U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/04/97 - 03/05/97 ** EVENT NUMBERS ** 31799 31874 31883 31884 31885 31886 31887 31888 31889 31890 31891 31892 31893 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31799 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 02/17/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:09 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/17/97 | +------------------------------------------------+EVENT TIME: 12:47[CST]| |NRC NOTIFIED BY: GAYHEART |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARC DAPAS 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 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ON FEBRUARY 15, 1997, A SPARE BREAKER ON A SAFETY-RELATED BUS WAS FOUND IN | | THE REMOVED POSITION. | | | | WHEN THE BREAKER WAS FOUND IN THE REMOVED POSITION, IT WAS IMMEDIATELY | | RACKED TO THE DISCONNECT POSITION. AFTER FURTHER ENGINEERING EVALUATION, | | THE BREAKER WAS DETERMINED NOT TO BE SEISMICALLY QUALIFIED IN THE REMOVED | | POSITION. IT IS CURRENTLY IN THE DISCONNECT POSITION WHICH IS SEISMICALLY | | QUALIFIED. THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | * * * 1734 EST MARCH 4, 1997, UPDATE FROM ZOLAN RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. SUBSEQUENT ROOT CAUSE | | INVESTIGATION COULD NOT IDENTIFY AN ACTIVITY THAT COULD HAVE CAUSED THE | | BREAKER TO HAVE BEEN PLACED IN THE REMOVED POSITION. THEREFORE, IN | | ACCORDANCE WITH NUREG-1022 (REVISION 1, SECOND DRAFT), SECTION 3.2.2(3), | | THE POINT OF DISCOVERY FOR THE BREAKER BEING IN THE REMOVED POSITION HAS | | BEEN DETERMINED TO BE 0300 ON FEBRUARY 15, 1997. BRAIDWOOD TECHNICAL | | SPECIFICATION 3/4.8.3.1, ACTION STATEMENT 'A,' DIRECTS THAT THE BUS CAN BE | | OUT OF SERVICE (DE-ENERGIZED) FOR 8 HOURS. OTHERWISE, THIS REQUIREMENT | | DIRECTS THE LICENSEE TO PLACE THE UNIT IN AT LEAST HOT STANDBY WITHIN THE | | NEXT 6 HOURS. THE LICENSEE BELIEVES THAT THERE WAS NO BASIS FOR MAKING | | THIS REPORT BECAUSE THE BREAKER POSITION WAS IMMEDIATELY CORRECTED AND | | BECAUSE THE LICENSEE COULD NOT POSITIVELY CONCLUDE WHEN THE BREAKER WAS | | MISPOSITIONED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3D0 (WRIGHT). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31874 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/01/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 04:12 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/01/97 | +------------------------------------------------+EVENT TIME: 02:57[CST]| |NRC NOTIFIED BY: RON HARPER |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GEOFFREY WRIGHT RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REMAINING B TRAIN EMERGENCY DIESEL GENERATOR (EDG) DECLARED INOPERABLE DUE | | TO POTENTIAL COMMON MODE FAILURE. | | | | THE FOLLOWING IS TEXT FROM A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "EMERGENCY DIESEL GENERATOR G-04 (B TRAIN) HAS BEEN OUT-OF-SERVICE DUE TO A | | GENERATOR BEARING FAILURE. WITH G-04 OUT-OF-SERVICE, DIESEL GENERATOR G-03 | | ('B' TRAIN) HAS BEEN PROVIDING STANDBY EMERGENCY POWER FOR BOTH UNITS 'B' | | TRAIN BUSSES. ON 02/28/97, AT 1600 HOURS, THE DIESEL MANUFACTURER REPORTED | | THAT THE G-04 BEARING FAILURE WAS DUE TO CIRCULATING CURRENTS IN THE SHAFT | | AND WAS A POTENTIAL COMMON MODE FAILURE FOR THE SIMILAR DIESEL GENERATOR, | | G-03. DIESEL GENERATOR G-03 WAS DECLARED OUT-OF-SERVICE AS OF 1600 HOURS | | ON 02/28/97. IN ACCORDANCE WITH THE PLANT TECHNICAL SPECIFICATIONS, THE | | 'A' TRAIN DIESEL GENERATORS (G-01 FOR UNIT 1, G-02 FOR UNIT 2) MUST BE | | TESTED WITHIN 24 HOURS AND EVERY 72 HOURS THEREAFTER. G-01 AND G-02 ARE | | NOT SUSCEPTIBLE TO THE POTENTIAL COMMON MODE FAILURE. DURING THE TIME THAT | | AN 'A' TRAIN DIESEL IS UNDER TEST, NO STANDBY EMERGENCY POWER WILL BE | | AVAILABLE TO THAT UNIT. THUS, TECHNICAL SPECIFICATION 15.3.0.B IS | | CONSERVATIVELY BEING ENTERED. THIS IS BEING REPORTED IN ACCORDANCE WITH 10 | | CFR 50.72(b)(2)(i). UNIT 1 IS PRESENTLY IN HOT STANDBY. UNIT 2 IS | | DEFUELED FOR A STEAM GENERATOR REPLACEMENT OUTAGE." | | | | THE LICENSEE INTENDS TO PERFORM SURVEILLANCE RUNS ON BOTH EDGs THIS MORNING | | AND TO EXIT THE LIMITING CONDITION FOR OPERATION. THE DRIVES FOR BOTH EDGs | | ARE GMC ELECTROMOTIVE DIVISION TYPE 20-645-E4. THE GENERATOR ENDS ARE TYPE | | L-11092 MANUFACTURED BY PORTEC, INC., ELECTRIC PRODUCT DIVISION LOCATED IN | | CLEVELAND, OHIO. THE LICENSEE BELIEVED THE PROBLEM WAS RELATED TO A DESIGN | | CHANGE ON INSULATING THE GENERATOR BEARING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0203 EST ON 03/04/97, FROM RON HARPER TO S.SANDIN * * * | | | | AT 0047 CST, THE LICENSEE CONSERVATIVELY ENTERED TECHNICAL SPECIFICATION | | 15.3.0.B TO PERFORM THE EVERY 72-HOUR OPERABILITY CHECKS OF EDG G-01 | | FOLLOWED BY G-02. A MEETING IS SCHEDULED FOR DAY SHIFT TODAY TO DISCUSS | | THE FINDINGS OF THE G-03 INVESTIGATION. ALL FOUR OFFSITE SOURCES OF POWER | | ARE AVAILABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (McCORMICKBARGER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31883 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BABCOCK & WILCOX CO. |NOTIFICATION DATE: 03/04/97 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 05:25 [ET]| |COMMENTS: HEU FABRICATION & SCRAP RECOVERY |EVENT DATE: 03/04/97 | | NAVAL REACTOR FUEL |EVENT TIME: 05:10[EST]| | |LAST UPDATE DATE: 03/04/97 | | CITY: LYNCHBURG REGION: 2 +-----------------------------+ | COUNTY: CAMPBELL STATE: VA |PERSON ORGANIZATION| |LICENSE#: SNM-42 AGREEMENT: N |EDWARD MCALPINE RDO | | DOCKET: 07000027 |ROBERT PIERSON, NMSS EO | +------------------------------------------------+BOB CALDWELL FEMA | |NRC NOTIFIED BY: MARK ELLIOT |CARL PAPERIELLO NMSS | |HQ OPS OFFICER: STEVE SANDIN |JOE HIMES RCT | +------------------------------------------------+RICHARD BARRETT, IRD AEOD | |EMERGENCY CLASS: ALERT | | |10 CFR SECTION: | | | | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALERT DECLARED DUE TO A LOCAL EVACUATION FOLLOWING A CHEMICAL SPILL. | | | | AT 0510 EST, B&W NAVAL NUCLEAR FUELS DECLARED AN ALERT FOLLOWING A SPILL OF | | APPROXIMATELY 100 LITERS OF URANYL NITRATE IN THE LOW ENRICHED URANIUM DOWN | | BLENDING AREA (BAY 14A). ALL BUT 1-2 LITERS OF THE MATERIAL CONTAINING 1% | | ENRICHED URANIUM WAS CONTAINED IN A CATCH TRAY. A LOCAL EVACUATION WAS | | PERFORMED BASED ON THE TOXIC NITRIC ACID FUMES. THERE WERE NO PERSONNEL | | INJURIES. THE SPILLED MATERIAL IS IN A SAFE GEOMETRY WITH NO POTENTIAL FOR | | RELEASE OFFSITE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR WHO IS RESPONDING TO THE | | SITE. THE LICENSEE ALSO NOTIFIED CAMPBELL COUNTY EMERGENCY OPERATIONS | | CENTER, AMHERST COUNTY EMERGENCY OPERATIONS CENTER, AND THE STATE OF | | VIRGINIA. IN ADDITION TO THE INDIVIDUALS REFERENCED ABOVE, THE NRC | | OPERATIONS CENTER NOTIFIED DOE (WILLIAMS), EPA (PEKAR), USDA (GRAHAM), AND | | HHS (RABB). | | | | * * * UPDATE AT 0650 EST ON 03/04/97, FROM ELLIOT TO S.SANDIN * * * | | | | THE ALERT IS STILL ON-GOING, AND A CLEANUP OF THE SPILLED MATERIAL IS IN | | PROGRESS. AIR SAMPLES TAKEN SHOW HIGH NITROUS OXIDE LEVELS (5 ppm). THE | | LICENSEE IS INCREASING FILTERED VENTILATION TO REDUCE LEVELS BELOW THE | | 2-ppm THRESHOLD. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0935 EST ON 03/04/97, FROM ELLIOT TAKEN BY MACKINNON * * * | | | | THE ALERT WAS TERMINATED AT 0932 EST AFTER NITROUS OXIDE LEVELS RETURNED TO | | ACCEPTABLE LEVELS AND AFTER PERSONNEL WERE ALLOWED TO RE-ENTER THE | | BUILDING. THE SPILL HAS BEEN CONTAINED AND CLEANED UP, AND THE ACID SYSTEM | | HAS ALSO BEEN NEUTRALIZED. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (MCALPINE), DOE (WILLIAMS), | | FEMA (HERSKO), NMSS EO (COOL), AEOD IRD (CONGEL), EPA (EBNER), USDA | | (LEWIS), AND HHS (SNOW). THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THE | | ALERT TERMINATION BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31884 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 03/04/97 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 07:55 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 03/04/97 | +------------------------------------------------+EVENT TIME: 07:35[EST]| |NRC NOTIFIED BY: MIKE KOHL |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BOB DENNIG, NRR EO | |AFIR 50.72(b)(1)(vi) FIRE (ONSITE) |HERSKO FEMA | | |RICH BARRETT, IRD AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO A FIRE ON SITE LASTING MORE THAN TEN MINUTES. | | | | AN ELECTRICAL FIRE OCCURRED IN THE 4A (ROD DRIVE) MOTOR GENERATOR SET. THE | | 4A MOTOR GENERATOR WAS SECURED, AND THE FIRE WAS EXTINGUISHED USING CARBON | | DIOXIDE. THERE WERE NO PERSONNEL INJURIES. THE METRO DADE COUNTY FIRE | | DEPARTMENT WAS CALLED TO THE SITE BUT DID NOT PARTICIPATE IN EXTINGUISHING | | THE ELECTRICAL FIRE. THE CAUSE OF THE FIRE IS UNKNOWN AT THIS TIME, AND A | | REFLASH WATCH IS AT THE SEEN OF THE ELECTRICAL FIRE. THERE IS STILL SMOKE | | IN THE 4A MOTOR GENERATOR ROOM. THIS EVENT DOES NOT AFFECT THE OPERABILITY | | OF UNIT 4, AND ALL THE EMERGENCY CORE COOLING SYSTEMS AND EMERGENCY DIESEL | | GENERATORS ARE FULLY OPERABLE. OFFSITE POWER IS AVAILABLE, AND THE | | ELECTRICAL GRID IS STABLE. THE LICENSEE STATED THAT THE UNIT WAS NOT IN | | ANY TECHNICAL SPECIFICATION ACTION STATEMENTS BECAUSE OF THIS ELECTRICAL | | FIRE. THE UNUSUAL EVENT WAS TERMINATED AT 0800 EST. | | | | THE 4A AND 4B ROD DRIVE MOTOR GENERATOR SETS ARE ELECTRICALLY CROSS TIED SO | | WHEN THE 4A ROD DRIVE MOTOR GENERATOR SET WAS SECURED, THE 4B ROD DRIVE | | MOTOR GENERATOR SET SUPPLIED ELECTRICAL POWER TO ALL OF UNIT 4's RODS. AN | | INVESTIGATION OF WHAT CAUSED THE ELECTRICAL FIRE WILL BE PERFORMED. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS OF THIS EVENT. THE NRC | | RESIDENT INSPECTOR WAS ALSO NOTIFIED OF THIS EVENT AND WAS IN THE CONTROL | | ROOM WHEN THIS EVENT NOTIFICATION WAS MADE BY THE LICENSEE. | | | | *** UPDATE @ 0829 EST ON 03/04/97, FROM KOHL TAKEN BY MACKINNON *** | | | | THE LICENSEE REPORTED THAT SPARKS UP TO A FOOT LONG WERE SEEN COMING FROM | | THE EXCITER OF THE 4A ROD DRIVE MOTOR GENERATOR SET. FLAMES WERE NOT SEEN. | | THE ROD DRIVE MOTOR GENERATOR SETS ARE LOCATED IN THE INVERTER ROOM WHICH | | IS HOUSED IN THE CONTROL ROOM BUILDING. AT THIS TIME, THE LICENSEE | | BELIEVES THAT THERE WAS AN ELECTRICAL FAULT IN THE 4A MOTOR GENERATOR SET. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED OF THIS UPDATE BY THE | | LICENSEE. THE R2DO (MCALPINE) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31885 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 03/04/97 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 10:20 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 03/04/97 | +------------------------------------------------+EVENT TIME: 09:55[EST]| |NRC NOTIFIED BY: MICHAEL S. BECKER |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE 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 +------------------------------------------------------------------------------+ | SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FAILURE DUE TO THE LOSS OF THE | | SPDS/ERF COMPUTER SYSTEM. | | | | AT 0855 EST, THE SPDS SYSTEM FAILED DUE TO THE FAILURE OF THE TECHNICAL | | SUPPORT CENTER (TSC) SPDS/ERF COMPUTER SYSTEM. THE CAUSE OF THE FAILURE | | HAS NOT BEEN DETERMINED, AND REPAIR EFFORTS ARE UNDERWAY. AT 0955 EST, THE | | LOSS OF SPDS FOR 1 HOUR REQUIRED A 1-HOUR NOTIFICATION PER VIRGINIA POWER | | ADMINISTRATIVE PROCEDURE VPAP-2802 AND 10 CFR 50.72(b)(1)(v). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31886 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/04/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:17 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/04/97 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: MIKE RUTKOSKE |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DANIEL HOLODY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF THE SPILL OF LESS THAN ONE OUNCE OF HYDRAULIC FLUID | | FROM A DUMPSTER REMOVAL TRUCK LOCATED INSIDE THE PROTECTED AREA | | | | AT APPROXIMATELY 0900, LESS THAN ONE OUNCE OF HYDRAULIC FLUID LEAKED FROM A | | DUMPSTER REMOVAL TRUCK LOCATED INSIDE THE PROTECTED AREA. THE OIL LEAKED | | ONTO THE PAVEMENT AND ENTERED TWO STORM DRAINS. THE SPILL WAS NOTICED AS | | AN OIL SHEEN ON THE PAVEMENT. THE OIL WAS CLEANED FROM THE PAVEMENT. THE | | STORM DRAINS WERE ALSO OPENED AND CLEANED. DURING THIS PROCESS, THE | | LICENSEE VERIFIED THAT THE OIL DID NOT SPREAD TO OTHER STORM DRAINS, THE | | DISCHARGE CANAL, OR THE HUDSON RIVER. THE DRIVER OF THE TRUCK WAS NOTIFIED | | OF THE LEAK, AND THE TRUCK WAS REMOVED FROM THE SITE. | | | | THE LICENSEE NOTIFIED THE NATIONAL RESPONSE CENTER (U.S. COAST GUARD), NEW | | YORK STATE DEPARTMENT OF ENVIRONMENTAL CONSERVATION, NEW YORK STATE | | INTERSTATE SANITATION COUNCIL, WESTCHESTER DEPARTMENT OF HEALTH, AND NRC | | RESIDENT INSPECTOR. THE LICENSEE ALSO NOTIFIED ITS PUBLIC INFORMATION | | DEPARTMENT, BUT ISSUANCE OF A PRESS RELEASE IS NOT CURRENTLY PLANNED. THE | | LICENSEE EXPECTS THE U.S. COAST GUARD TO RESPOND TO THE SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31887 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 03/04/97 | |UNIT: [1] [ ] [ ] STATE: FL |NOTIFICATION TIME: 14:22 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 03/04/97 | +------------------------------------------------+EVENT TIME: 12:22[EST]| |NRC NOTIFIED BY: JAMES HURCHALLA |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR TRIP ON LOW REACTOR COOLANT SYSTEM FLOW DUE TO THE LOSS | | OF A REACTOR COOLANT PUMP | | | | AT 1222, THE 1A2 REACTOR COOLANT PUMP TRIPPED FOR UNKNOWN REASONS WHILE THE | | UNIT WAS OPERATING AT 100% REACTOR POWER, CAUSING AN AUTOMATIC REACTOR | | TRIP. ALL RODS FULLY INSERTED, AND AUXILIARY FEEDWATER INITIATED (AS | | EXPECTED) ON LOW STEAM GENERATOR LEVEL. ALL SYSTEMS FUNCTIONED AS REQUIRED | | WITH THE EXCEPTION OF THE 1B MAIN FEEDWATER REGULATING VALVE. THIS VALVE | | DID NOT AUTOMATICALLY CLOSE AS EXPECTED. THERE WERE NO EMERGENCY CORE | | COOLING SYSTEM INJECTIONS, AND THE LICENSEE STATED THAT NONE OF THE CODE | | SAFETY VALVES, PRESSURIZER POWER OPERATED RELIEF VALVES, OR SECONDARY | | SAFETY RELIEF VALVES OPENED BASED UPON INFORMATION AVAILABLE AT THE TIME OF | | THIS NOTIFICATION. | | | | THE UNIT IS CURRENTLY IN HOT STANDBY. THE 1A2 REACTOR COOLANT PUMP IS STILL | | SECURED, BUT THE REMAINING REACTOR COOLANT PUMPS ARE CURRENTLY RUNNING TO | | PROVIDE FORCED PRIMARY SYSTEM CIRCULATION. NORMAL CHARGING AND MAKEUP ARE | | BEING USED FOR PRIMARY INVENTORY CONTROL, AND ALL CONTAINMENT PARAMETERS | | ARE NORMAL. SECONDARY STEAM IS BEING BYPASSED TO THE CONDENSER, AND | | AUXILIARY FEEDWATER IS SUPPLYING WATER TO THE STEAM GENERATORS. THE | | EMERGENCY DIESEL GENERATORS, OFFSITE POWER, AND ALL EMERGENCY CORE COOLING | | SYSTEMS ARE ALSO CURRENTLY AVAILABLE. | | | | THE CAUSES OF THE 1A2 REACTOR COOLANT PUMP TRIP AND THE FAILURE OF THE 1B | | MAIN FEEDWATER REGULATING VALVE TO CLOSE ARE UNDER INVESTIGATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31888 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. ARMY (ROCK ISLAND ILLINOIS) |NOTIFICATION DATE: 03/04/97 | | CITY: FORT DRUM REGION: 1 |NOTIFICATION TIME: 14:39 [ET]| | COUNTY: FORT DRUM STATE: NY |EVENT DATE: 02/28/97 | |LICENSE#: 12-0072206 AGREEMENT: Y |EVENT TIME: 09:30[EST]| | DOCKET: |LAST UPDATE DATE: 03/04/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |DANIEL HOLODY, REG 1 RDO | | |DON COOL, NMSS EO | +------------------------------------------------+FRED COMBS, NMSS EO | |NRC NOTIFIED BY: JEFF HAVENNER |FRANK CONGEL, IRD AEOD | |HQ OPS OFFICER: LEIGH TROCINE |JIM MCCORMICKBARGER R3DO | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE2 20.2202(b)(2) EXCESSIVE RELEASE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. ARMY AT ROCK ISLAND, ILLINOIS, REPORTED THE RELEASE OF 10 CURIES | | OF TRITIUM FROM AN M1A1 COLLIMATOR LOCATED IN A PORTABLE STORAGE SHED AT | | FORT DRUM, NEW YORK. | | | | ON FEBRUARY 28, 1997, TWO INDIVIDUALS WERE PERFORMING A MAINTENANCE | | PROCEDURE ON AN M1A1 COLLIMATOR (A REFERENCE POINT FOR ARTILLERY) INSIDE A | | PORTABLE STORAGE SHED AT FORT DRUM. THE PROCEDURE INVOLVED THE PURGING OF | | MOISTURE FROM THE COLLIMATOR WITH DRY NITROGEN. APPARENTLY, THE | | FLOW/PRESSURE WAS TOO HIGH, AND THE SOURCE INSIDE THE COLLIMATOR BROKE | | RELEASING 10 CURIES OF TRITIUM INTO THE STORAGE SHED AT 0930 EST. ROCK | | ISLAND WAS NOTIFIED OF THIS EVENT AT APPROXIMATELY 1400 CST ON MARCH 3, | | 1997. | | | | THE STORAGE SHED AND VARIOUS TOOLS WERE CONTAMINATED AS A RESULT OF THE | | TRITIUM RELEASE. WIPE SAMPLES INDICATED THAT CONTAMINATION LEVELS WERE | | APPROXIMATELY 10,000 DISINTEGRATIONS PER MINUTE ON A TOOL BOX AND | | APPROXIMATELY 500,000 DISINTEGRATIONS PER MINUTE ON THE COLLIMATOR. THE | | COLLIMATOR HAS BEEN PACKAGED AND PLACED IN A RADIOACTIVE WASTE HOLDING | | AREA. THE STORAGE SHED HAS BEEN POSTED AS OFF LIMITS, AND ADDITIONAL WIPE | | TESTS ARE PLANNED. THE LICENSEE ALSO PLANS TO DECONTAMINATE THE STORAGE | | SHED. IN ADDITION, THE LOCAL RADIATION PROTECTION OFFICER WAS NOTIFIED, | | AND BIO-ASSAY SAMPLES ARE CURRENTLY BEING ANALYZED TO DETERMINE THE | | EXPOSURE LEVELS FOR THE INDIVIDUALS INVOLVED IN THE EVENT. | | | | (REFER TO THE HOO LOG FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31889 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NUTTING ENGINEERS OF FLORIDA, INC. |NOTIFICATION DATE: 03/04/97 | | CITY: BOYNTON BEACH REGION: 2 |NOTIFICATION TIME: 15:59 [ET]| | COUNTY: PALM BEACH STATE: FL |EVENT DATE: 03/04/97 | |LICENSE#: 934-1 AGREEMENT: Y |EVENT TIME: 11:45[EST]| | DOCKET: |LAST UPDATE DATE: 03/04/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS PEEBLES RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+FRANK CONGEL, IRD AEOD | |NRC NOTIFIED BY: DAVID FERGUSON | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STATE OF FLORIDA BUREAU OF RADIATION CONTROL REPORTED THE LOSS OF A | | TROXLER SOIL MOISTURE DENSITY GAUGE BETWEEN JOB SITES IN DELRAY BEACH, | | FLORIDA. THE GAUGE WAS OWNED BY NUTTING ENGINEERS OF FLORIDA, INC., | | LOCATED IN BOYNTON BEACH, FLORIDA. | | | | BETWEEN 0930 AND 1000, A TROXLER SOIL MOISTURE DENSITY GAUGE (MODEL #3411B, | | SERIAL #12482) FELL FROM A TRANSPORTATION VEHICLE BETWEEN JOB SITES IN | | DELRAY BEACH, FLORIDA. APPARENTLY, THE JOB SITES (AN OFFICE DEPOT ON | | CONGRESS AVENUE AND THE MORIKOMI ELEMENTARY SCHOOL ACROSS THE STREET FROM | | MORIKOMI PARK) WERE LOCATED CLOSE TOGETHER, AND THE GAUGE WAS NOT PROPERLY | | SECURED IN THE TRANSPORTATION VEHICLE PRIOR TO TRANSPORT. THE GAUGE WAS | | DISCOVERED TO BE MISSING AT 1145, AND THE INCIDENT WAS REPORTED TO THE | | STATE OF FLORIDA BUREAU OF RADIATION CONTROL AT 1150. A SEARCH OF THE | | TRANSPORTATION ROUTE WAS CONDUCTED, BUT THE GAUGE WAS NOT FOUND. THE | | MISSING GAUGE CONTAINED DOUBLE ENCAPSULATED SEALED SOURCES (8 MILLICURIES | | OF CESIUM-137 AND 40 MILLICURIES OF AMERICIUM-241/BERYLLIUM). | | | | THE LICENSEE PLANS TO ISSUE A PRESS RELEASE, AND THE PALM BEACH SHERIFF'S | | DEPARTMENT WAS NOTIFIED. (REFER TO THE HOO LOG FOR CONTACT NAMES, | | ADDRESSES, AND TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31890 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 03/04/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/03/97 | +------------------------------------------------+EVENT TIME: 00:00[CST]| |NRC NOTIFIED BY: PAUL WENC |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |VERNON HODGE, RVIB NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION - CRACKING OF VITEC TRANSFORMER CORES | | | | THESE TRANSFORMERS ARE INSTALLED IN VARIOUS SAFETY-RELATED CIRCUITS BOARDS. | | TEMPERATURE CHANGES IN THESE CIRCUIT BOARDS COULD CAUSE ASSOCIATED | | INSTRUMENTATION TO DRIFT OUT OF RANGE. THE SAFETY-RELATED APPLICATIONS | | WHERE THIS TRANSFORMER HAS THE MOST POTENTIAL IMPACT ARE THE DELTA | | TEMPERATURE PROTECTION FUNCTIONS (NRA CARDS) IN THE REACTOR PROTECTION | | SYSTEM (RPS). THE DRIFT IN THE RPS COULD CAUSE A CHANNEL TO TRIP RESULTING | | IN A LOSS OF REDUNDANCY IN THE DIVERSE TRIP FUNCTION. | | | | NOTE: THIS ISSUE ALSO APPLIES TO BRAIDWOOD UNITS 1 AND 2 AND TO ZION | | UNITS 1 AND 2. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31891 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/04/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 16:52 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/04/97 | +------------------------------------------------+EVENT TIME: 14:46[CST]| |NRC NOTIFIED BY: R.P. WOOD |LAST UPDATE DATE: 03/04/97 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 HOT SHUTDOWN | 0 HOT SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INABILITY TO CROSS CONNECT THE UNIT 1 AND 2 COMPONENT COOLING WATER (CCW) | | SYSTEMS DURING ROUTINE TESTING | | | | ON MARCH 4, 1997, UNIT 1 WAS IN A SHUTDOWN CONDITION WITH REACTOR COOLANT | | SYSTEM TEMPERATURE AND PRESSURE AT 380øF AND 1,108 PSIG. UNIT 2 WAS SHUT | | DOWN AND DEFUELED DURING ITS ANNUAL REFUELING OUTAGE. THE TECHNICAL | | SPECIFICATIONS AND FINAL SAFETY ANALYSIS REPORT CREDIT THE ABILITY TO CROSS | | CONNECT THE UNIT 1 AND UNIT 2 CCW SYSTEMS, AND A TEST WAS CONDUCTED TO | | PROVE THIS CAPABILITY. WHILE PERFORMING THIS TEST, "PBTP 058 STROKE CCW | | CROSS CONNECT VALVES CC-722A&B," OPERATORS FIRST OPENED AND THEN SHUT VALVE | | CC-722A (THE CCW PUMP SUCTION CROSS CONNECT VALVE). THE OPERATION OF THIS | | VALVE WAS PERFORMED SUCCESSFULLY. HOWEVER, THE CCW PUMP DISCHARGE CROSS | | CONNECT VALVE, CC-722B, COULD NOT BE OPENED. THIS RESULTED IN THE | | INABILITY TO CROSS CONNECT THE UNIT 1 AND UNIT 2 CCW SYSTEMS AND IS A | | DEGRADED CONDITION THAT RESULTS IN THE PLANT POTENTIALLY BEING IN AN | | UNANALYZED CONDITION. SINCE BOTH UNITS ARE SHUT DOWN, THIS EVENT WAS | | REPORTED IN ACCORDANCE WITH 10 CFR 50.72(b)(2)(i). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31892 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/05/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 03:20 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/04/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:30[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/05/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |WRIGHT RDO | | DOCKET: 0707001 |COOL EO | +------------------------------------------------+ | |NRC NOTIFIED BY: UNDERWOOD | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBC 76.120(c)(2)(iii) REDUNDANT EQUIP INOP | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR REPORT | | | | "DURING THE WEEKLY CRITICALITY ACCIDENT ALARM SYSTEM (CAAS) CLUSTER CHECKS | | IN THE C-337 PROCESS BUILDING, 2 OF THE 3 MODULES ON 'V' CLUSTER WERE | | DISCOVERED TO HAVE METER INDICATIONS OF 9.0 mR. A METER INDICATION LESS | | THAN 9.5 mR ON A MODULE HAS BEEN DETERMINED TO BE UNACCEPTABLE. | | ADDITIONALLY, AT LEAST 2 OF THE 3 MODULES IN A SINGLE CAAS CLUSTER MUST BE | | OPERABLE FOR THE CLUSTER TO BE OPERABLE. TSR 2.4.4.2a AND 2.4.4.2b REQUIRE | | THE CAAS TO BE OPERABLE FOR DETECTION AND AUDIBILITY, RESPECTIVELY. THE | | CAAS IS DESIGNED TO PROVIDE OVERLAPPING COVERAGE FROM ADJACENT CLUSTERS, | | HOWEVER, 'V' CLUSTER DOES NOT HAVE COMPLETE OVERLAPPING COVERAGE FROM | | ADJACENT CLUSTERS. THE LCO ACTIONS INCLUDE: DISCONTINUE CELL MAINTENANCE | | ACTIVITIES REQUIRING BREACH OF THE UF6 BOUNDARY OF CELLS CONTAINING UF6 | | ENRICHED TO ò1.0 WT% U-235, MONITOR TEMPERATURES/PRESSURES IN THE CASCADE | | CELLS CONTAINING UF6 ENRICHED ò1.0 WT% U-235, DO NOT HANDLE WASTE | | CONTAINING URANIUM ENRICHED TO ò1.0 WT% U-235, DO NOT USE WET AIR PUMPS FOR | | EVACUATION OF CELLS CONTAINING UF6 ENRICHED ò1.0 WT% U-235, MONITOR | | TEMPERATURE AND PRESSURE OF SURGE DRUMS CONTAINING UF6 ENRICHED ò1.0 WT% | | U-235, PLACE FREEZER SUBLIMERS CONTAINING UF6 ENRICHED ò1.0 WT% U-235 IN | | MODE F/S 3, F/S 4, F/S 5 OR F/S 6; EVACUATE THE AREA WITHIN THE AREA NOT | | COVERED BY DETECTION CAPABILITY, RESTRICT ACCESS TO AREA EVACUATED, PROVIDE | | PERSONNEL ALLOWED INTO THE AREA RESTRICTED WITH AN ALTERNATE MEANS OF | | CRITICALITY ALARM NOTIFICATION SUCH AS A DEVICE THAT WILL ALARM ON SENSING | | A 10 mR/HR DOSE RATE (LOSS OF DETECTION), RESTORE DETECTION BY INSTALLING A | | PORTABLE UNIT PROVIDING REQUIRED DETECTION AND ALARMS OR RESTORE CAAS | | DETECTION TO OPERABLE STATUS, AND PROVIDE PERSONNEL ALLOWED INTO THE AREA | | RESTRICTED WITH AN ALTERNATE MEANS OF CRITICALITY ALARM NOTIFICATION SUCH | | AS A DEVICE THAT WILL ALARM ON SENSING A 10 mR/HR DOSE RATE OR A RADIO IN | | CONSTANT COMMUNICATION WITH THE CENTRAL CONTROL FACILITY (LOSS OF | | AUDIBILITY ONLY). | | | | "THE FIRST SET OF DATA REQUIRED BY THE LCO WAS COMPLETED AT 1430, | | APPROXIMATELY 90 BARRICADES (CONES WITH SIGNS) WERE ESTABLISHED AT INTERIOR | | LOCATIONS OF THE BUILDING TO RESTRICT ACCESS AT 1545, BARRICADES (CONES | | WITH SIGNS) WERE ESTABLISHED AT EXTERIOR LOCATIONS TO RESTRICT ACCESS AT | | 1443 (THIS WAS LATER SUPPLEMENTED WITH A CONE AT THE SOUTH END OF THE C-337 | | EAST TRUCK ALLEY), AN ANNOUNCEMENT WAS MADE OVER THE PLANT PUBLIC ADDRESS | | AND RADIO NETWORKS AT 1450 RESTRICTING ACCESS TO PLANT PERSONNEL TO THE | | NORTHEAST AREA OF THE C-337 BUILDING. MAINTENANCE HAS REPLACED THE | | INOPERABLE MODULES AND FUNCTIONAL TESTING OF THE SYSTEM IS PLANNED FOR | | TONIGHT." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31893 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 03/05/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 05:45 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/05/97 | +------------------------------------------------+EVENT TIME: 04:24[EST]| |NRC NOTIFIED BY: D. ROLAND |LAST UPDATE DATE: 03/05/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HOLODY RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 STARTUP | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INFORMATION CALL REGARDING UNIT SHUTDOWN | | | | "SUSQUEHANNA UNIT 1 WAS MANUALLY SHUT DOWN ON 3/5/97 TO FACILITATE | | INVESTIGATION AND REPAIRS TO THE MAIN TURBINE BYPASS VALVE SYSTEM. A UNIT | | STARTUP WAS IN PROGRESS ON 3/4/97. THE REACTOR WAS CRITICAL AND PRESSURE | | WAS APPROXIMATELY 335 PSIG. WHEN ATTEMPTING TO CONTROL VESSEL PRESSURE WITH | | TURBINE BYPASS VALVES, ALL FIVE VALVES MOMENTARILY WENT WIDE OPEN. STARTUP | | ACTIVITIES WERE PLACED ON HOLD. NO IMMEDIATE CAUSE FOR THE ANOMALY COULD BE | | DETERMINED. THE DECISION WAS MADE TO SHUT THE UNIT DOWN FOR INVESTIGATION | | AND REPAIRS. | | | | "AT 0155 ON 3/5/97, A CONTROLLED SHUTDOWN WAS COMMENCED BY INSERTING | | CONTROL RODS. AT 0414, ALL RODS WERE FULLY INSERTED AND THE REACTOR | | CONFIRMED TO BE SUB-CRITICAL. AT 0424, THE REACTOR MODE SWITCH WAS TAKEN TO | | SHUTDOWN, PLACING THE PLANT IN CONDITION 3. | | | | "THERE WERE NO LEVEL OR PRESSURE PERTURBATIONS. THERE WERE NO CONTAINMENT | | ISOLATIONS, ECCS INJECTIONS, OR DIESEL GENERATOR STARTS. ALL SYSTEMS WORKED | | AS EXPECTED. | | | | "THIS EVENT DOES NOT REPRESENT A SHUTDOWN REQUIRED BY TECH SPECS. THE ESF | | ACTUATION OF THE REACTOR PROTECTION SYSTEM IS NOT REPORTABLE SINCE IT IS | | PROCEDURALLY RECOGNIZED AS PREPLANNED. | | | | "THE UNIT WILL BE TAKEN TO COLD SHUTDOWN TO FACILITATE INVESTIGATION AND | | REPAIRS. UNIT 2 WAS NOT AFFECTED BY THIS EVENT AND REMAINS IN CONDITION 1 | | AT 89% (MAXIMUM ACHIEVABLE POWER DUE TO END OF CYCLE CORE COASTDOWN)." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS NOTIFICATION BY THE | | LICENSEE. | +------------------------------------------------------------------------------+