THE X-326 FACILITY, PORTSMOUTH PERSONNEL CONFIRMED | | THAT THE TOP ENRICHMENT IN THE CASCADE REACHED 20.7 WEIGHT PERCENT U-235, | | WHICH EXCEEDED THE AUTHORIZED MAXIMUM OF 20.0 WEIGHT PERCENT U-235. THE | | TOTAL QUANTITY OF MATERIAL ABOVE 20.0 WEIGHT PERCENT U-235 IS ESTIMATED TO | | BE 800 MILLIGRAMS OF U-235 IN THE FORM OF GASEOUS UF6 (REFERENCE | | APPLICATION FNMCP 1.2). THERE WAS NO LOSS OF CONTROL OF NUCLEAR MATERIAL | | DURING THIS EVENT. | | | | THIS EVENT IS REPORTED AS A 1-HOUR REPORT. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32098 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 04/07/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 17:25 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 16:30[EDT]| |NRC NOTIFIED BY: DAN CIFONELLI |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE 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 +------------------------------------------------------------------------------+ | DISCOVERY THAT THE CONTROL CIRCUITS FOR THE EMERGENCY DIESEL GENERATOR | | COOLING WATER OUTLET VALVES DO NOT HAVE THE REQUIRED SEPARATION OR | | PROTECTION TO MEET UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) COMMITMENTS | | | | DURING A REVIEW OF AN OPERATING EXPERIENCE REPORT ASSOCIATED WITH | | APPENDIX R CONTROL ROOM FIRES AT AN ENTERGY FACILITY, NINE MILE POINT | | DESIGN ENGINEERING PERSONNEL DETERMINED THAT A DESIGN PROBLEM AT NINE | | MILE POINT UNIT 2 EXISTS WITH THE CONTROL CIRCUITS FOR EMERGENCY DIESEL | | GENERATOR COOLING WATER OUTLET VALVES 2SWP*MOV-66A AND B. THE CONTROL | | CIRCUITS DO NOT HAVE THE REQUIRED SEGREGATION OR PROTECTION TO MEET THE | | DESIGN COMMITMENTS IN UNIT 2 UFSAR, APPENDIX 9B, SECTION 9B.8.2.3. | | | | AT 1630, THE LICENSEE DECLARED THE ASSOCIATED CONTROL CHANNELS OF THE | | REMOTE SHUTDOWN SYSTEM INOPERABLE. TECHNICAL SPECIFICATION 3.3.7.4, ACTION | | b, REQUIRES THE LICENSEE TO RESTORE THESE CHANNELS TO OPERABLE STATUS | | WITHIN 7 DAYS OR TO PLACE UNIT 2 IN AT LEAST A HOT SHUTDOWN CONDITION | | WITHIN THE FOLLOWING 12 HOURS. | | | | LICENSEE ENGINEERING PERSONNEL ARE PREPARING THE NECESSARY CONTROL CIRCUIT | | DESIGN CHANGES TO PROVIDE COMPLIANCE WITH THE UFSAR. THE LICENSEE EXPECTS | | TO IMPLEMENT THESE DESIGN CHANGES ON 04/08/97. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32099 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 18:32 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 15:10[CDT]| |NRC NOTIFIED BY: DAVE SCHMIDT |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 76 POWER OPERATION | 76 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A SIGNIFICANT REFRIGERANT LEAK NEAR A CONTROL ROOM HEATING | | VENTILATION AND AIR CONDITIONING (HVAC) SYSTEM COMPRESSOR DISCHARGE MUFFLER | | | | CONTROL ROOM OPERATORS STARTED THE TRAIN 'B' CONTROL ROOM HVAC SYSTEM IN | | ORDER TO ADD REFRIGERANT TO THE SYSTEM WHEN A SIGNIFICANT REFRIGERANT LEAK | | NEAR THE COMPRESSOR DISCHARGE MUFFLER WAS DETECTED. THE LICENSEE DECLARED | | THE SYSTEM INOPERABLE. THE LICENSEE CONSIDERS THIS SYSTEM A SINGLE TRAIN | | ACCIDENT MITIGATION SYSTEM. | | | | QUAD CITIES UNITS 1 AND 2 HAVE A COMMON CONTROL ROOM. TECHNICAL | | SPECIFICATION 3.8.D.1.b REQUIRES THE LICENSEE TO RESTORE THIS SYSTEM TO | | OPERABLE STATUS WITHIN 30 DAYS OR TO PLACE UNIT 1 IN AT LEAST A HOT | | SHUTDOWN CONDITION WITHIN 12 HOURS AND A COLD SHUTDOWN CONDITION WITHIN THE | | FOLLOWING 24 HOURS. UNIT 2 IS DEFUELED IN A REFUELING OUTAGE. | | | | THE LICENSEE PLANS TO REPAIR THE SYSTEM WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32100 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 18:48 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 15:11[EDT]| |NRC NOTIFIED BY: MIKE MOHNEY |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE, R1 RDO | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION |MILTON SHYMLOCK, R2 RDO | | |JOHN MADERA, R3 RDO | | |WILLIAM JOHNSON, R4 RDO | | |VERN HODGE, RVIB NRR | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 HAS OBSERVED AN INCREASING NUMBER OF STRUTHERS-DUNN 219 NE | | SERIES RELAY FAILURES. | | | | THESE RELAYS ARE INSTALLED IN A VARIETY OF SAFETY-RELATED APPLICATIONS. THE | | FAILURE MECHANISM IS THE THERMAL DEGRADATION OF THE RELAY BEARING PAD | | MATERIAL (A 1-MILLIMETER THICK STRIP OF MAGNETIC VINYL PLASTIC MATERIAL | | LOCATED NEAR THE RELAY COIL) DUE TO EXPOSURE TO HIGH TEMPERATURES | | (APPROXIMATELY 175øF) WHEN THE COIL IS ENERGIZED. THIS CAUSES LOSS OF THE | | ALIGNMENT BETWEEN THE ARMATURE AND COIL AND CAUSES RAPID MOTION | | (CHATTERING) OF ARMATURE AND CONTACTS. THE RELAY CAN FAIL WITH AN OPEN | | CONTACT, A CLOSED CONTACT, OR A SHORTED COIL. THIS FAILURE MECHANISM HAS | | BEEN OBSERVED ONLY FOR RELAYS WITH AC COILS. | | | | THE FAILURE MECHANISM AND FAILURE MODES HAVE BEEN CONFIRMED WITH THE | | MANUFACTURER, STRUTHERS-DUNN. PER THE MANUFACTURER, MAGNETIC VINYL PLASTIC | | IS NOT THE PROPER BEARING PAD MATERIAL. SILICON RUBBER, WHICH HAS A HIGH | | RESISTANCE TO HEAT DEGRADATION, IS THE PROPER BEARING PAD MATERIAL. | | | | THE LICENSEE HAS REASONABLE ASSURANCE OF CONTINUED OPERABILITY BASED ON THE | | FOLLOWING: | | | | - PANEL WALKDOWNS ARE PERFORMED WEEKLY TO LISTEN FOR BUZZING RELAYS AND | | TAKE IMMEDIATE ACTION IF ANY BUZZING IS DETECTED. | | - RELAY BUZZING IS AN INDICATION WHICH PRECEDES RELAY FAILURE. ADEQUATE | | TIME EXISTS BETWEEN THE START OF BUZZING AND EVENTUAL RELAY FAILURE; | | THE FAILURE IS NOT IMMEDIATE. | | - THERE ARE CURRENTLY NO INDICATIONS OF IMMINENT FAILURE OBSERVED FOR ANY | | OF THE AFFECTED RELAYS. | | - THE RELAYS ARE SCHEDULED FOR REPLACEMENT BEFORE THE END OF THEIR | | QUALIFIED OR CALCULATED SERVICE LIFE. | | | | ALL SAFETY-RELATED SYSTEMS ARE OPERABLE. | | | | IF UNDETECTED, THIS CONDITION COULD HAVE PREVENTED THE FULFILLMENT OF A | | SAFETY FUNCTION. THEREFORE, THIS REPORT IS BEING MADE IN ACCORDANCE WITH | | 10 CFR 50.72(b)(2)(iii)(D). THIS REPORT IS ALSO BEING MADE PURSUANT TO THE | | REQUIREMENTS OF 10 CFR PART 21. | | | | THE LICENSEE PLANS TO SUBMIT A LICENSEE EVENT REPORT ON THIS EVENT. | | | | THE LICENSEE PLANS TO NOTIFY LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32101 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 04/07/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 19:53 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 04/07/97 | +------------------------------------------------+EVENT TIME: 18:10[CDT]| |NRC NOTIFIED BY: DAVE SCHMIDT |LAST UPDATE DATE: 04/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 76 POWER OPERATION | 74 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO LOW STANDBY LIQUID CONTROL | | SYSTEM PUMP FLOW DURING TESTING | | | | BOTH POSITIVE DISPLACEMENT STANDBY LIQUID CONTROL SYSTEM PUMPS FAILED | | ROUTINE TECHNICAL SPECIFICATION IN-SERVICE TESTS DUE TO LOW FLOW. AS A | | RESULT, THE LICENSEE DECLARED BOTH SUBSYSTEMS OF THE STANDBY LIQUID CONTROL | | SYSTEM (EMERGENCY BORON INJECTION SYSTEM) TO BE INOPERABLE. | | | | TECHNICAL SPECIFICATION 3.4.A.1.b REQUIRES THE LICENSEE TO RESTORE AT LEAST | | 1 SUBSYSTEM TO OPERABLE STATUS WITHIN 8 HOURS OR TO PLACE UNIT 1 IN AT | | LEAST A HOT SHUTDOWN CONDITION WITHIN 12 HOURS. | | | | CONTROL ROOM OPERATORS BEGAN SHUTTING DOWN UNIT 1 AT 1820 CDT, AND POWER | | WAS AT 74% AT THE TIME OF THIS NOTIFICATION. THE LICENSEE IS CURRENTLY | | ATTEMPTING TO RESTORE AT LEAST ONE SUBSYSTEM TO OPERABLE STATUS PRIOR TO | | COMPLETION OF THE UNIT 1 SHUTDOWN. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+