U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/30/96 - 10/31/96 ** EVENT NUMBERS ** 31238 31243 31244 31245 31246 31247 31248 31249 31250 31251 31252 31253 31254 31255 31256 31257 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31238 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 10/29/96 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 11:48 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 10/29/96 | +------------------------------------------------+EVENT TIME: 10:00[EST]| |NRC NOTIFIED BY: CLARKSON |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THEY DISCOVERED TWO OF THE MAIN STEAM SAFETY VALVES | | (3MS-1 & 3MS-10) HAD MISSING SPINDLE NUT COTTER PINS. | | | | THIS DISCOVERY WAS MADE 10/24/96, DURING AN INSPECTION OF THE MAIN STEAM | | SAFETY VALVES. TWO OF THE SIXTEEN VALVES WERE FOUND WITHOUT SPINDLE NUT | | COTTER PINS INSTALLED. THE FUNCTION OF THIS COTTER PIN IS TO AFFIX THE | | SPINDLE NUT TO THE SPINDLE TO PREVENT NUT MOVEMENT DURING PERIODS OF VALVE | | VIBRATION. THE MAIN STEAM SAFETY VALVES ARE DESIGNED TO PROTECT THE MAIN | | STEAM PIPING FROM OVERPRESSURIZATION DURING CERTAIN PLANT TRANSIENTS. WITH | | THE SPINDLE NUT COTTER PIN MISSING, THE SPINDLE NUT COULD ROTATE DOWN THE | | SPINDLE DURING FLOW INDUCED VIBRATION. MOVEMENT TOWARD THE VALVE BODY | | COULD CAUSE THE VALVE TO MALFUNCTION. FOLLOWING A REVIEW (10/29/96) OF | | THIS CONDITION, IT WAS DETERMINED THAT THE EVENT WAS REPORTABLE. THEY ARE | | STILL INVESTIGATING THE REASON THE COTTER PINS WERE MISSING. THE RI WAS | | INFORMED. | | | | * * * UPDATE AT 0850 ON 10/30/96 BY NIX TAKEN BY WEAVER * * * | | | | THE LICENSEE CALLED TO CLARIFY THE FACT THAT THE MISSING COTTER PINS HAD | | NOT YET BEEN REPLACED, BUT WOULD BE REPLACED PRIOR TO UNIT 3 STARTUP. | | HOO NOTIFIED RDO (LESSER). | | | | | | HOO NOTE: SEE EVENT #31248 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31243 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 04:19 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 01:44[CST]| |NRC NOTIFIED BY: JOEY CLARK |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOESEPH TAPIA 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BUMPED FUSE TRIGGERS AN ESF ACTUATION. | | | | A TECHNICIAN BUMPED A FUSE HOLDER WHILE PERFORMING SURVEILLANCE TESTS, | | CAUSING A MOMENTARY INTERRUPTION OF POWER TO A TRIP UNIT. THIS RESULTED IN | | A DIVISION 1 GROUP 2 ISOLATION OF THE REACTOR CORE ISOLATION COOLING SYSTEM | | (RCIC) DUE TO SPURIOUS STEAM SUPPLY PRESSURE LOW AND STEAM SUPPLY LINE HIGH | | FLOW TRIP SIGNALS. ALL EQUIPMENT RESPONDED AS DESIGNED (THE STEAM SUPPLY | | VALVE TO THE RCIC TURBINE CLOSED). THE RCIC SYSTEM HAS BEEN RESET. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31244 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PORTSMOUTH GENERAL HOSPITAL |NOTIFICATION DATE: 10/30/96 | | CITY: PORTSMOUTH REGION: 2 |NOTIFICATION TIME: 09:34 [ET]| | COUNTY: STATE: VA |EVENT DATE: 10/15/96 | |LICENSE#: 45-09102-02 AGREEMENT: N |EVENT TIME: 08:00[EST]| | DOCKET: |LAST UPDATE DATE: 10/30/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MARK LESSER RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ROY HELTZEL | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PORTSMOUTH GENERAL HOSPITAL, PORTSMOUTH, VA. MISSING CALIBRATION SOURCE. | | | | THE LICENSEE DETERMINED ON 10/15/95 AT APPROXIMATELY 0800 EDT THAT A SMALL | | GAMMA CALIBRATION SOURCE WAS NOT ACCOUNTED FOR. FURTHER CHECKING HAS LED | | THE LICENSEE TO QUESTION IF THE SOURCE EVER EXISTED AT THE SITE. THE | | MISSING SOURCE IS 142æCi OF Cs-137 SERIAL NUMBER NEN S356013-020. EXPOSURE | | TO THE SOURCE AT ONE METER WOULD RESULT IN A 0.5 mR/HOUR DOSE. THE SOURCE | | IS IN THE FORM OF EPOXY RESIN IN A PLASTIC VIAL 1.5" DIAMETER BY 4" LONG. | | CALIBRATION SOURCES ARE USUALLY STORED IN THE HOSPITAL'S HOT LAB. THE | | LICENSEE'S CONSULTANT HAS DISCUSSED THIS EVENT WITH REGION 2 (DAVID | | COLLINS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31245 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 10/30/96 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 09:34 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 08:40[EST]| |NRC NOTIFIED BY: DOUG CREMER |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFETY RELIEF VALVE INADVERTENTLY OPENED | | | | AN OPERATOR ACCIDENTALLY OPENED SRV RV-2-02-071D BY BUMPING THE CONTROL | | SWITCH WITH HIS CLIPBOARD WHILE PASSING A UNIT 2 CONTROL BOARD. THE | | OPERATOR IMMEDIATELY RECOGNIZED THE PROBLEM AND RETURNED THE SWITCH TO THE | | NORMAL (AUTOMATIC) POSITION, AND THE SRV CLOSED. THE SRV WAS OPEN FOR | | ABOUT 1 SECOND. THE PLANT RESPONDED AS EXPECTED TO THE TRANSIENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31246 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 10:05 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 10/29/96 | +------------------------------------------------+EVENT TIME: 12:15[EST]| |NRC NOTIFIED BY: DAN HARDIN |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CP&L SUPERVISOR TESTED POSITIVE IN A RANDOM DRUG SCREENING. HIS | | PROTECTED AREA ACCESS HAS BEEN TERMINATED. HE HAD NOT PERFORMED SAFETY | | RELATED WORK. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31247 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 10/30/96 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:15 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 08:25[EST]| |NRC NOTIFIED BY: CORNAX |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN ESF ACTUATION DUE TO A SPIKE ON RAD MONITOR R-49. | | | | THE PLANT EXPERIENCED AN ELECTRICAL DISTURBANCE IN THEIR 345kV SYSTEM THAT | | CAUSED RAD MONITOR R-49 TO SPIKE. THIS RESULTED IN A S/G BLOWDOWN VALVE | | ISOLATION(ESF ACTUATION). THE PLANT WAS STABLE DURING THE EVENT. THE RAD | | MONITOR WAS RESET AND ALL SYSTEMS WERE RETURNED TO NORMAL. THE RI WAS | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31248 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 10/30/96 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 14:14 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 11:00[EST]| |NRC NOTIFIED BY: NIX |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED FOUR OF SIXTEEN MAIN STEAM SAFETY VALVES WITH THE | | SPINDLE NUT COTTER PINS INSTALLED IMPROPERLY. | | | | THIS CONDITION WAS DISCOVERED DURING AN INSPECTION OF THE MAIN STEAM SAFETY | | VALVES ON 10/14/96. FOUR OF THE VALVES HAD THE SPINDLE NUT COTTER PIN | | INCORRECTLY BENT SO THAT IT COULD NOT PREVENT THE PIN FROM POSSIBLY | | VIBRATING OUT OF THE SPINDLE NUT. THE COTTER PINS WERE CORRECTLY BENT | | FOLLOWING THEIR DISCOVERY. THE FUNCTION OF THE COTTER PIN IS TO PREVENT | | THE NUT FROM MOVEMENT ON THE SPINDLE DURING VALVE VIBRATION. THE MAIN STEAM | | SAFETY VALVES FUNCTION IS TO PROTECT MAIN STEAM PIPING FROM | | OVERPRESSURIZATION DURING CERTAIN PLANT TRANSIENTS AND CYCLE FULLY SHUT, | | FOLLOWING SUFFICIENT STEAM HEADER BLOWDOWN, TO MINIMIZE THE POTENTIAL FOR A | | PRIMARY SYSTEM OVERCOOLING EVENT. IF AN INCORRECTLY INSTALLED COTTER PIN | | VIBRATED OUT OF THE SPINDLE NUT, IT COULD CAUSE A CONDITION WHERE THE | | SPINDLE NUT MIGHT ROTATE DOWN THE SPINDLE, RESULTING IN THE POSSIBLE | | FAILURE OF THE VALVE TO PROPERLY CLOSE. ON 10/30/96 IT WAS CONCLUDED THAT A | | REASONABLE DOUBT EXISTED AS TO WHETHER THESE VALVES COULD PERFORM THEIR | | DESIGN FUNCTIONS, THEREFORE IT WAS DETERMINED THIS WAS A REPORTABLE EVENT. | | THEY ARE CURRENTLY INVESTIGATING WHY THESE COTTER PINS WERE INCORRECTLY | | INSTALLED. THE RI WAS INFORMED. | | | | HOO NOTE: SEE EVENT #31238 FOR A RELATED EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31249 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 10/30/96 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 16:04 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 10/29/96 | | LEU FABRICATION |EVENT TIME: 22:30[EST]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 10/30/96 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |MARK LESSER RDO | | DOCKET: 07001113 |COMBS EO | +------------------------------------------------+ROTH NMSS | |NRC NOTIFIED BY: PAULSON |BARRETT IRD | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A CONDITION PURSUANT TO NRC BULLETIN 91-01 SINCE MASS | | CONTROL WAS LOST AS A RESULT OF SCRUBBER FAILURE, AND LESS THAN A SAFE MASS | | WAS INVOLVED. | | | | AT APPROXIMATELY 10:30 ON 10/29/96, RADIATION PROTECTION REPORTED THAT | | 16kgs OF MATERIAL WERE REMOVED FROM A FAVORABLE GEOMETRY 6-INCH DEWATERING | | CENTRIFUGE VENT OFFGAS(VOG) DUCT. SUBSEQUENT INSPECTIONS OF A DOWNSTREAM | | 8-INCH DUCT REMOVED AN ADDITIONAL 11.6kgs OF MATERIAL, FOR A TOTAL | | ACCUMULATION OF 27.6kgs. THE MATERIAL REMOVED WAS ANALYZED AND DETERMINED | | TO BE 60wt.% URANIUM, FOR A TOTAL U CONTENT OF 16.6kgs. THIS IS LESS THAN | | THE SAFE MASS LIMIT OF 37kgs FOR 4.025% ENRICHED UO2. | | | | THE CENTRIFUGE SCRUBBER WAS DETERMINED TO HAVE A PARTIALLY PLUGGED SPRAY | | NOZZLE, CAUSING THE URANIUM PARTICULATE CARRYOVER. THE SECOND CONTROL, | | FAVORABLE GEOMETRY, REMAINED IN EFFECT. THUS NO UNSAFE CONDITION EXISTED. | | DOWNSTREAM DUCTWORK HAS BEEN INSPECTED; NO SIGNIFICANT ACCUMULATION FOUND. | | THE NOZZLE HAS BEEN REMOVED, CLEANED AND REINSTALLED. ALL CHEMICAL | | CONVERSION LINES HAVE BEEN SHUT DOWN PENDING ADDITIONAL | | INSPECTIONS/CORRECTIVE ACTIONS. | | | | 1) SAFETY SIGNIFICANCE - LOW - FAVORABLE GEOMETRY INTACT(6-INCH DUCT) | | 2) POTENTIAL CRITICALITY PATHS INVOLVED - MULTIPLE FAILURE MODES WOULD BE | | REQUIRED BEFORE A CRITICALITY EXCURSION IS POSSIBLE | | 3) CONTROLLED PARAMETERS - GEOMETRY: 6" & 8" DIA FAVORABLE GEOMETRY | | CYLINDRICAL DUCTS USED | | MASS: NO SIGNIFICANT URANIUM ACCUMULATION ALLOWED IN DUCTWORK | | | | THE STATE AND LOCAL AGENCIES WILL BE INFORMED ALONG WITH REG 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31250 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 16:08 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 01:44[CST]| |NRC NOTIFIED BY: MATZKE |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A LOSS OF CONTAINMENT BOUNDARY. | | | | TECHNICAL SPECIFICATION 2.8(1) REQUIRES, IN PART, FOR REFUELING OPERATIONS: | | ALL AUTOMATIC CONTAINMENT ISOLATION VALVES BE OPERABLE OR AT LEAST ONE | | VALVE IN EACH LINE SHALL BE CLOSED. A CHECK LIST IS PERFORMED TO ENSURE | | CONTAINMENT CLOSURE TO MEET THIS SPECIFICATION DURING A SHUTDOWN WHERE | | VARIOUS EVOLUTIONS MAY IMPACT THE EXACT MANNER IN WHICH THE CONTAINMENT IS | | CONSIDERED TO BE CLOSED. AT THE TIME OF THIS EVENT, "YCV-1045A" WAS THE | | CONTAINMENT CLOSURE BOUNDARY ON "A" S/G. | | | | AT 01:13 (CST) ON 10/30/96 THE FUSES FOR "YCV-1045", STEAM SUPPLY TO STEAM | | DRIVEN AUX FW PUMP "FW-10", WERE PULLED TO ACCOMMODATE MAINTENANCE. PRIOR | | TO THIS EVOLUTION, THE CONTROL SWITCH FOR "YCV-1045" WAS CLOSED. "YCV-1045" | | IS A FAIL OPEN VALVE WHICH WAS CLOSED FOR THE CLEARANCE. THE STEAM SUPPLY | | VALVES FROM EACH HEADER("YCV-1045A" & "YCV-1045B") OPENED, AS DESIGNED, | | BASED UPON THE POSITION OF "YCV-1045". THE POSITION OF THESE VALVES IS NOT | | ANNUNCIATED ON THE CONTROL BOARDS, SO THE ONLY INDICATION READILY APPARENT | | TO THE OPERATORS IN THE CONTROL ROOM WAS THE CHANGE IN THE POSITION LIGHTS | | FROM GREEN TO RED FOR THE TWO VALVES. THIS WAS NOTICED BY THE OPERATOR AT | | APPROXIMATELY 01:44, AT WHICH TIME THE VALVES WERE TAKEN TO OVERRIDE | | POSITION AT WHICH POINT THE VALVES CLOSED. DURING THE TIME "YCV-1045A" WAS | | OPEN, 2 FUEL BUNDLES WERE TRANSFERRED FROM THE UPENDER AND PLACED IN THE | | CORE. IT WAS INITIALLY BELIEVED THAT CONTAINMENT WAS STILL CLOSED WITH THE | | VALVES OPEN. IT WAS THEN DETERMINED THAT WITH THE SECONDARY MANWAY REMOVED | | FROM "A" STEAM GENERATOR, A PATH EXISTED THROUGH THE MANWAY, OUT THE STEAM | | LINE AROUND THE MSIV, THROUGH "YCV-1045A", THROUGH A 1/2" NEEDLE | | VALVE("MS-366") WHICH WAS 1/16" OPEN, AND THROUGH ITS OPEN ISOLATION | | VALVE("MS-365"). ON THE DOWN STREAM SIDE OF THE MSIV THERE WAS IS A CHECK | | VALVE("HCV-1041B") WHICH WAS DETERMINED NOT TO SEAT TIGHTLY IN THIS | | CONFIGURATION TO BE CONSIDERED A BOUNDARY. AT 12:05 THE LICENSEE | | DETERMINED THAT THIS EVENT WAS REPORTABLE. THERE WAS NO INDICATION OF ANY | | RELEASE. THE RI WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31251 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 18:28 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 14:45[CST]| |NRC NOTIFIED BY: LOESCH |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | "D2" EMERGENCY DIESEL GENERATOR AUTOSTARTED DURING A TEST. | | | | THIS OCCURRED DURING POST MAINTENANCE TESTING OF THE "D2" EMERGENCY DIESEL | | GENERATOR, WHEN IT INADVERTENTLY STARTED DURING THE "AIR ROLL" OF THE | | ENGINE AFTER SHUTDOWN. IT DID NOT LOAD AND WAS IMMEDIATELY SHUTDOWN, WITH | | THE "AIR ROLL" BEING SUCCESSFULLY COMPLETED. THE CAUSE WAS DUE TO PERSONNEL | | NOT FOLLOWING THE TEST PROCEDURE PROPERLY. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31252 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 19:10 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 16:55[CST]| |NRC NOTIFIED BY: HOUSTON |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT THE PLANT IS IN AN ANALYZED CONDITION. | | | | THIS WAS DETERMINED DURING THE PERFORMANCE OF SPECIAL PROCEDURE(LST-96-070) | | WHEN THE AUX EQUIPMENT ROOM WAS FOUND NOT TO MEET THE 1/8" POSITIVE | | PRESSURE REQUIREMENT. IT HAS BEEN DETERMINED THAT IT IS POSSIBLE THAT THE | | GENERAL DESIGN CRITERIA 19 OF APPENDIX A OF 10CFR50 MAY NOT BE ADHERED TO. | | DUE TO THE ABOVE CONDITION, THE POSSIBILITY EXIST THAT THE PLANT IS IN AN | | UNANALYZED CONDITION. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31253 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 21:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 21:00[EST]| |NRC NOTIFIED BY: HACKNEY |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 | 86 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 IS BEING SHUT DOWN FROM 100% POWER DUE TO TS 3.8.2.1 REQUIREMENT. | | | | THE LICENSEE INITIATED A PLANT SHUTDOWN AT THE RATE OF 20%/HR DUE TO THE | | CHANNEL 3 125 VOLT BATTERY BANK FAILING THE REQUIRED CRITERIA FOR THE | | MODIFIED PERFORMANCE TEST. THE BATTERY WAS THEREFORE DECLARED INOPERABLE | | ON 10/28/96 AT 09:56 AND REQUIRED TO BE OPERABLE OR THE PLANT BE SHUTDOWN | | BY 10/31/96 AT 09:56. THIS BATTERY IS A SHARED COMPONENT WITH UNIT 2, SO | | UNIT 2 WILL ALSO START SHUTTING DOWN LATER IN THE NIGHT IF THE BATTERY IS | | NOT RETURNED TO OPERABLE CONDITION. THE LICENSEE ALSO NOTED THAT THEY STILL | | HAVE A STEAM GENERATOR TUBE LEAK WHICH STARTED 08/30/96 ON THE "1B" S/G. | | THIS LEAK(14.4 GPD) HAS NOTHING TO DUE WITH THE PLANT S/D, BUT TUBE LEAKAGE | | WILL BE CONTINUOUSLY MONITORED DURING SHUTDOWN FOR ANY SIGNIFICANT CHANGES. | | | | THE RI WILL BE INFORMED. | | | | NOTE: UNIT 2 IS ALSO BEING SHUT DOWN DUE TO THIS INOPERABLE BATTERY. | | SEE EVENT #31257. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31254 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 21:50 [ET]| |RX TYPE: [1] CE |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 17:40[EST]| |NRC NOTIFIED BY: MCDOUGOLD |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE MAINE DEPARTMENT OF HUMAN SERVICES OF AN | | UNSCHEDULED RELEASE. | | | | CONTROL ROOM PERSONNEL NOTICED THE PRIMARY VENT STACK GAS RELEASE HAD | | ELEVATED TO 100CPM. SAMPLES WERE TAKEN AND A 0.05 CURIE RELEASE WAS | | CALCULATED. THIS RELEASE WAS GREATER THAN THE AMOUNT THE LICENSEE STATED | | (0.01 CURIE) FOR THEIR DAILY RELEASE ON THEIR TELEPHONE ANSWERING MACHINE | | TAPE. THE VALUE STATED ON THE TAPE CAN BE CHANGED ON A DAILY BASIS. THE | | CAUSE OF LICENSEE EXCEEDING THEIR STATED DAILY RELEASE WAS DUE TO THE | | CHEMISTRY SECTION PURGING RCS SAMPLE LINES FOR MORE THAN 5 MINS. THE RI | | WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31255 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 10/30/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:58 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 18:30[CST]| |NRC NOTIFIED BY: WIEGING |LAST UPDATE DATE: 10/30/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED MOTOR CONTROL CENTERS(MCCs) 136X-1 AND 136X-2 | | INOPERABLE. | | | | THESE MCCs ARE REQUIRED BY TS FOR BOTH UNITS 1 & 2. THEIR FEED BREAKERS ARE | | CURRENTLY CLOSED AND SUPPLYING LOAD, BUT THE MECHANICAL TRIP INTERLOCKS OF | | THE TWO BREAKERS ARE POISED TO TRIP. THIS CONDITION IS DUE TO A | | MISALIGNMENT OF THE RACKING MECHANISM TRIP INTERLOCK ASSEMBLY WHICH WAS | | FOUND DURING A ROUTINE BREAKER INSPECTION DURING UNIT 1 MAINTENANCE OUTAGE. | | THIS CONDITION IS ASSUMED TO HAVE EXISTED SINCE AT LEAST 1993, WHEN THE | | BREAKERS WERE LAST RACKED OUT. FROM THAT TIME TO THE PRESENT, NO | | ABNORMALITIES WERE NOTED IN THE PERFORMANCE OF THESE BREAKERS, AND ALL | | EQUIPMENT SUPPLIED BY THESE MCCs OPERATED, AS EXPECTED. PLANS ARE UNDERWAY | | TO REPAIR THIS CONDITION. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31256 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/31/96 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 00:27 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 22:25[CST]| |NRC NOTIFIED BY: BILL HENNIG |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - 1 OF 2 PRESSURIZER SAFETY VALVES FAILED ITS INITIAL SETPOINT TEST - | | | | WITH UNIT 2 DEFUELED, 1 OF 2 PRESSURIZER SAFETY VALVES, #2RC-434, FAILED | | ITS INITIAL SETPOINT TEST AT WYLE LABS. THE SAFETY VALVE LIFTED AT | | 2564 PSIG WHEN TESTED AT 90øF WHICH IS 5 PSIG ABOVE THE SETTING OF | | 2485 PSIG +3%. WHEN THE VALVE WAS TESTED AT 140øF, ITS SETPOINT WAS 1.3% | | LOWER. THIS VALVE WAS TESTED PER ASME B&PV CODE, SECTION XI AND OM-1-1981. | | | | THE OTHER UNIT 2 SAFETY VALVE, #2RC-435, WILL BE REMOVED, SHIPPED TO WYLE | | LABS, AND TESTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31257 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 10/31/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 03:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/31/96 | +------------------------------------------------+EVENT TIME: 03:00[EST]| |NRC NOTIFIED BY: SPENCER HACKNEY |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO INOP 125 VOLT VITAL BATTERY - | | | | ONE OF FOUR 125 VOLT VITAL BATTERIES (CHANNEL 3) FAILED THE REQUIRED | | TEST CRITERIA FOR A MODIFIED PERFORMANCE TEST. AT 0956 ON 10/28/96, | | THE LICENSEE DECLARED THE BATTERY INOPERABLE (ALTHOUGH IT IS FUNCTIONAL). | | TECH SPEC LCO A/S 3.8.2.1 REQUIRES THE LICENSEE TO RESTORE THE INOPERABLE | | VITAL BATTERY TO OPERABLE STATUS WITHIN 72 HOURS WHILE UNIT 2 IS IN MODES | | 1 THROUGH 4 OR TO SHUT UNIT 2 DOWN TO HOT STANDBY MODE WITHIN 6 HOURS AND | | COLD SHUTDOWN MODE WITHIN THE FOLLOWING 30 HOURS. | | | | AT 0300 ON 10/31/96, THE LICENSEE BEGAN SHUTTING UNIT 2 DOWN FROM 100% | | POWER. | | | | THIS BATTERY ALSO SUPPLIES POWER TO UNIT 1. | | | | THE LICENSEE PLANS TO REPLACE THE BATTERY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: UNIT 1 IS ALSO BEING SHUT DOWN DUE TO THIS INOPERABLE BATTERY. | | SEE EVENT #31253. | +------------------------------------------------------------------------------+