U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/08/96 - 08/09/96 ** EVENT NUMBERS ** 30737 30786 30847 30848 30849 30850 30851 30852 30853 30854 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30737 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 07/11/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 14:49 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/11/96 | +------------------------------------------------+EVENT TIME: 14:03[EDT]| |NRC NOTIFIED BY: DICK SMEDLEY |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM CREED 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 +------------------------------------------------------------------------------+ | DISCOVERY THAT APPROXIMATELY 900 CABLES IN THE ELECTRICAL DISTRIBUTION | | SYSTEM DO NOT MEET THE THERMAL SIZING DESIGN BASIS | | | | WHILE COMPARING THE FINAL SAFETY ANALYSIS REPORT (FSAR) TO AS-BUILT PLANT | | CONDITIONS, IT WAS DETERMINED THAT A NUMBER OF CABLES DO NOT MEET THE | | THERMAL SIZING DESIGN BASIS STATED IN SECTION 8.5.2 OF THE FSAR. THE FSAR | | STATES THAT THE AMPACITY MAY BE ADJUSTED BASED ON ACTUAL CONDITIONS. | | HOWEVER, NOT ALL CABLES HAVE BEEN SPECIFICALLY ANALYZED TO PROVIDE FOR THIS | | ADJUSTMENT. THEREFORE, THEY MAY BE OUTSIDE THE DESIGN BASIS, AND | | SPECIFICALLY, THEIR DESIGN LIFE MAY BE SHORTENED. THE LICENSEE HAS | | CONSERVATIVELY DECIDED TO REPORT THIS ISSUE WHILE IT CONTINUES TO ANALYZE | | THE SITUATION. | | | | THE LICENSEE HAS DETERMINED THAT ALL OF THE CABLES REMAIN OPERABLE SINCE | | THE INTERNATIONAL CABLE ENGINEERS ASSOCIATION (ICEA) VALUES, WHICH ARE SET | | TO PREVENT OVERHEATING RESULTING IN INSULATION DEGRADATION AND INCREASED | | AGING, ASSUME CONSERVATIVE CONDITIONS. IN OTHER WORDS, ICEA VALUES ASSUME | | THAT ALL CABLES IN A GIVEN TRAY ARE POWER CABLES THAT ARE ENERGIZED | | CARRYING MAXIMUM CURRENT ALL OF THE TIME. THESE CONDITIONS DO NOT EXIST IN | | THE UNANALYZED TRAYS DURING OPERATION OR IN ATTAINING AND MAINTAINING SAFE | | SHUTDOWN. THERE ARE APPROXIMATELY 900 CABLES IN THE ELECTRICAL | | DISTRIBUTION SYSTEM WHICH ARE IN THIS CONDITION, AND THEY ARE LOCATED IN | | VARIOUS AREAS THROUGHOUT THE PLANT. THE UNIT HAS NOT EXPERIENCED ANY | | FAILURES AS A RESULT OF INSULATION DEGRADATION. BECAUSE THE LICENSEE HAS | | DETERMINED THAT ALL OF THE CABLES REMAIN OPERABLE, TECHNICAL SPECIFICATION | | LIMITING CONDITIONS FOR OPERATION HAVE NOT BEEN ENTERED. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | ***RETRACTION @ 1855 EDT 08/08/96 BY R VINCENT TAKEN BY MACKINNON*** | | BASED ON FURTHER EVALUATION AND COMPLETION OF A 10 CFR 50.59 EVALUATION, IT | | HAS BEEN CONCLUDED THAT THE CONDITION IS AN ANALYSIS DOCUMENTATION ISSUE | | RATHER THAN A FUNDAMENTAL DESIGN FLAW. THEREFORE THIS CONDITION IS NOT | | OUTSIDE THE DESIGN BASIS OF THE PLANT AND THAT THE ORIGINAL NOTIFICATION IS | | HEREBY RETRACTED. RI NOTIFIED & R3DO (BRUCE BURGESS) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30786 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/25/96 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/25/96 | +------------------------------------------------+EVENT TIME: 18:27[EDT]| |NRC NOTIFIED BY: RICK HENRIQUEZ |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MCFADDEN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |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 +------------------------------------------------------------------------------+ | SAFETY CLASS PIPING COULD EXCEED ITS DESIGN PRESSURE UNDER LOCA CONDITIONS | | | | PIPING IN SIX DIFFERENT SYSTEMS WHICH PENETRATE CONTAINMENT HAVE THE | | POTENTIAL TO CAUSE A LOSS OF CONTAINMENT INTEGRITY UNDER LOCA CONDITIONS. | | EACH OF THESE PIPES HAS THE POTENTIAL TO BE WATER FILLED AND EACH HAS NO | | PRESSURE RELIEF. UNDER LOCA CONDITIONS, THE TEMPERATURE INCREASE IN THE | | CONTAINMENT WOULD RAISE THE TEMPERATURE OF THE WATER IN THESE PIPES, AND | | THEREBY INCREASE THE PRESSURE IN THE PIPING, POTENTIALLY OVER PRESSURIZING | | THE PIPING. THE SYSTEMS INVOLVED ARE: (1) REACTOR BUILDING CLOSED COOLING | | WATER, (2) RHR SHUTDOWN COOLING LINE, (3) MAIN STEAM LINE DRAINS, | | (4) CONTAINMENT FLOOR DRAINS, (5) CONTAINMENT EQUIPMENT DRAINS, AND | | (6) RECIRC SAMPLE LINE. | | | | THE LICENSEE CONSIDERS THESE SYSTEMS OPERABLE BASED ON DISCUSSIONS BETWEEN | | GE AND THEIR ENGINEERING STAFF. VALVE LEAKAGE SHOULD LIMIT THE PRESSURE | | RISE IN THE AFFECTED PIPING TO LESS THAN THE DUCTILE FAILURE LIMIT. LONG | | TERM CORRECTIVE ACTION IS STILL UNDER DEVELOPMENT. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE @ 1520 EDT 08/08/96 BY A. WISNIEWSKI TAKEN BY MACKINNON*** | | | | TODAY, AT 1455 EDT, CONTROL ROOM WAS INFORMED THAT THIS EVENT SHOULD HAVE | | BEEN REPORTED AS A ONE HOUR NON-EMERGENCY OUTSIDE OF DESIGN BASIS EVENT - | | [10CFR 50.72 (b)(1)(ii)(B)]. GENERAL ELECTRIC INFORMED THE LICENSEE THAT | | THE PIPES MENTIONED ABOVE WILL NOT FAIL UNDER A DESIGN BASIS ACCIDENT. | | LICENSEE WILL NOTIFY THE STATE OF VERMONT OF THIS UPDATE. R1DO (JIM NOGGLE) | | NOTIFIED. THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS UPDATE BY THE | | LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30847 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 08/08/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 03:11 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 08/08/96 | +------------------------------------------------+EVENT TIME: 01:20[CDT]| |NRC NOTIFIED BY: JAY HOUSTON |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CONTRACTOR WAS LEFT UNESCORTED IN THE CONTRACTOR'S LUNCH ROOM FOR | | APPROXIMATELY ONE HOUR. THE INDIVIDUAL WAS ESCORTED OFF SITE. THE | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30848 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 08/08/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 14:03 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/07/96 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: ARMANDO |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JMI NOGGLE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DID NOT SUBMIT A LICENSE AMENDMENT WHEN THEIR OPERATING SHIFTS | | SWITCHED FROM 8 HOUR SHIFTS TO 12 HOUR SHIFTS. | | | | DURING A REVIEW OF THE LICENSEE REQUIREMENTS, PSE&G DISCOVERED A DEVIATION | | FROM THE LICENSE CONDITIONS CONCERNING THE SHIFT SCHEDULES. THE SALEM UNIT | | 2 LICENSE, CONDITION 2.C.(24).a, REQUIRED THAT PSE&G ESTABLISH AN 8-HOUR | | OPERATING SHIFT TO COMPLY WITH NUREG 0737, ITEM I.A.1.3 BY JUNE 3, 1981. | | THIS CONDITION WAS SATISFIED AS REQUIRED, HOWEVER, IN 1992, PSE&G | | TRANSITIONED FROM AN 8-HOUR SHIFT TO A 12-HOUR OPERATING SHIFT. THIS WAS | | ACCOMPLISHED WITHOUT THE REQUIRED LICENSE AMENDMENT BEING PROCESSED TO | | REMOVE THIS RESTRICTION FROM THE OPERATING LICENSE. SALEM UNIT 1 DOES NOT | | HAVE THE SAME RESTRICTION. LICENSEE WILL NOTIFY THE NRC REGIONAL | | ADMINISTRATOR OR HIS DESIGNEE NO LATER THAN THE FIRST WORKING DAY FOLLOWING | | THE VIOLATION EITHER BY A FACSIMILE OR A PHONE CALL. | | LICENSE WILL SUBMIT A LICENSE AMENDMENT TO CORRECT THIS PROBLEM. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30849 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 08/08/96 | |UNIT: [1] [2] [ ] STATE: GA |NOTIFICATION TIME: 14:03 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/08/96 | +------------------------------------------------+EVENT TIME: 11:05[EDT]| |NRC NOTIFIED BY: JOHN HOPKINS |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILT SHYMLOCK RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING A ROUTINE SURVEILLANCE ON THE UNIT 2 POST ACCIDENT SAMPLE SYSTEM | | (PASS), FUEL HANDLING BUILDING POST ACCIDENT FILTRATION TRAIN "A" | | AUTOMATICALLY STARTED ON A VALID SIGNAL. | | | | WHILE PERFORMING A ROUTINE SURVEILLANCE ON THE UNIT 2 PASS, RADIATION | | LEVELS INCREASED IN THE FUEL HANDLING BUILDING (FHB) RADIATION MONITORS IN | | UNIT 2. THE SUSPECTED CAUSE OF THE INCREASE IS THE ELEVATED ACTIVITY OF THE | | UNIT 2 REACTOR COOLANT SYSTEM ASSOCIATED WITH SUSPECTED FUEL LEAKS AND THE | | VENTING OF PASS DRAINS TO THE FHB VENTILATION. PRIOR TO THE FHB POST | | ACCIDENT FILTRATION ACTUATION, THE "B" TRAIN FILTRATION UNIT WAS IN | | OPERATION FOR ROUTINE SURVEILLANCE AND THE "A" TRAIN WAS IN STANDBY. THE | | TWO RADIATION MONITORS IN THE UNIT 2 DUCT WORK DETECTED THE INCREASE | | ACTIVITY AND ACTUATED BOTH FILTRATION UNITS. THE "A" TRAIN UNIT AUTO | | STARTED AND THE "B" TRAIN UNIT CONTINUED OPERATION. | | | | PRIOR TO THE PASS ACTIVITIES, THE RADIATION MONITORS WERE READING | | APPROXIMATELY 3E-06ęCi/cc AND THE PEAK READING WAS 5.2E-04ęCi/cc. TRIP | | SETPOINT FOR THESE MONITORS IS 5.19E-04ęCi/cc. THE ACTIVITY IS DECAYING | | NORMALLY. THE PASS SURVEILLANCE WAS TERMINATED AT 1106 EDT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30850 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 08/08/96 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 16:17 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/07/96 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: ARMANDO |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM NOGGLE RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TEN OF 222 REPLACEMENT SUMMATOR AND ISOLATOR MODULES FOR SALEM UNIT 2 (USED | | IN THE REACTOR CONTROL AND PROTECTION SYSTEMS) WERE FOUND TO HAVE | | UNSOLDERED ELECTRICAL CONNECTIONS DURING INSPECTION. | | | | NUS MODEL OCA801 SIGNAL ISOLATOR MODULES AND MODEL MTH801 SIGNAL SUMMATOR | | MODULES ARE BEING INSTALLED AS REPLACEMENT FOR MODULES IN THE REACTOR | | CONTROL AND PROTECTION SYSTEM TO PROVIDE IMPROVED RELIABILITY. DURING BENCH | | TESTING, AN ELECTRICAL CONNECTION WITH NO SOLDER WAS OBSERVED ON A | | REPLACEMENT SUMMATOR MODULE. ALL REPLACEMENT SUMMATOR AND ISOLATOR MODULES | | FOR SALEM UNIT 2 WERE THEN INSPECTED. TEN OF 222 MODULES WERE FOUND TO HAVE | | UNSOLDERED ELECTRICAL CONNECTIONS. ANOTHER SEVEN MODULES WERE FOUND TO HAVE | | INSUFFICIENT SOLDER ON AT LEAST ONE CONNECTION. SOME OF THE DEFECTIVE | | CONNECTIONS WERE COVERED BY HEAT SHRINK INSULATION. | | THE MODULES WERE MANUFACTURED BY NUS, P.O BOX 50736, IDAHO FALLS, ID., | | 83405. ALL REPLACEMENT MODULES FOR SALEM UNIT 2 HAVE BEEN INSPECTED BY THE | | VENDOR AND REPAIRED. ALL REPLACEMENT MODULES FOR SALEM UNIT 1 HAVE BEEN | | RETURNED TO THE VENDOR FOR INSPECTION AND REPAIR. PSE&G IS INVESTIGATING | | THE CAUSE OF THE DEFECT WITH THE VENDOR. RESULTS WILL BE PROVIDED WHEN THE | | INVESTIGATION IS COMPLETED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS PART 21 BY THE LICENSEE. | | | | PART 21 SENT TO VERN HODGE VIA FACSIMILE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30851 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 08/08/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/08/96 | +------------------------------------------------+EVENT TIME: 13:36[CDT]| |NRC NOTIFIED BY: DAVID SHAW |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 96 POWER OPERATION | 96 POWER OPERATION | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE NOTIFIED THE NATIONAL RESPONSE CENTER THAT APPROXIMATELY 5 GALLONS | | OF HYDRAZINE WAS SPILLED INSIDE THEIR TURBINE BUILDING AND APPROXIMATELY 25 | | TO 50 GALLONS OF HYDRAZINE WERE VENTED OUTSIDE THE TURBINE BUILDING. NO ONE | | WAS OVERCOME BY THE FUMES FROM THE HYDRAZINE. | | | | THE LICENSEE DISCOVERED THAT A PORTABLE CHEMICAL ADDITION TANK LOCATED | | INSIDE THE TURBINE BUILDING WAS LEAKING HYDRAZINE FROM ITS SIGHT GLASS. | | APPROXIMATELY 5 GALLONS OF HYDRAZINE LEAKED FROM THE SIGHT GLASS BEFORE THE | | LEAK COULD BE STOPPED. AFTER ISOLATING THE LEAK, THE LICENSEE DISCOVERED | | THAT BETWEEN 25 TO 50 GALLONS OF HYDRAZINE HAD BEEN VENTED THROUGH THE | | CHEMICAL ADDITION TANK RELIEF VALVE OUT OF THE TURBINE BUILDING. THE | | LICENSEE DECLARED A HAZMAT CONDITION IN THE IMMEDIATE AREA AROUND THE SPILL | | AND EXITED THE HAZMAT CONDITION AT 1454 CDT. THE LICENSEE IS NOW IN THE | | PROCESS OF CLEANING UP THE HYDRAZINE. LICENSEE NOTIFIED THE NATIONAL | | RESPONSE CENTER OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 30852 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NUCLEAR FUEL SERVICES INC. |NOTIFICATION DATE: 08/08/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 17:51 [ET]| |COMMENTS: HEU CONVERSION & SCRAP RECOVERY |EVENT DATE: 08/08/96 | | NAVAL REACTOR FUEL CYCLE |EVENT TIME: 09:00[EDT]| | LEU SCRAP RECOVERY |LAST UPDATE DATE: 08/08/96 | | CITY: ERWIN REGION: 2 +-----------------------------+ | COUNTY: UNICOI STATE: TN |PERSON ORGANIZATION| |LICENSE#: SNM-124 AGREEMENT: Y |MILT SHYMLOCK RDO | | DOCKET: 07000143 |JOHN AUSTIN (NMSS) EO | +------------------------------------------------+FRANK CONGEL (IRD) AEOD | |NRC NOTIFIED BY: GILBERT ROSENBERGER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |KBBE 70.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CRITICALITY ALARM SYSTEM FAILED. CRITICALITY CONTROL SYSTEM WAS NOT | | DEGRADED BY THE LOSS OF THE ALARM SYSTEM. NO SPECIAL NUCLEAR MATERIAL (SNM) | | WAS MOVED DURING THE TIME PERIOD THAT THE CRITICALITY ALARM SYSTEM WAS | | INOPERABLE AND NO ONE WAS EXPOSED TO RADIATION/RADIOACTIVE MATERIAL. | | | | AT APPROXIMATELY 0900 EDT ON 08/08/96, THE RADIATION TECHNICIAN SUPERVISOR | | OBSERVED THAT A TROUBLE LIGHT FOR THE CRITICALITY/FIRE ALARM SYSTEM WAS | | ILLUMINATED AT THE REMOTE PANEL IN BUILDING 220, BUT THE WARNING BUZZER WAS | | NOT SOUNDING. HE CONTACTED AN ELECTRONIC TECHNICIAN, WHO WENT TO CHECK THE | | CENTRAL ALARM CONTROL PANEL IN BUILDING 105B. | | | | UPON HIS ARRIVAL, THE ELECTRONIC TECHNICIAN FOUND THE TROUBLE LIGHT | | ILLUMINATED, AND ALSO A MESSAGE THAT INDICATED THAT THE CENTRAL ALARM | | CONTROL UNIT COULD NOT COMMUNICATE WITH EITHER THE INPUT DETECTOR MODULES | | OR WITH THE OUTPUT ALARM MODULES. THE TECHNICIAN ATTEMPTED TO CLEAR THE | | TROUBLE, USING THE NORMAL PROCEDURE OF ACKNOWLEDGING THE TROUBLE AND | | RESETTING THE INDICATOR, BUT WAS UNSUCCESSFUL. THE TROUBLE MESSAGE HAD BEEN | | REGISTERED AT 1720 EDT, 08/07/96, DURING A THUNDERSTORM. | | | | THE ELECTRONIC TECHNICIAN COMPLETELY REMOVED POWER FROM THE CENTRAL CONTROL | | UNIT, AND THEN RESTORED POWER. THE CENTRAL ALARM CONTROL PANEL REACTIVATED | | WITH THE TROUBLE LIGHT REMOVED. A TEST OF THE ALARM SOUNDING SHOWED THAT | | THE SYSTEM WAS AGAIN FUNCTIONAL, BUT SOME ABNORMALITIES REMAINED, WHICH | | COULD NOT BE CLEARED. | | THE CENTRAL ALARM SYSTEM IS NEW, HAVING BEEN INSTALLED IN LATE MAY, 1996. | | THE SYSTEM VENDOR WAS TIME CONTROLS, INC., WHO USED EDWARDS SYSTEM | | TECHNOLOGY MODULES. BOTH THE SITE WIDE CRITICALITY AND FIRE ALARM ARE | | ACTIVATED BY THIS SYSTEM. THE VENDOR WAS CONTACTED DURING THE AFTERNOON OF | | 08/08/96, AND AGREED TO HAVE AN ENGINEER AT THE NFS SITE DURING THE MORNING | | OF 08/09/96. | | | | DURING THE THUNDERSTORM, WHICH BEGAN ABOUT 1700 EDT, 08/07/96, SECURITY | | PERSONNEL NOTICED SOME UNUSUAL BEHAVIOR OF THEIR MONITORING SYSTEMS, BUT | | THERE WAS NO LOSS OF POWER. THERE WERE SEVERAL LIGHTNING STRIKES, BUT NONE | | NEARBY. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT IN THE MORNING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 30853 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 08/08/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 18:59 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 08/08/96 | | LEU FABRICATION |EVENT TIME: 07:30[EDT]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 08/08/96 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |MILT SHYMLOCK RDO | | DOCKET: 07001113 |JOHN AUSTIN (NMSS) EO | +------------------------------------------------+FRANK CONGEL (IRD) AEOD | |NRC NOTIFIED BY: LON PAULSON | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |KBBE 70.50(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SIX CRITICALITY WARNING SYSTEM HORNS WERE FOUND INOPERABLE. | | | | ON 08/08/96 AT APPROXIMATELY 0730, IT WAS DISCOVERED THAT THREE OF THE | | CRITICALITY WARNING SYSTEM HORNS WERE INOPERABLE WITHIN THE FUEL | | MANUFACTURING OPERATION. SUBSEQUENT TESTING REVEALED THREE ADDITIONAL | | IMPACTED AREAS. THE CRITICALITY WARNING SYSTEM RELIES ON THESE HORNS; | | THEREFORE THE HORN FAILURE CONSTITUTES A CONDITION IN WHICH EQUIPMENT FAILS | | TO FUNCTION AS DESIGNED. | | | | OPERATIONS WERE IMMEDIATELY SUSPENDED AND MOVEMENT OF FISSILE MATERIAL | | STOPPED IN ALL AFFECTED AREAS. ALL WORKERS WERE REMOVED FROM THOSE AREAS | | WITH DEFECTIVE HORNS (6 AREAS). HORN OPERABILITY WAS RESTORED AND | | SATISFACTORILY TESTED AS OF 1820 EDT. NORMAL OPERATIONS HAS RESUMED. TWO OF | | THE SIX HORNS WERE REPLACED AND THE AMPLIFIERS TO THE OTHER FOUR HORNS WERE | | REPLACED. LICENSEE NOTIFIED NRC RGN2 (GOODEN). LICENSEE WILL NOTIFY THE | | STATE AND THE NRC REGION 2 OFFICE IN THE MORNING OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30854 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 08/08/96 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 22:29 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/08/96 | +------------------------------------------------+EVENT TIME: 19:25[PDT]| |NRC NOTIFIED BY: SKAGG |LAST UPDATE DATE: 08/08/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE REVIEWING RESULTS OF AUGMENTED TESTING OF MAIN STEAM SAFETY VALVES | | (MSSV) FOR STEAM GENERATORS 2-1 AND 2-2, THE LICENSEE DISCOVERED THAT 6 OUT | | OF 10 OF THE MSSVs LIFT SETPOINTS EXCEEDED THEIR TECHNICAL SPECIFICATION | | LIMITS. | | | | WHILE REVIEWING THE RESULTS OF AUGMENTED TESTING OF UNIT 2 MSSVs, PG&E | | DETERMINED THAT THE AS-FOUND LIFT PRESSURES FOR 6 OF 10 UNIT 2 MSSVs ON | | STEAM GENERATORS 2-1 AND 2-2 EXCEEDED THE TECHNICAL SPECIFICATION | | TOLERANCES. PRELIMINARY ANALYSIS OF THIS DATA INDICATES THAT THIS | | CONSTITUTES A CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT. THE DESIGN | | BASIS OF THE MSSVs IS TO LIMIT THE SECONDARY SYSTEM PRESSURE OF THE STEAM | | GENERATOR TO ó110% OF DESIGN PRESSURE WHEN PASSING 100% OF DESIGN STEAM | | FLOW). | | | | THE TESTING WAS PERFORMED IN ACCORDANCE WITH PG&Es "TEST PROGRAM PROCEDURES | | FOR MAIN STEAM SAFETY VALVES," SUBMITTED TO THE NRC IN PG&E LETTER | | DCL-96-156, DATED JULY 16, 1996. AS PRESCRIBED BY SURVEILLANCE TEST | | PROCEDURE M-77A, "AUGMENTED TEST PROGRAM FOR MAIN STEAM SAFETY VALVES" | | (MSSV), THE AUGMENTED TESTING HAS BEEN EXPANDED TO INCLUDE MSSVs ON STEAM | | GENERATORS 2-3, AND 2-4. THIS TESTING IS CURRENTLY IN PROGRESS. | | | | THE STEAM GENERATOR 2-1 AND 2-2 MSSVs WERE RESET TO WITHIN ń1% TO MEET THE | | REQUIREMENTS OF THE TECHNICAL SPECIFICATIONS (WHICH IS WITHIN ń3% OF THE | | LIFT SETPOINT). THE MSSVs ARE DRESSER MODEL 3707R. | | | | LICENSEE COMPLETED TESTING STEAM GENERATOR 2-3 MSSVs AND ALL THE VALVES | | WERE WITHIN THEIR TOLERANCE. LICENSEE SHOULD BE COMPLETED TESTING STEAM | | GENERATOR 2-4 MSSVs BY 0400 EDT. | | | | ON STEAM GENERATOR 2-1 MSSVs # 4 (SETPOINT OF 1078psig, LIFTED AT 1147psig) | | AND # 6 (SETPOINT 1103psig, LIFTED AT 1206psig) FAILED. ON STEAM GENERATOR | | 2-2 MSSVs # 7 (SETPOINT OF 1065psig, LIFTED AT 1162psig), # 8 (SETPOINT OF | | 1078psig, LIFTED AT 1146psig), # 9 (SETPOINT OF 1090psig, LIFTED AT | | 1158psig), AND # 223 (SETPOINT OF 1115psig, LIFTED AT 1179psig) FAILED. | | | | LICENSEE WILL NOTIFY THE STATE AND THE COUNTY OF THIS EVENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+