U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/28/98 - 01/29/98 ** EVENT NUMBERS ** 33609 33610 33611 33612 33613 33614 33615 33616 33617 33618 33619 33620 33621 33622 33623 +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 33609 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NUCLETRON CORPORATION(COLUMBIA, MD) |NOTIFICATION DATE: 01/28/98 | | CITY: DULLES AIRPORT REGION: 2 |NOTIFICATION TIME: 11:04 [ET]| | COUNTY: LOUDOUN STATE: VA |EVENT DATE: 01/28/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/28/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |CHRIS CHRISTENSEN RDO | | |COOL EO | +------------------------------------------------+DAVID SILK RDO1 | |NRC NOTIFIED BY: HALL(U.S.CUSTOMS) |RICHARD BARRETT IRD | |HQ OPS OFFICER: CHAUNCEY GOULD |BELT DOT | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | U.S. CUSTOMS SERVICE AT DULLES INTERNATIONAL AIRPORT, VIRGINIA, REPORTED | | THEIR RADIATION DETECTION PAGERS PEGGED THEIR SCALE WITH A READING OF 9 (NO | | UNITS ON PAGER) WHEN THEY APPROACHED 12 CANISTERS WHICH WERE BEING SHIPPED | | FROM NUCLETRON CORPORATION OF COLUMBIA, MARYLAND, TO MALLINCKRODT IN | | HOLLAND. | | | | THE CONTAINERS DO NOT APPEAR TO BE DAMAGED BUT THE READINGS THEY WERE | | RECEIVING AT THE CANISTERS WAS HIGH ENOUGH TO HAVE THEM BACK OFF. THE | | CANISTERS CONTAINED IRIDIUM-192(2.920 CI). | | | | ***UPDATE AT 1155 BY HALL TO GOULD*** THE AIRPORT SURVEYED THE CANISTERS | | WITH A RADIATION DETECTOR AND DETERMINED THEY WERE WITHIN FAA's LIMITS FOR | | BEING TRANSPORTED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33610 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 11:30 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 09:48[EST]| |NRC NOTIFIED BY: ED FERRIS |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK 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 +------------------------------------------------------------------------------+ | SPIKE ON RB VENT SYSTEM EXHAUST RAD MONITOR (REFER TO EVENT #33617.) | | | | AT 0946, THE "B" REACTOR BUILDING VENTILATION SYSTEM EXHAUST RADIATION | | MONITOR SPIKED TO A LEVEL OF 70,000 CPM. THE "A" REACTOR BUILDING VENT | | EXHAUST RAD MONITOR, AS WELL AS THE REFUELING FLOOR VENT SYSTEM EXHAUST RAD | | MONITORS, REMAINED AT NORMAL RAD LEVELS. PORTABLE CONTINUOUS AIR MONITORS | | LOCATED IN THE REACTOR BUILDING ALSO REFLECTED NORMAL READINGS. THE SPIKE | | ON THE "B" REACTOR BUILDING VENT MONITOR IS BELIEVED TO BE SPURIOUS, AND | | THE CAUSE IS BEING INVESTIGATED. THE RAD MONITOR SPIKE RESULTED IN | | ISOLATION OF REACTOR BUILDING VENTILATION AND A STANDBY GAS TREATMENT | | SYSTEM ACTUATION. PRIMARY CONTAINMENT ATMOSPHERE SAMPLE VALVES ALSO | | ISOLATED. ALL ISOLATIONS AND INITIATIONS FUNCTIONED PROPERLY AS A RESULT | | OF THE RAD MONITOR SPIKE. THE "B" REACTOR BUILDING VENT MONITOR IS BEING | | REMOVED FROM SERVICE FOR TROUBLESHOOTING AND REPAIR. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33611 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 01/28/98 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 12:52 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 11:50[EST]| |NRC NOTIFIED BY: SWEENEY |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A NON-LICENSED EMPLOYEE WAS DETERMINED TO BE UNDER THE INFLUENCE OF ALCOHOL | | DURING A FOR-CAUSE TEST. THE EMPLOYEE'S ACCESS TO THE PLANT HAS BEEN | | SUSPENDED. REFER TO THE HOO LOG FOR ADDITIONAL DETAILS. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33612 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:00 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 12:05[CST]| |NRC NOTIFIED BY: M. GRAHAM |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR BUILDING AVERAGE TEMPERATURES COULD EXCEED EQ LIMITS. | | | | THE LICENSEE HAS CONDUCTED A SENSITIVITY ANALYSIS AND CONCLUDED THAT THE | | POST-LOCA REACTOR BUILDING GENERAL AREA TEMPERATURE WILL BE AS HIGH AS | | 139øF. THIS IS 35ø ABOVE THE TEMPERATURE LISTED IN UFSAR SECTION 3.11 AND | | 19ø ABOVE THE EQ MILD ZONE LIMIT. THIS ISSUE DOES NOT AFFECT THE CURRENT | | OPERABILITY OF THE PLANT BECAUSE BOTH UNITS ARE IN COLD SHUTDOWN. | | | | THIS ISSUE AFFECTS ALL CLASS 1E EQUIPMENT IN THE REACTOR BUILDING. THE | | PROGRAMS AFFECTED ARE INSTRUMENT SETPOINT CALCULATIONS, ENVIRONMENTAL | | QUALIFICATION PROGRAM, AND ELECTRICAL PROTECTIVE EQUIPMENT SETPOINTS | | (THERMAL OVERLOADS). | | | | AS A RESULT OF THIS REVIEW, THE LICENSEE CONCLUDED THAT SOME TECHNICAL | | SPECIFICATION RELATED INSTRUMENT SETPOINTS MAY HAVE INSUFFICIENT MARGINS. | | THEREFORE, BOTH UNITS MAY HAVE BEEN IN UNANALYZED CONDITIONS DURING | | OPERATION DUE TO THIS ISSUE. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33613 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 15:42 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 01/27/98 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: MICHAEL ZACCONE |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |VERN HODGE 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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT REGARDING WOODWARD GOVERNORS FOR DIESEL GENERATORS | | AT V.C. SUMMER NUCLEAR STATION (VCSNS) | | | | THE FOLLOWING INFORMATION WAS SUBMITTED BY THE LICENSEE VIA FACSIMILE: | | | | "ON JANUARY 9, 1998, CONDITION EVALUATION REPORT 98-0038 AND NONCONFORMANCE | | NOTICE (NCN) 98-0038 REPORTED THE FAILURE OF EG-A CONTROL, SERIAL NUMBER | | 1425251. DUE TO POTENTIAL APPLICATIONS IN THE INDUSTRY AND THE SAFETY | | SIGNIFICANCE OF ITS APPLICATION AS A GOVERNOR CONTROL FOR EMERGENCY DIESEL | | GENERATORS (EDGs), THIS FAILURE IS CONSIDERED TO BE REPORTABLE UNDER 10 CFR | | PART 21. IN THIS CASE, V.C. SUMMER NUCLEAR STATION ENSURED THAT ADEQUATE | | TESTING HAD BEEN PERFORMED TO THE ASSOCIATED EG-A TO VERIFY ITS OPERABLE | | STATUS. THE VENDOR, ENGINE SYSTEMS, INCORPORATED (ESI), HAS BEEN NOTIFIED | | OF THIS SITUATION AND UNDERSTANDS THAT A PART 21 NOTIFICATION IS BEING | | SUBMITTED BASED ON THEIR CERTIFICATION OF CONFORMANCE ON THE EG-A WITH | | INADEQUATE POST-REFURBISHMENT BENCH TESTING BY THE VENDOR THAT DID NOT | | IDENTIFY INTERMITTENT FAILURES IN ELECTRICAL COMPONENTS (SUCH AS | | POTENTIOMETERS AND ZENER DIODES). | | | | A TEAM FROM VCSNS PROCUREMENT ENGINEERING FLEW TO THE VENDOR'S REPAIR | | FACILITY (WOODWARD GOVERNOR COMPANY) IN FORT COLLINS, CO, TO EVALUATE THEIR | | REPAIR PROGRAM. FUTURE PURCHASE REQUISITIONS FOR EG-A REPAIR/REFURBISHMENT | | WILL INCLUDE REQUIREMENTS FOR A 50-HOUR BURN-IN AND BENCH TESTING OF THE | | EG-A CONTROL FOR DETECTION OF INTERMITTENT FAILURES." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33614 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 16:34 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 15:26[EST]| |NRC NOTIFIED BY: JOHN SLATTERY |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATIONS DUE TO HIGH LAKE LEVEL | | | | THE LICENSEE NOTIFIED COUNTY HIGHWAY DEPARTMENTS AND LOCAL RESIDENTS | | REGARDING HIGH LAKE LEVELS. PLANT PROCEDURE 0.OP.59.1, "RESERVOIR | | SPILLWAY," REQUIRES THAT THESE NOTIFICATIONS BE MADE WHENEVER LAKE LEVEL | | INCREASES TO 250.9 FEET MSL. THESE NOTIFICATIONS WERE MADE DUE TO THE | | POTENTIAL FOR DOWNSTREAM FLOODING; THE PLANT IS UNAFFECTED AT THIS TIME. | | THE LICENSEE REPORTED THAT THE INCREASED LAKE LEVEL HAS BEEN CAUSED BY | | HEAVY RAINFALL IN THE AREA. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33615 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/28/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 16:40 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 16:35[EST]| |NRC NOTIFIED BY: R. SMITH |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | |VIA FACSIMILE FEMA | | |VIA FACSIMILE DOE | | |VIA FACSIMILE USDA | | |VIA FACSIMILE HHS | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO VIOLATION OF NPDES PERMIT | | | | THE LICENSEE NOTIFIED THE CONNECTICUT STATE DEPARTMENT OF ENVIRONMENTAL | | PROTECTION REGARDING A VIOLATION OF THE SITE NPDES (NATIONAL POLLUTION | | DISCHARGE ELIMINATION SYSTEM) PERMIT. THE MAINTENANCE SHOP AND OIL ROOM | | OIL/WATER SEPARATOR WAS PUMPED INTO THE YARD DRAIN SYSTEM, WHICH IS AN | | UNAPPROVED DISCHARGE PATH. UPON DISCOVERY, THE DISCHARGE WAS TERMINATED, | | AND THE AREA WAS SURVEYED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. IN ADDITION TO THE | | NOTIFICATIONS REFERENCED ABOVE, THE NRC OPERATIONS CENTER NOTIFIED EPA AND | | DOT/NRC VIA FACSIMILE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33616 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 17:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 15:00[EST]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ICE CONDENSER FLOW PASSAGES BLOCKED BY SNOW AND ICE ACCUMULATION | | | | DURING AN ICE CONDENSER FLOW PASSAGE INSPECTION, THE LICENSEE DETERMINED | | THAT 10 TO 20% OF THE ICE CONDENSER FLOW PASSAGES IN BOTH UNITS WERE | | RESTRICTED BY SNOW AND ICE. A MINIMUM OF NINE RESTRICTED FLOW PASSAGES WERE | | DISCOVERED IN EACH OF THE UNITS' 24 ICE CONDENSER BAYS. ACCORDING TO THE | | PLANT TECHNICAL SPECIFICATIONS, MORE THAN ONE RESTRICTED FLOW PASSAGE PER | | BAY IS EVIDENCE OF ABNORMAL DEGRADATION OF THE ICE CONDENSER. THE LICENSEE | | IS CURRENTLY INVESTIGATING THE CAUSE OF THIS CONDITION, AND POTENTIAL | | PREVENTIVE ACTIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33617 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:44 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 15:49[EST]| |NRC NOTIFIED BY: KLEVORN |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STANDBY GAS TREATMENT SYSTEM WOULD NOT HAVE AUTOMATICALLY STARTED IN | | RESPONSE TO HIGH RADIATION SIGNAL. (REFER TO EVENT #33610.) | | | | THE LICENSEE HAS DISCOVERED A CONFIGURATION IN WHICH THE STANDBY GAS | | TREATMENT SYSTEM (SGTS) WOULD NOT HAVE AUTOMATICALLY STARTED IN RESPONSE TO | | A REACTOR BUILDING VENTILATION RADIATION MONITOR ALARM. AT 1030, THE 'B' | | REACTOR BUILDING BELOW REFUEL FLOOR VENTILATION EXHAUST RADIATION MONITOR | | FAILED; HOWEVER, THE 'A' MONITOR REMAINED IN SERVICE. IN ADDITION, THE 'A' | | SGTS SUBSYSTEM WAS OUT OF SERVICE FOR PLANNED MAINTENANCE. AT 1549, THE | | LICENSEE DETERMINED THAT THE REMAINING ('B') SGTS SUBSYSTEM WOULD NOT HAVE | | AUTOMATICALLY STARTED IN RESPONSE TO A HIGH RADIATION CONDITION IN THE | | REACTOR BUILDING BELOW REFUEL FLOOR VENTILATION EXHAUST FLOWPATH. THE | | LICENSEE REPORTED THAT THE 'A' RADIATION MONITOR ONLY SENDS A START SIGNAL | | TO THE 'A' SGTS SUBSYSTEM. | | | | THE LICENSEE MANUALLY STARTED THE 'B' SGTS SUBSYSTEM AND ISOLATED THE | | REACTOR BUILDING VENTILATION SYSTEM. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33618 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:08 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 00:00[CST]| |NRC NOTIFIED BY: R. FRANZ |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |VERN HODGE NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT - DEVIATIONS IN SAFETY RELATED BATTERY CHARGERS | | | | THE LICENSEE HAS IDENTIFIED SEVERAL DEVIATIONS IN POWER CONVERSION | | PRODUCTS, INC. MODEL 3SC-130-130 BATTERY CHARGERS USED IN SAFETY-RELATED | | APPLICATIONS. THESE DEVIATIONS INCLUDE INADEQUATE SOLDER CONNECTIONS AND | | INCORRECT TIME DELAY ON A HIGH VOLTAGE ALARM (DSHV) CIRCUIT CARD. IN | | ADDITION, AN INCORRECT DSHV RESET VOLTAGE SETPOINT WAS SPECIFIED BY SARGENT | | AND LUNDY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33619 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/28/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:33 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/28/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:25[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/28/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: LARSON | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4-HOUR NRC BULLETIN 91-01 REPORT | | | | A DEFICIENT NUCLEAR CRITICALITY SAFETY ANALYSIS EVALUATION HAS BEEN | | IDENTIFIED. THE NCSA FAILS TO IDENTIFY THE CONTROLS/PARAMETERS NEEDED TO | | CONTROL WET AIR EVACUATION (WAE) USING AN AIR JET/AIR EJECTOR. USE OF THIS | | NCSA HAS BEEN SUSPENDED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33620 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/28/98 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 20:22 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 17:25[CST]| |NRC NOTIFIED BY: D. DALY |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE DUE TO FAILED STEAM SUPPLY DRAIN VALVE | | | | AN OPERATOR NOTICED THAT THE CONTROL ROOM POSITION INDICATOR FOR THE HIGH | | PRESSURE COOLANT INJECTION (HPCI) TURBINE STEAM SUPPLY STOP VALVE ABOVE | | SEAT DRAIN VALVE INDICATED CLOSED. (THE VALVE IS USUALLY OPEN.) THIS IS AN | | AIR OPERATED, SPRING-TO-CLOSE VALVE AND IS USED TO DRAIN CONDENSATE FROM | | PIPING BETWEEN THE HPCI TURBINE STEAM SUPPLY VALVE AND THE STOP VALVE. THE | | LICENSEE DETERMINED THAT THE DRAIN VALVE WAS ACTUALLY CLOSED AND THAT THE | | VALVE DIAPHRAGM APPEARED TO HAVE RUPTURED. THE HPCI SYSTEM HAS BEEN | | DECLARED INOPERABLE, AND THE HPCI TURBINE STEAM INLET INBOARD ISOLATION | | VALVE CONTROL SWITCH WAS PLACED IN THE PULL-TO-LOCK POSITION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33621 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 01/28/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 20:26 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 01/28/98 | | LEU FABRICATION |EVENT TIME: 19:40[EST]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 01/28/98 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |CHRIS CHRISTENSEN RDO | | DOCKET: 07001113 |MARGARET FEDERLINE EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: RICK FOLECK | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INFORMATION CALL DUE TO FIRE AT FACILITY | | | | A SMALL FIRE OCCURRED IN THE COMPONENTS OPERATION (FCO) BUILDING. THE FIRE | | DID NOT INVOLVE ANY RADIOACTIVE MATERIALS (THEY ARE HOUSED IN A DIFFERENT | | BUILDING). THE BUILDING WAS EVACUATED DUE TO SMOKE, AND THE ONSITE | | EMERGENCY RESPONSE ORGANIZATION WAS ACTIVATED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33622 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 01/28/98 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 20:56 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/28/98 | +------------------------------------------------+EVENT TIME: 16:47[CST]| |NRC NOTIFIED BY: RILEY COLLINS |LAST UPDATE DATE: 01/28/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM DUE TO PROBLEMS WITH MSR CONTROLS | | | | THE REACTOR WAS MANUALLY SCRAMMED DUE TO DIFFERENTIAL TEMPERATURES OF >25øF | | BETWEEN THE MOISTURE SEPARATOR/REHEATERS AND THE LOW PRESSURE TURBINES. THE | | '1Y98' INVERTER LOST POWER WHILE THE LICENSEE WAS ATTEMPTING TO RESTORE IT | | TO SERVICE FOLLOWING MAINTENANCE. THE RESULTANT LOSS OF POWER TO A MOISTURE | | SEPARATOR/REHEATER (MSR) CONTROL CABINET CAUSED UNEVEN HEATING OF STEAM IN | | THE SECOND STAGE OF THE MSR, AND LED TO THE HIGH DIFFERENTIAL TEMPERATURES. | | ALL CONTROL RODS INSERTED FOLLOWING THE SCRAM. | | | | THE REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM AUTOMATICALLY STARTED ON | | LOW-LOW REACTOR WATER VESSEL WATER LEVEL (LEVEL 2) FOLLOWING THE SCRAM, BUT | | IT AUTOMATICALLY ISOLATED WHEN REACTOR VESSEL WATER LEVEL REACHED THE | | HIGH-HIGH SETPOINT (LEVEL 8). THE UNIT IS CURRENTLY STABLE IN HOT SHUTDOWN. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33623 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/29/98 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 02:19 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/29/98 | +------------------------------------------------+EVENT TIME: 01:08[EST]| |NRC NOTIFIED BY: CROSSMAN |LAST UPDATE DATE: 01/29/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPDS COMPUTER SYSTEM FAILURE | | | | THE PLANT LOST ITS SPDS COMPUTER, AND IT COULD NOT BE RECOVERED WITHIN 1 | | HOUR. THE CAUSE OF FAILURE IS UNKNOWN AT THIS TIME, BUT MAINTENANCE | | PERSONNEL ARE STILL WORKING ON IT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | | ***UPDATE AT 0513 ON 01/29/98 FROM CROSSMAN TO GOULD*** | | | | THE SPDS WAS RESTORED TO MINIMUM OPERATION AT 0500. THEY HAD PROBLEMS WITH | | SOME OF THE CRT DISPLAYS WHICH HAD TO BE DISCONNECTED TO RETURN SPDS TO | | MINIMUM OPERABILITY. THEY ARE CONTINUING WORK ON THE FAILED MONITORS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. THE R2DO | | (CHRISTENSEN) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+