U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/20/97 - 05/21/97 ** EVENT NUMBERS ** 31988 32345 32353 32354 32355 32356 32357 32358 32359 32360 32361 32362 32363 32364 32365 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31988 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/20/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 18:06 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/20/97 | +------------------------------------------------+EVENT TIME: 17:15[EST]| |NRC NOTIFIED BY: THOMPSON |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 28 POWER OPERATION | 28 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE TECHNICAL SPECIFICATION FOR MAXIMUM POWER LEVEL SETPOINT WITH | | INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION IS IN ERROR. | | | | THE PERCENT OF RATED THERMAL POWER LISTED IN TECHNICAL SPECIFICATION TABLE | | 3.7-1, "MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH | | INOPERABLE STEAM LINE SAFETY VALVES WHILE IN FOUR LOOP OPERATION", IS | | NON-CONSERVATIVE WHEN APPLIED TO THREE INOPERABLE MAIN STEAM SAFETY VALVES | | (MSSV) ON THE SAME LOOP. THE SUBJECT TECHNICAL SPECIFICATION ALLOWS | | CONTINUED OPERATION IN THIS CONDITION PROVIDED RATED THERMAL POWER IS | | REDUCED TO 43%. CALCULATIONS PREPARED IN SUPPORT OF AN ASSOCIATED PROPOSED | | AMENDMENT INDICATE THAT THE UNIT SHOULD BE SHUTDOWN WITH THREE MSSVs | | INOPERABLE ON THE SAME LOOP TO PREVENT OVERPRESSURIZATION OF THE MAIN STEAM | | SYSTEM. | | | | A LICENSEE EVENT REPORT WILL BE SENT TO THE NRC IN ACCORDANCE WITH | | 10CFR50.73 (a)(2)(ii). | | | | LICENSEE SAID THAT CATAWBA UNIT 1 AND 2 HAVE TECHNICAL SPECIFICATIONS WHICH | | ARE SIMILAR TO THE MCGUIRE TECHNICAL SPECIFICATIONS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1400 ON 05/20/97 BY DAVE MILLER ENTERED BY JOLLIFFE * * * | | | | FURTHER LICENSEE INVESTIGATION, INCLUDING ADDITIONAL CALCULATIONS PERFORMED | | BY LICENSEE SAFETY ANALYSIS PERSONNEL, INDICATE THAT THE VALUES LISTED IN | | TABLE 3.7-1 FOR ONE AND TWO INOPERABLE STEAM LINE SAFETY VALVES ARE ALSO | | NON-CONSERVATIVE. | | | | THE LICENSEE HAS IMPLEMENTED ADMINISTRATIVE CONTROLS TO PROHIBIT OPERATION | | OF UNITS 1 AND 2 WITH INOPERABLE MAIN STEAM SAFETY VALVES. CURRENTLY, ALL | | MAIN STEAM SAFETY VALVES FOR UNITS 1 AND 2 ARE OPERABLE. PRESENTLY, UNIT 1 | | IS AT 21% POWER AND UNIT 2 IS AT 100% POWER. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R2DO TOM DECKER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32345 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 05/17/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 03:24 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/17/97 | +------------------------------------------------+EVENT TIME: 03:15[EDT]| |NRC NOTIFIED BY: HOYLE |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SECURITY EVENT - | | | | PLANT SECURITY REPORTED UNAUTHORIZED ENTRY INTO THE PROTECTED AREA. | | IMMEDIATE COMPENSATORY MEASURES TAKEN UPON DISCOVERY. THE RESIDENT | | INSPECTOR WAS INFORMED. REFER TO HOO LOG FOR DETAILS. | | | | * * * UPDATE AT 1923 ON 05/20/97 BY DAVE BLACK ENTERED BY JOLLIFFE * * * | | | | AFTER REVIEWING THIS EVENT, THE LICENSEE DESIRES TO RETRACT THIS EVENT | | SINCE NO SECURITY VIOLATION HAD BEEN COMMITTED. REFER TO THE HOO LOG FOR | | DETAILS. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE OPERATIONS | | OFFICER NOTIFIED THE R2DO TOM DECKER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32353 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 05/20/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 02:51 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 05/19/97 | +------------------------------------------------+EVENT TIME: 22:51[CDT]| |NRC NOTIFIED BY: SCHMIDT |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 89 POWER OPERATION | 89 POWER OPERATION | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE "B" TRAIN AIR HANDLING UNIT FOR THE CONTROL ROOM HVAC SYSTEM WAS | | DECLARED INOPERABLE. | | | | DURING THE PERFORMANCE OF THE MONTHLY SURVEILLANCE ON THE "B" TRAIN OF THE | | CONTROL ROOM HVAC SYSTEM, THE AIR HANDLING UNIT POWER CIRCUIT BREAKER | | TRIPPED (CAUSE IS UNKNOWN AND BEING INVESTIGATED). THIS MADE THE EMERGENCY | | VENTILATION SYSTEM REFRIGERATION CONTROL UNIT INOPERABLE, AND PLACED UNIT 1 | | IN AN LCO ACTION STATEMENT TO RESTORE THE EQUIPMENT TO OPERABLE CONDITION | | WITHIN 30 DAYS OR BE IN AT LEAST HOT SHUTDOWN IN THE FOLLOWING 12 HRS AND | | COLD SHUTDOWN IN THE NEXT 24 HRS. UNIT 2 WILL NOT RESTART WHILE THIS | | EQUIPMENT IS INOPERABLE DUE TO COMPANY POLICY AGAINST STARTUP INTO A LCO | | ACTION STATEMENT. THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32354 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 05/20/97 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 05:23 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 03:15[CDT]| |NRC NOTIFIED BY: MATTSON |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN 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 88 POWER OPERATION | 88 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT RECEIVED AN UNEXPECTED GROUP 4 (HPCI) ISOLATION DURING HPCI LOW | | PRESSURE ISOLATION SURVEILLANCE. | | | | THE INADVERTENT ISOLATION OCCURRED WHILE CHANNEL 1 WAS IN THE TRIPPED | | POSITION, PER SURVEILLANCE PROCEDURES, AND VOLTAGE READINGS WERE BEING | | TAKEN. THE CAUSE OF THE ISOLATION IS UNKNOWN AT THIS TIME, BUT THEY ARE | | STILL INVESTIGATING. THE ISOLATION IMMEDIATELY CLEARED ITSELF. THE | | RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32355 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 05/20/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:09 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 09:45[EDT]| |NRC NOTIFIED BY: FREEMAN |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AESS 50.72(b)(1)(v) EMERGENCY SIREN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT DISCOVERED SIX EMERGENCY SIRENS FAILED TO OPERATE DURING A TEST. | | | | THESE SIRENS ARE PART OF THEIR PROMPT NOTIFICATION SYSTEM AND THE CAUSE OF | | THEIR FAILURE IS UNKNOWN. THE LICENSEE HAS A WORK CREW MAKING REPAIRS TO | | THE SIRENS. THE RESIDENT INSPECTOR WAS NOTIFIED ALONG WITH THE OCEAN | | COUNTY SHERIFF. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32356 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/20/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 11:03 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 10:10[EDT]| |NRC NOTIFIED BY: WISNIEWSKI |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED THE CONTROL ROOM VENT SYSTEM INOPERABLE. | | | | THIS WAS DETERMINED WHILE PERFORMING OP4192(CONTROL ROOM HVAC ISOLATION | | SURVEILLANCE) DAMPER AOD-113-2 FAILED THE SURVEILLANCE BY LETTING LIGHT | | PASS THROUGH WHILE IN THE CLOSED POSITION. THIS DAMPER ISOLATES OUTSIDE | | SUPPLY AIR AND COULD RESULT IN EXCESSIVE AIR IN-LEAKAGE. CONTROL ROOM | | VENTILATION IS REQUIRED TO ISOLATE PER FSAR SECTION 10.12.3.3. MAINTENANCE | | PERSONNEL ARE CLEANING AND REPAIRING THE DAMPER. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND WILL NOTIFY STATE | | OFFICIALS. | | | | * * * UPDATE AT 1125 ON 5/20/97 BY WISNIEWSKI ENTERED BY GOULD * * * | | | | AT 1110, THE DAMPER PASSED ITS SURVEILLANCE TEST. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND WILL NOTIFY STATE | | OFFICIALS. | | | | THE OPERATIONS OFFICER NOTIFIED THE R1DO LAURIE PELUSO. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32357 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: US ARMY (ROCK ISLAND, ILLINOIS) |NOTIFICATION DATE: 05/20/97 | | CITY: ROCK ISLAND REGION: 3 |NOTIFICATION TIME: 12:57 [ET]| | COUNTY: ROCK ISLAND STATE: IL |EVENT DATE: 05/20/97 | |LICENSE#: 12-00722-14 AGREEMENT: Y |EVENT TIME: 09:30[CDT]| | DOCKET: |LAST UPDATE DATE: 05/20/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRUCE JORGENSEN, R3 RDO | | | | +------------------------------------------------+GARY SANBORN, R4 RDO | |NRC NOTIFIED BY: TIM MOHS, ACALA SAFETY | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LOSS OF RADIOACTIVE MATERIAL (10 ęCi Ni-63 SOURCE) AT FORT HOOD, TEXAS - | | | | ON 03/27/97, OFFICIALS AT FORT HOOD, TEXAS, DETERMINED THAT A PORTABLE | | HAND-HELD CHEMICAL AGENT MONITOR (#Z16C12099/Z16M11976) USED TO DETECT | | CHEMICAL AGENTS IN THE FIELD WAS MISSING. THE MONITOR CONTAINS A SOLID | | 10 MILLICURIE NICKEL-63 SOURCE (LOW LEVEL BETA EMITTER). | | | | ON 04/28/97, OFFICIALS AT FORT HOOD BEGAN AN INVESTIGATION TO LOCATE THE | | MISSING MONITOR. | | | | AT 0930 (CDT) ON 05/20/97, OFFICIALS AT FORT HOOD REPORTED THE LOSS OF | | RADIOACTIVE MATERIAL TO ACALA SAFETY, ROCK ISLAND ARSENAL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32358 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 05/20/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 16:01 [ET]| |RX TYPE: [3] CE |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 12:45[CDT]| |NRC NOTIFIED BY: BILL PENDERGRASS |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -BOTH CONTROL ROOM EMERGENCY FILTRATION SYSTEM TRAINS DECLARED INOPERABLE- | | | | DURING THE PERFORMANCE OF A TECH SPEC SURVEILLANCE TEST (CONTROL ROOM | | BOUNDARY PRESSURIZATION TEST), THE LICENSEE DISCOVERED A SINGLE FAILURE | | VULNERABILITY IN THE CONTROL ROOM EMERGENCY FILTRATION (CREF) SYSTEM. | | | | FOLLOWING THE RECEIPT OF A SAFETY INJECTION ACTUATION SIGNAL OR THE | | DETECTION OF HIGH RADIATION AT THE AIR INTAKE, THE CREF SYSTEM IS DESIGNED | | TO PROVIDE FILTERED RECIRCULATED AIR WITH MAKEUP AIR FOR PRESSURIZATION | | BEING FILTERED BEFORE ENTERING THE CONTROL ROOM ENVELOPE. | | | | THE CREF SYSTEM IS DESIGNED TO ATTAIN A POSITIVE PRESSURE (0.125 INCH WG) | | WITH LESS THAT OR EQUAL TO 200 CFM OF OUTSIDE AIR WHEN OPERATING IN THE | | PRESSURIZATION MODE FOLLOWING A DESIGN BASIS EVENT. THIS PRESSURIZATION | | IS MAINTAINED BY A MODULATING RECIRCULATION DAMPER IN EACH TRAIN OF THE | | CREF SYSTEM WHICH REGULATES THE FLOW OF RECIRCULATED AIR AGAINST THE | | FLOW OF PRESSURIZATION AIR FROM OUTSIDE THE CONTROL ROOM. EACH OF THE | | RECIRCULATION DAMPERS IS DESIGNED TO FAIL OPEN. | | | | DURING THE PERFORMANCE OF THE CONTROL ROOM BOUNDARY PRESSURIZATION TEST, | | THE LICENSEE DISCOVERED THAT THE FAILURE OF EITHER RECIRCULATION DAMPER | | COULD RESULT IN THE INABILITY TO ADEQUATELY MAINTAIN THE REQUIRED | | PRESSURIZATION. | | | | ALTHOUGH AN ACTUAL FAILURE DID NOT OCCUR, THIS CONDITION IS BEING REPORTED | | TO THE NRC BECAUSE IT REASONABLY MIGHT HAVE OCCURRED. | | | | THE LICENSEE DECLARED BOTH TRAINS OF THE CREF SYSTEM INOPERABLE. | | | | TECH SPEC LCO ACTION STATEMENT 3/4.7.6.2 REQUIRES THE SUSPENSION OF ALL | | FUEL MOVEMENT WITH BOTH TRAINS OF THE CREF SYSTEM INOPERABLE; AND REQUIRES | | THE RESTORATION OF ONE INOPERABLE CREF SYSTEM TRAIN TO OPERABLE STATUS | | WITHIN 7 DAYS OR THE SUSPENSION OF ALL FUEL MOVEMENT. THE LICENSEE HAS | | SUSPENDED ALL FUEL MOVEMENT UNTIL AT LEAST ONE CREF SYSTEM TRAIN IS | | RESTORED TO OPERABLE STATUS. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32359 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION DATE: 05/20/97 | | CITY: SAN ANTONIO REGION: 4 |NOTIFICATION TIME: 16:35 [ET]| | COUNTY: STATE: TX |EVENT DATE: 05/19/97 | |LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 15:45[EDT]| | DOCKET: 03028641 |LAST UPDATE DATE: 05/20/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS DECKER, R2 RDO | | | | +------------------------------------------------+BRUCE JORGENSEN, R3 RDO | |NRC NOTIFIED BY: MAJOR JIM HICKS |GARY SANBORN, R4 RDO | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |JBDA 40.60(b)(4)(i) FIRE/EXP INVOLV LNM | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - BURNED AIRCRAFT ENGINE AND DIRT/SOIL CONTAMINATED WITH NICKEL-THORIUM - | | | | AT 1400 ON 05/15/97, THE METAL IN A SCRAP J-33 AIRCRAFT ENGINE CAUGHT ON | | FIRE FROM A BLOW TORCH IN A SCRAP METAL YARD IN PENSACOLA, FLORIDA. THE | | SCRAP DEALER DUMPED A TRUCK LOAD OF DIRT ON THE BURNING ENGINE TO SMOTHER | | THE FIRE. THE SCRAP DEALER LEFT THE DIRT ON THE ENGINE UNTIL 05/19/97 TO | | ENSURE THAT THE FIRE WAS OUT. | | | | AT 1545 ON 09/19/97, WHILE DIGGING THE ENGINE OUT OF THE DIRT, AIR FORCE | | OFFICIALS FROM WRIGHT-PATTERSON AIR FORCE BASE, DAYTON, OHIO, FOUND THE | | BURNED OUT ENGINE AND THE SURROUNDING DIRT AND SOIL TO BE CONTAMINATED | | WITH NICKEL-THORIUM CALLED "ENGINE FUSION CASE." | | | | THESE OFFICIALS COLLECTED THE CONTAMINATED ENGINE REMAINS, DIRT AND SOIL IN | | THREE 55 GALLON DRUMS AND WILL PROCESS THIS MATERIAL AS LOW LEVEL WASTE. | | | | NO PERSONNEL WERE CONTAMINATED OR INJURED. | | | | THE LICENSEE WILL SUBMIT A WRITTEN REPORT TO THE NRC WITHIN 30 DAYS. | | | | THIS EVENT WAS DISCUSSED WITH REGION 4 LINDA McLEAN. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32360 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 05/20/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 16:53 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 14:57[CDT]| |NRC NOTIFIED BY: JIM KURAS |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN 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 90 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -MANUAL REACTOR TRIP FROM 90% POWER DUE TO STEAM LEAK IN TURBINE BUILDING- | | | | THE LICENSEE DISCOVERED A STEAM LEAK IN THE TURBINE BUILDING COMING FROM | | THE THIRD STAGE EXTRACTION STEAM ISOLATION VALVE (#AF-FV-58C) TO THE #7B | | MAIN FEEDWATER HEATER. THE LICENSEE SUSPECTS A BODY-TO-BONNET LEAK BASED | | ON A VISUAL INSPECTION. CONTROL ROOM OPERATORS REDUCED POWER FROM 100% TO | | 90% TO REDUCE THE LEAK. THE LICENSEE EVACUATED THE TURBINE BUILDING. | | | | AT 1457 (CDT), CONTROL ROOM OPERATORS MANUALLY TRIPPED THE PLANT FROM | | 90% POWER. ALL CONTROL RODS INSERTED COMPLETELY. THE MAIN TURBINE TRIPPED | | AND TERMINATED THE STEAM LEAK. THE AUXILIARY FEEDWATER SYSTEM ACTUATED, | | AS EXPECTED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER. THE PLANT IS | | STABLE IN MODE 3 (HOT STANDBY). | | | | THE STEAM IN THE TURBINE BUILDING CAUSED INTERMITTENT 125 VDC NON-SAFETY | | RELATED BUS GROUND ALARMS. THERE DOES NOT APPEAR TO BE ANY EQUIPMENT | | DAMAGE AND NO PERSONNEL WERE INJURED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO ISSUE A PRESS | | RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32361 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 05/20/97 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 17:51 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 15:40[EDT]| |NRC NOTIFIED BY: JOHN DINELLI |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -PAST OPERATION OF SW VLVS COULD HAVE PLACED PLANT IN UNANALYZED CONDITION- | | | | AT 1540 ON 05/20/97, AS A RESULT OF QUESTIONS RAISED DURING AN NRC | | INSPECTION, THE LICENSEE DETERMINED THAT PAST OPERATION OF THE 18 INCH | | SERVICE WATER (SW) DISCHARGE THROTTLE VALVES #SWN-35-1 AND 2 HAD | | POTENTIALLY PLACED THE PLANT IN AN UNANALYZED CONDITION THAT COULD HAVE | | COMPROMISED PLANT SAFETY. | | | | THE POSITION OF THE DISCHARGE THROTTLE VALVES IS ADJUSTED DURING NORMAL | | OPERATION TO MAINTAIN COMPONENT COOLING WATER (CCW) TEMPERATURE WITHIN THE | | OPERATING RANGE BASED ON RIVER WATER TEMPERATURE. THE SERVICE WATER VALVES | | REMAIN IN THEIR PRE-ACCIDENT POSITION FOLLOWING THE LOCA, AND WITH THE | | VALVES IN THIS POSITION, THE ABILITY OF THE SERVICE WATER TO KEEP THE CCW | | WITHIN THE REQUIRED TEMPERATURE LIMITS FOLLOWING TRANSFER FROM THE | | INJECTION TO THE RECIRCULATION PHASE, HAS NOT BEEN ANALYZED. THE DISCHARGE | | THROTTLE VALVES ARE REPOSITIONED TO THEIR MAXIMUM OPEN POSITION IN | | ACCORDANCE WITH EMERGENCY OPERATING PROCEDURE #ES-1.3 WELL AFTER THE | | INITIATION OF RECIRCULATION. | | | | UNIT 3 IS PRESENTLY IN MODE 5 (COLD SHUTDOWN) IN A REFUELING OUTAGE. | | OPERATIONAL LIMITS WILL BE PROVIDED TO PLANT OPERATORS PRIOR TO PLANT | | STARTUP TO ENSURE THAT THE DESIGN BASIS OF THE PLANT IS MAINTAINED. | | LICENSEE EVALUATION OF THIS SCENARIO IS ONGOING. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32362 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 05/20/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 19:57 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: DENNIS MAY |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - FAILURE OF NON-SEISMIC PIPING COULD AFFECT SAFETY RELATED EQUIPMENT - | | | | DURING A LICENSEE INDIVIDUAL PROBABILISTIC EVALUATION OF EXTERNAL EVENTS | | FOR INTERNAL FLOODING, LICENSEE DESIGN ENGINEERS DETERMINED THAT THE | | FAILURE OF NON-SEISMIC PIPING WOULD AFFECT SAFETY RELATED EQUIPMENT. | | THIS DETERMINATION IS CONTRARY TO STATEMENTS CONTAINED IN THE UFSAR, | | THE 1988 PLANT FLOODING STUDY, AND/OR VARIOUS NRC CORRESPONDENCE. | | | | DOCUMENTED QUANTITATIVE ANALYSIS IS CURRENTLY NOT AVAILABLE TO DEMONSTRATE | | THAT THE PLANT CAN MEET LICENSING STATEMENTS REGARDING EQUIPMENT | | OPERABILITY FOLLOWING FLOODING RESULTING FROM FAILURE OF NON-SEISMIC | | PIPING. FURTHER FORMAL QUANTITATIVE ANALYSIS IS REQUIRED TO VERIFY THAT | | THE PLANT LICENSING BASIS IS MET. | | | | THE PIPES OF CONCERN ARE AS FOLLOWS: | | 1. THE SERVICE WATER SUPPLY LINE (#SW-10) TO THE RECIRC MOTOR-GENERATOR | | SET LUBE OIL COOLERS. PIPING OF CONCERN IS GREATER THAN 6 INCH | | DIAMETER PIPING LOCATED ABOVE REACTOR BUILDING ELEVATION 252 FEET. | | 2. THE SERVICE WATER SUPPLY LINE (#SW-33) AND RETURN LINE (SW-34) TO | | SERVICE CHILLER #SCH-2. PIPING OF CONCERN IS LOCATED ABOVE REACTOR | | BUILDING ELEVATION 252 FEET AND PIPING IN THE HVAC ROOM. | | 3. THE 4 INCH AND 6 INCH DIAMETER FIRE SYSTEM PIPING LOCATED IN THE UPPER | | RCIC ROOM. | | | | ALTHOUGH THE PIPES OF CONCERN ARE NOT SEISMIC CATEGORY I, THE LICENSEE'S | | PRELIMINARY EVALUATION CONCLUDED THAT THE PIPES WILL NOT FAIL DURING A | | DESIGN BASIS EARTHQUAKE. THE LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32363 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 05/20/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:52 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: NICK CONICELLA |LAST UPDATE DATE: 05/20/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 +------------------------------------------------------------------------------+ | -STATION SERVICE WATER PUMP AUTO STARTED WHILE BEING REMOVED FROM SERVICE- | | | | THE 'C' STATION SERVICE WATER (SSW) PUMP AUTO STARTED WHILE BEING REMOVED | | FROM SERVICE IN ACCORDANCE WITH AN APPROVED STATION OPERATING PROCEDURE. | | THE PUMP AUTO START SIGNAL ORIGINATED FROM A LOW FLOW SIGNAL ON THE 'A' SSW | | PUMP WHICH IS THE COMPANION PUMP OF THE 'C' SSW PUMP IN THE SAME SSW LOOP. | | THE LICENSEE BELIEVES THAT THE PUMP START SIGNAL WAS CAUSED BY ENTRAPPED | | AIR OR SILT IN THE FLOW INSTRUMENT SENSING LINES SINCE NO OTHER INDICATIONS | | OF AN ACTUAL LOW FLOW CONDITION EXISTED. | | | | THE PUMP AUTO START IS BEING REPORTED AS AN ESF ACTUATION BECAUSE THIS | | LOW FLOW START IS LISTED AS A START SIGNAL FOR AN ESSENTIAL AUXILIARY | | SUPPORTING SYSTEM IN THE UFSAR. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32364 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 05/21/97 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 03:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/20/97 | +------------------------------------------------+EVENT TIME: 21:31[PDT]| |NRC NOTIFIED BY: PIERCE |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SUSPECTED BLOWN POTENTIAL TRANSFORMER CIRCUIT FUSE CAUSED EMERGENCY DIESEL | | GENERATOR (EDG) TO START. | | | | VITAL BUSES F, G, AND H ARE ENERGIZED AND OPERABLE. AUXILIARY POWER IS | | OPERABLE WITH STARTUP POWER AVAILABLE AND EMERGENCY DIESEL GENERATORS 1-1 | | AND 1-3 ARE OPERABLE. | | | | WHILE RESTORING STARTUP TRANSFORMER 1-2 AND NON-VITAL 4.16KV BUS E, AN | | INADVERTENT START OF EMERGENCY DIESEL GENERATOR 1-1 OCCURRED (THE EDG RAN | | UNLOADED FOR 10 TO 15 MINUTES BEFORE IT WAS SECURED). THE START WAS CAUSED | | BY ACTUATION OF DEVICE 27HHU (STARTUP TRANSFORMER FEEDER UNDERVOLTAGE | | RELAY) WHEN THE # 10 KNIFE SWITCH (TEST CUT OUT) WAS CLOSED. CAUSE OF THE | | RELAY ACTUATION DURING BUS RESTORATION IS SUSPECTED TO BE A BLOWN POTENTIAL | | TRANSFORMER CIRCUIT FUSE ASSOCIATED WITH VITAL BUS H STARTUP FEEDER. | | TECHNICAL MAINTENANCE DEPARTMENT IS INVESTIGATING TO DETERMINE THE EXACT | | CAUSE. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32365 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/21/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 05:14 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/21/97 | +------------------------------------------------+EVENT TIME: 02:54[CDT]| |NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 05/21/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |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 1 STARTUP | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE. | | | | AT 0144 CDT WHILE OPERATING HPCI SYSTEM TO DEMONSTRATE OPERABILITY | | FOLLOWING REFUELING OUTAGE A HPCI TURBINE BEARING LOW PRESSURE ALARM WAS | | RECEIVED. THE HPCI TURBINE WAS TRIPPED IN ACCORDANCE WITH STATION OPERATING | | PROCEDURES. LOCAL OIL PRESSURE INDICATED 10 psig, THE ALARM SET POINT IS | | 5.5 psig. THE PRESSURE SWITCH WAS CAL CHECKED AND DETERMINED TO BE | | OPERATING CORRECTLY. AT 0254 CDT THE HPCI SYSTEM WAS DECLARED INOPERABLE. | | | | EARLIER IN THE SHIFT, AT 0014 CDT, THE REACTOR CORE ISOLATION COOLING | | SYSTEM WAS RUN AND DEMONSTRATED TO BE OPERABLE. BOTH LOW PRESSURE COOLANT | | INJECTION AND CORE SPRAY SUBSYSTEMS WERE VERIFIED TO BE OPERABLE. THE | | AUTOMATIC DEPRESSURIZATION SYSTEM LOGIC IS CURRENTLY BEING DEMONSTRATED TO | | BE OPERABLE. | | | | THE LICENSEE ENTERED TECHNICAL SPECIFICATION LCO ACTION STATEMENT 3.5.4.C | | AFTER HPCI WAS DECLARED INOPERABLE. THIS ACTION STATEMENT REQUIRES AN | | ORDERLY SHUTDOWN TO BE INITIATED AND REACTOR PRESSURE TO BE REDUCED TO 150 | | psig OR LESS WITHIN 24 HOURS. THE LICENSEE IS CURRENTLY MAKING EFFORT TO | | CORRECT THIS CONDITION. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+