U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/29/95 - 06/30/95 ** EVENT NUMBERS ** 28977 28997 28999 29000 29001 29002 29003 29004 29005 29006 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28977 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 06/22/95 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 14:33 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 06/22/95 | +------------------------------------------------+EVENT TIME: 10:30[MST]| |NRC NOTIFIED BY: BRAD EKLUND |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IF A SAFE SHUTDOWN EARTHQUAKE HAD OCCURRED BETWEEN JULY 17, 1992, AND APRIL | | 28, 1994, A FAILURE OF NON-SEISMIC RADIATION MONITORS COULD HAVE PREVENTED | | THE FULFILLMENT OF THE SAFETY FUNCTION OF ESSENTIAL COOLING WATER. | | | | THE LICENSEE DISCOVERED THAT IF A SAFE SHUTDOWN EARTHQUAKE HAD OCCURRED | | BETWEEN JULY 17, 1992, AND APRIL 28, 1994, A FAILURE OF NON-SEISMIC | | RADIATION MONITORS COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY | | FUNCTION OF THE ESSENTIAL COOLING WATER SYSTEM. THIS CONDITION WAS | | PREVIOUSLY IDENTIFIED, BUT IT WAS DETERMINED AT THAT TIME THAT IT DID NOT | | AFFECT THE OPERABILITY OF THE ESSENTIAL COOLING WATER SYSTEM. HOWEVER, THE | | RADIATION MONITORS HAVE BEEN ISOLATED SINCE APRIL 28, 1994, AS A | | CONSERVATIVE MEASURE. ON JUNE 14, 1995, DURING THE PERFORMANCE OF | | ADDITIONAL EVALUATIONS TO UPGRADE THE RADIATION MONITORS TO SEISMIC | | REQUIREMENTS, THE LICENSEE'S ENGINEERING PERSONNEL DETERMINED THAT THE | | ESSENTIAL COOLING WATER RADIATION MONITORS WERE NOT CAPABLE OF WITHSTANDING | | A SAFE SHUTDOWN EARTHQUAKE. THE LICENSEE EVALUATED THIS CONDITION FOR | | REPORTABILITY AND DETERMINED IT TO BE REPORTABLE ON JUNE 22, 1995. | | | | THE ESSENTIAL COOLING WATER RADIATION MONITORS ARE LOCATED IN LINES | | APPROXIMATELY ONE-INCH IN DIAMETER WHICH GO FROM THE SUCTION SIDE OF THE | | PUMP TO THE DISCHARGE SIDE OF THE PUMP. THE LICENSEE'S EVALUATION | | DETERMINED THAT THERE WAS NOT ENOUGH SEISMIC SUPPORT FOR THESE LINES AND | | THAT IF ONE OF THESE LINES WOULD HAVE BROKEN DURING A SAFE SHUTDOWN | | EARTHQUAKE (WHILE THE LINE WAS NOT ISOLATED AND DEPENDING ON THE SIZE OF A | | POTENTIAL LINE BREAK), SURGE TANK LEVEL COULD HAVE DECREASED LOW ENOUGH SO | | THAT IT COULD HAVE AFFECTED ESSENTIAL COOLING WATER PUMP OPERATIONS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | | | | *** UPDATE @ 1848 EDT ON 6/29/95 **FROM LICENSEE: EKLUND BY:McGINTY *** | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON THE FOLLOWING: | | | | STRESS ANALYSES USING THE ME-101 AND STRUDL COMPUTER CODES WERE CONDUCTED | | TO DETERMINE THE INTEGRITY OF THE PIPING/TUBING. INDIVIDUAL CASES WERE | | WERE RUN TO ACCOUNT FOR UNIT UNIQUE DIFFERENCES. THE ALLOWABLE STRESS FOR | | THE TUBING MATERIAL WAS CALCULATED FROM THE MATERIAL TEST RESULTS FOR THE | | TUBING AND TAKEN AS 25 PERCENT OF TENSILE STRENGTH WHICH IS CONSISTENT WITH | | ALLOWABLE STRESS USED BY ASME FOR THAT MATERIAL. THE RESULTS SHOW THAT THE | | MAXIMUM STRESS IN ANY SERVICE LEVEL IS LESS THAN 40 PERCENT OF THE | | ALLOWABLE. THE RESULTING STRESSES ON ALL PIPE SUPPORTS ARE LESS THAN 60 | | PERCENT OF THE ALLOWABLE AND ARE STILL WITHIN THE ORIGINAL DESIGN LOADS. | | | | BASED ON THE STRESS AND STRUCTURAL ANALYSES CONDUCTED, THE RADIATION | | MONITORS AND THE ASSOCIATED TUBING AND PIPING IN THEIR EXISTING CONDITION | | WOULD HAVE RETAINED THEIR PRESSURE BOUNDARY INTEGRITY DURING AND AFTER A | | POSTULATED SAFE SHUTDOWN EARTHQUAKE. THEREFORE, THE REPORTED CONDITION ON | | 6/22/95 WOULD NOT HAVE IMPACTED THE ESSENTIAL COOLING WATER SYSTEM FROM | | PERFORMING ITS INTENDED SAFETY FUNCTION AND IS HEREBY RETRACTED. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. HOO NOTIFIED THE R4DO | | (SANBORN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28997 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 06/28/95 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 14:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/28/95 | +------------------------------------------------+EVENT TIME: 13:50[EDT]| |NRC NOTIFIED BY: DENNIS MCCORKEL |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUNO URYC RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |BOB DENNIG EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |JOHN DAMICO FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT - ALL SITE EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE | | | | ALL SITE EMERGENCY DIESEL GENERATORS (EDG) WERE DECLARED INOPERABLE BASED | | ON A DESIGN FLAW IN THEIR TURBOCHARGERS. EACH UNIT HAS TWO EDGs. THE '2B' | | EDG IS TAGGED OUT AND UNAVAILABLE (THE TURBOCHARGER FAILED ON THIS EDG), | | THE OTHER THREE EDGs ARE AVAILABLE. ALL OTHER SAFETY SYSTEMS AND OFFSITE | | POWER SOURCES ARE OPERABLE. | | | | THE UNUSUAL EVENT WAS DECLARED AT 1350. THE LICENSEE ENTERED TECH SPEC | | 3.0.3 AT THE SAME TIME. BOTH UNITS MUST BE IN MODE 3 WITHIN 7 HOURS OF | | DECLARATION (2050) AND MODE 5 WITHIN AN ADDITIONAL 30 HOURS. | | | | THE EDGs WERE MANUFACTURED BY NORDBERG, AND THE TURBOCHARGERS WERE MADE BY | | ABB. THE INVESTIGATION IS FOCUSING ON A DESIGN FLAW THAT INCREASES THE | | TURBULENCE OF THE INTAKE AIR STREAM IN THE TURBOCHARGER. | | | | THE LICENSEE NOTIFIED APPROPRIATE STATE AND LOCAL OFFICIALS AS WELL AS THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1850 ON 6/28/95 BY MCCORKEL TAKEN BY WEAVER * * * | | UNIT 1 IS IN MODE 3. ENFORCEMENT DISCRETION HAS BEEN GRANTED FOR UNIT 2. | | THE LICENSEE HAS 34 HOURS TO COMPLETE THE REPAIRS ON THE '2B' EDG. UPON | | COMPLETION OF REPAIRS TO THE '2B' EDG, THE LICENSEE WILL BE IN A 72-HOUR | | LCO WITH ONLY THE '2A' EDG INOPERABLE ON UNIT 2. THE POWER DESCENT ON UNIT | | 2 WAS STOPPED AT 30%. POWER WILL BE INCREASED TO 45% ON UNIT 2 AND HELD | | THERE. | | | | THE HOO NOTIFIED THE RDO (URYC) AND EO (SPESSARD). | | | | * * * UPDATE ON 0751 EDT FROM SARRATT TAKEN BY KARSCH * * * | | THE LICENSEE TERMINATED THE UNUSUAL EVENT FOR UNIT 2 AT 0740 EDT BY | | RETURNING THE "2B" EDG TO OPERABILITY. A NEW DESIGN DIFFUSER PLATE WAS | | INSTALLED IN THE TURBOCHARGER TO BLANK OFF THE TURBULENCE. THE | | DISCRETIONARY ENFORCEMENT HAS BEEN TERMINATED. UNIT 2 IS IN A 72-HOUR LCO | | WHICH STARTED AT 1350 EDT 6/28/95, FOR THE "2A" EDG. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. R2DO (URYC), NRR EO (DENNIG), AND FEMA | | (WITSBERGER) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28999 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 06/29/95 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 12:01 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 10:30[EDT]| |NRC NOTIFIED BY: RUSSELL |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 98 POWER OPERATION | 98 POWER OPERATION | | 2 | N Y 99 POWER OPERATION | 99 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TENNESSEE DEPARTMENT OF ENVIRONMENT AND CONSERVATION NOTIFIED OF A FISH | | KILL. | | | | AT 1030 EST ON 6/29/95, THE TENNESSEE DEPARTMENT OF ENVIRONMENT AND | | CONSERVATION (DIVISION OF WATER POLLUTION CONTROL) WAS NOTIFIED THAT 34 | | FISH WERE DEAD IN SEQUOYAH'S DIFFUSER POND AS A RESULT OF OPERATIONS AT | | SEQUOYAH NUCLEAR PLANT. OPERATIONS IN PROGRESS INVOLVE UNIT 1's COOLING | | TOWER BEING IN SERVICE IN A CLOSED/HELPER MODE DIVERTING A PORTION OF THE | | PLANT DISCHARGE BACK TO THE FORE BAY. THE TOWER WAS PLACED IN SERVICE AS A | | RESULT OF LOW DISSOLVED OXYGEN IN THE DIFFUSER POND AND THUS A CONCERN FOR | | THE FISH IN THE DIFFUSER POND/RIVER. THE RESULTING CONSEQUENCE HAS BEEN AN | | INCREASE IN THE FORE BAY AND DIFFUSER POND TEMPERATURES AND THE DEATH OF | | THE FISH. DIFFUSER POND TEMPERATURE IS 110øF. SEQUOYAH IS IN COMPLIANCE | | WITH ITS NPDES PERMIT. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29000 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 06/29/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:35 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 10:54[EDT]| |NRC NOTIFIED BY: ALLEN |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A REACTOR BUILDING VENTILATION ISOLATION WHICH | | OCCURRED DURING SURVEILLANCE TESTING. | | | | DURING THE PERFORMANCE OF A SURVEILLANCE TEST (RX BUILDING EXHAUST RAD | | MONITOR INSTRUMENT LOGIC SYSTEM FUNCTIONAL AND SIMULATED AUTOMATIC | | ACTUATION TEST), THE 'A' RX BUILDING EXHAUST RAD MONITOR SPIKED OFF-SCALE | | WHEN I&C CONNECTED A SIGNAL GENERATOR INTO THE TEST PORT. THIS CAUSED A | | VALID 'A' SIDE RX BUILDING ISOLATION THAT WAS NOT PLANNED FOR UNTIL THE | | NEXT STEP OF THE TEST. | | | | THE PROCEDURE INSERTS THE SIGNAL GENERATOR INTO THE TEST PORT, DIALS IT | | DOWN SO THE TRIP WILL NOT OCCUR, AND THEN DIALS IT UP TO INITIATE THE TRIP | | AND VERIFY THE SETPOINT AND THE ISOLATIONS. I&C PERSONNEL BELIEVE THAT | | JUST THE ACT OF PLUGGING IN THE SIGNAL GENERATOR CAN CAUSE AN ELECTRONIC | | NOISE SIGNAL (REGARDLESS OF THE POTENTIOMETER SETPOINT) AND CAUSE THE TRIP | | TO OCCUR. ALL INDICATIONS SHOW THAT THE TRIP OCCURRED AT THE DESIRED | | SETPOINT, AND ALL ISOLATIONS OCCURRED AS REQUIRED. THE LICENSEE IS | | REPORTING THE ACTUATION BECAUSE IT OCCURRED UPON CONNECTING THE SIGNAL | | GENERATOR (VICE WHEN THE SIGNAL WAS DIALED UP ON THE GENERATOR AS DESIRED). | | | | THE LICENSEE IS INVESTIGATING THE CAUSE AND CORRECTIVE ACTION. THE | | PROCEDURE WILL BE CHANGED TO ENSURE THE SIGNAL GENERATOR IS OFF PRIOR TO | | CONNECTING IT AND DIALED DOWN PRIOR TO ENERGIZING IT. THE LICENSEE WILL | | INFORM THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29001 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 06/29/95 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:15 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 15:54[EDT]| |NRC NOTIFIED BY: KRITZER |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES 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 +------------------------------------------------------------------------------+ | ANALYSIS OF A GE SIL ON LOSS OF GENERATOR STATOR COOLING REVEALED THAT FUEL | | DESIGN LIMITS MAY BE EXCEEDED ON A LOSS OF STATOR COOLING. | | | | THE LICENSEE HAS COMPLETED AN ANALYSIS OF GE SIL 581 (JULY 21, 1994), WHICH | | DEALT WITH THE LOSS OF GENERATOR STATOR COOLING. THE ANALYSIS CONCLUDED | | THAT WITH VERMONT YANKEE OPERATING AT 100% POWER WITH SOME OF THE FUEL | | NODES OPERATING AT THE LINEAR HEAT GENERATION RATE (LHGR) LIMIT OF 14.4 | | kw/ft, A FUEL DESIGN (THERMAL OVERPOWER) LIMIT COULD POSSIBLY BE EXCEEDED | | UPON A LOSS OF STATOR COOLING EVENT. | | | | THE LHGR LIMIT OF 14.4 kw/ft CORRESPONDS TO A MAXIMUM FRACTION OF LIMITING | | POWER DENSITY (MFLPD) OF 1.0 AT VERMONT YANKEE. THE LICENSEE WILL BE | | ADMINISTRATIVELY CONTROLLING THE THERMAL LIMITS AND REDUCING THE FUEL | | OPERATING LIMITS FOR MFLPD, MAXIMUM FRACTION OF LIMITING AVERAGE PLANAR | | LINEAR HEAT GENERATION RATE (MAPRAT), AND LHGR TO 97% OF THE CURRENTLY | | ALLOWED VALUES. WITH THESE CORRECTIVE ACTIONS IN PLACE, VERMONT YANKEE | | WOULD NOT EXCEED ANY FUEL DESIGN LIMITS IN THE EVENT OF A LOSS OF STATOR | | COOLING EVENT. THE LICENSEE WILL BE FURTHER INVESTIGATING THIS MATTER. THE | | LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 29002 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: BUREAU OF INDIAN AFFAIRS |NOTIFICATION DATE: 06/29/95 | | CITY: ALBUQUERQUE REGION: 4 |NOTIFICATION TIME: 18:12 [ET]| | COUNTY: STATE: NM |EVENT DATE: 06/29/95 | |LICENSE#: 30-15065-01 AGREEMENT: Y |EVENT TIME: 16:11[MDT]| | DOCKET: |LAST UPDATE DATE: 06/29/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GARY SANBORN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: RALPH TAPIA | | |HQ OPS OFFICER: TIM McGINTY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PICKUP TRUCK CONTAINING A TROXLER GAUGE WAS STOLEN. | | | | MR. RALPH TAPIA, OF THE DEPARTMENT OF THE INTERIOR, BUREAU OF INDIAN | | AFFAIRS (ROADS BRANCH), LOCATED IN ALBUQUERQUE, NM, REPORTED A STOLEN | | TROXLER MOISTURE DENSITY GAUGE. | | | | MR. TAPIA WAS PERFORMING AN INVENTORY TODAY AND DETERMINED THAT A PICKUP | | TRUCK CONTAINING A TROXLER MOISTURE DENSITY GAUGE HAD BEEN STOLEN ABOUT TWO | | WEEKS AGO. THE LICENSEE REPORTED THE EVENT TO THE OPERATIONS CENTER | | IMMEDIATELY UPON DISCOVERY. THE MISSING TROXLER GAUGE (MODEL 3411B) THAT | | WAS IN THE STOLEN TRUCK IS UNDER THE JURISDICTION OF THE IRRIGATION BRANCH | | AND DID NOT COME TO HIS ATTENTION UNTIL TODAY. | | | | THE LICENSEE CALLED SOON AFTER DISCOVERY AND DID NOT HAVE INFORMATION | | IMMEDIATELY AVAILABLE REGARDING THE TROXLER SOURCES OR THE INVESTIGATION | | INTO THE STOLEN TRUCK/GAUGE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29003 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 06/29/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 19:37 [ET]| |RX TYPE: [1] CE |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 18:40[EDT]| |NRC NOTIFIED BY: WILLOUGHBY |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES RDO | |DSAF 73.71(b)(1) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFEGUARDS SYSTEMS DEGRADATION RELATED AREA BOUNDARY. | | | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN UPON DISCOVERY. THE LICENSEE | | WILL INFORM THE RESIDENT INSPECTOR AND THE STATE. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29004 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 06/29/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 21:27 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 19:49[EDT]| |NRC NOTIFIED BY: VINCHKOSKI |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT BORES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 3 | M/R Y 12 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP INITIATED FROM 12% POWER WHEN THE SPEED OF THE | | OPERATING MAIN BOILER FEED PUMP DECREASED. | | | | UNIT 3 WAS IN THE PROCESS OF A PLANT STARTUP WITH REACTOR POWER AT 12% AND | | TURBINE LOAD AT APPROXIMATELY 50 MW WHEN THE SINGLE IN-SERVICE (#32) MAIN | | BOILER FEED PUMP (MFP) DECREASED IN SPEED AND THE CORRESPONDING FEEDWATER | | FLOW. THE #32 MFP DID NOT RESPOND TO THE EFFORTS OF THE OPERATORS TO | | INCREASE SPEED. THE #31 MFP WAS OUT OF SERVICE AT THE TIME FOR | | MAINTENANCE. BOTH MFP's ARE STEAM DRIVEN AT INDIAN POINT 3. STEAM | | GENERATOR WATER LEVELS DECREASED, AND CONTROL ROOM OPERATORS INITIATED A | | MANUAL REACTOR TRIP WHEN STEAM GENERATOR LEVELS WERE APPROXIMATELY 15%. (AN | | AUTOMATIC LOW STEAM GENERATOR LEVEL RX TRIP OCCURS AT 8%.) | | | | ALL RODS FULLY INSERTED INTO THE CORE IN RESPONSE TO THE MANUAL RX TRIP. | | CURRENTLY, AUX FEEDWATER IS BEING USED TO FEED THE STEAM GENERATORS AS | | REQUIRED. (DUE TO THE EXTENDED SHUTDOWN, THERE IS NOT MUCH DECAY HEAT.) | | THE PLANT IS BEING MAINTAINED AT NO-LOAD Tavg AND NORMAL PRESSURE. THE 4 | | BUSES THAT INDIAN POINT 3 NORMALLY USES OFF OF THE MAIN GENERATOR TO POWER | | IN-HOUSE LOADS TRANSFERRED TO OFF-SITE POWER SUPPLIES PROPERLY. THE ECCSs | | AND EDGs ARE AVAILABLE AND OPERATIONAL. | | | | THE LICENSEE WILL BE INVESTIGATING THE CAUSE OF THE SPEED DECREASE ON THE | | #32 MFP. THE LICENSEE INTENDS TO RESTORE THE #31 MFP TO SERVICE AND TO | | STARTUP TOMORROW CONTINUING WITH THE SCHEDULED STARTUP TESTING WHILE THE | | PROBLEM WITH THE #32 MFP IS BEING INVESTIGATED. THE LICENSEE INFORMED THE | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29005 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 06/29/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 22:06 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 16:30[CDT]| |NRC NOTIFIED BY: KOLB |LAST UPDATE DATE: 06/29/95 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RHR SHUTDOWN COOLING INJECTION VALVE ON THE 'A' LOOP TRIPPED WHEN SHUTDOWN | | COOLING WAS INITIATED. | | | | QUAD CITIES UNIT 2 IS IN A REFUELING OUTAGE AND IN THE PROCESS OF | | TENSIONING THE HEAD BOLTS FOR A SCHEDULED JULY 7th RESTART. THE 'B' LOOP | | OF RHR SHUTDOWN COOLING WAS UNAVAILABLE DUE TO THE 'MO2-1001-5B' (RHR | | SERVICE WATER FLOW TO HEAT EXCHANGER DISCHARGE) VALVE BEING OUT OF SERVICE | | FOR MAINTENANCE. WHILE ATTEMPTING TO PLACE THE 'A' LOOP OF RHR IN THE | | SHUTDOWN COOLING MODE, THE 'MO2-1001-29A' ('A' LOOP RHR INJECTION VALVE TO | | THE REACTOR VESSEL) VALVE BREAKER TRIPPED. WHILE INVESTIGATING, IT WAS | | DETERMINED THAT THE '29A' VALVE ON THE 'A' LOOP WAS INOPERABLE WHICH | | PREVENTED RHR SHUTDOWN COOLING FROM BEING INITIATED. | | | | AT 2028 CDT, THE LICENSEE DETERMINED THE REPORTABILITY OF THIS EVENT, AND | | OPERATORS WERE SENT OUT TO MANUALLY INITIATE SHUTDOWN COOLING BY PERFORMING | | A RETURN TO SERVICE ON THE '5B' VALVE ON THE 'B' LOOP. AT 2055 CDT, THE | | 'B' LOOP OF RHR WAS SUCCESSFULLY PLACED IN THE SHUTDOWN COOLING MODE. | | | | DURING THE ENTIRE EVOLUTION, REACTOR WATER TEMPERATURE WAS MAINTAINED AT | | 120øF WITH THE REACTOR WATER CLEANUP (RWCU) SYSTEM. REACTOR WATER | | TEMPERATURE HAD INCREASED ONLY 10øF DURING THE DAY WITH ONLY RWCU IN | | SERVICE. THE LICENSEE WAS STARTING RHR IN THE SHUTDOWN COOLING MODE ON THE | | 'A' LOOP IN AN EFFORT TO MAINTAIN A 110-120øF TEMPERATURE BAND FOR THE | | COMFORT OF THE PERSONNEL TENSIONING THE BOLTS ON THE VESSEL HEAD. THE | | LICENSEE HAS NOTIFIED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29006 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 06/30/95 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 00:31 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 06/29/95 | +------------------------------------------------+EVENT TIME: 20:16[CDT]| |NRC NOTIFIED BY: DOM LOGALBO |LAST UPDATE DATE: 06/30/95 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ 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 | 0 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N N 0 | 0 | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN EMERGENCY EQUIPMENT COOLING WATER (EECW) PUMP STARTED UNEXPECTEDLY | | DURING AN RHR SYSTEM SURVEILLANCE TEST. | | | | DURING PERFORMANCE OF 0-SI-4.2.B-67 (RHR SERVICE WATER INITIATION LOGIC), | | AN UNEXPECTED AUTO START OF B1 EECW PUMP OCCURRED. AS PART OF THE TEST, | | JUMPERS WERE PUT IN PLACE TO PREVENT EECW PUMPS A3, B1, C1, AND D3 FROM | | AUTO STARTING ON LOW RAW COOLING WATER (RCW) SYSTEM PRESSURE. WHEN RCW | | SYSTEM PRESSURE WAS LOWERED IN A SUBSEQUENT STEP TO TEST THE INITIATION | | LOGIC, PUMP B1 UNEXPECTEDLY AUTOMATICALLY STARTED. | | | | TESTING HAS BEEN SUSPENDED PENDING INVESTIGATION OF THE CAUSES OF THIS | | EVENT. THE JUMPERS SEEM TO BE CORRECTLY INSTALLED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+