U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/08/94 - 04/11/94 ** EVENT NUMBERS ** 26634 27053 27058 27059 27060 27061 27062 27063 27064 27065 27066 27067 27068 27069 27070 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 26634 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/18/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 19:32 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/18/94 | +------------------------------------------------+EVENT TIME: 18:45[EST]| |NRC NOTIFIED BY: CROKE |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY NICHOLSON RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED TS 3.5.D.4 REQUIRING THEM TO BE IN COLD S/D WITHIN 24 HRS | | DUE TO THE SERVICE WATER SYSTEM BEING INOPERABLE. | | | | THE SERVICE WATER SYSTEM BECAME INOPERABLE WHEN MAINTENANCE PERSONNEL | | REMOVED THE "P-7-1C" SERVICE WATER PUMP FROM ONE OF THE SERVICE WATER LINES | | SO THEY COULD REBUILD IT. AFTER THE PUMP WAS REMOVED, IT WAS DETERMINED | | THAT THEY LEFT THE PIPING IN A CONDITION THAT INVALIDATED THE SEISMIC | | ANALYSIS FOR THE SERVICE WATER SYSTEM. WITH THE PUMP REMOVED FROM THE | | PIPING, THERE IS THE POTENTIAL FOR DAMAGE TO THE OTHER THREE SERVICE WATER | | LINES AND THAT IS WHY THE SYSTEM WAS DECLARED INOPERABLE. MAINTENANCE IS IN | | THE PROCESS OF INSTALLING THE PUMP BACK IN THE LINE SO THAT THEY CAN MEET | | THE SEISMIC ANALYSIS. THEY WILL REMAIN AT 100% POWER AND WILL ONLY START | | SHUTDOWN IF THEY DO NOT HAVE THE PUMP INSTALLED WITHIN A 12 HR PERIOD. THE | | CAUSE OF THIS CONDITION WAS DUE TO MISCOMMUNICATION. THE RI WAS INFORMED | | AND THE STATE WILL BE INFORMED. | | | | ***UPDATE AT 21:11 BY CROKE TO GOULD*** THEY REINSTALLED THE "P-7-1C" | | SERVICE WATER PUMP AND EXITED THE LCO AT 21:00 | | | | ***UPDATE AT 14:10 @ 4/8/94 BY BROOKS TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT AFTER FURTHER REVIEW AFTER THE ENGINEERING DEPARTMENT | | HAD DETERMINED THAT THE SERVICE WATER SYSTEM WAS ONLY DEGRADED, BUT STILL | | OPERABLE. BY IT BEING OPERABLE, IT WAS STILL CAPABLE OF PERFORMING ITS | | DESIGNED SAFETY FUNCTION, THEREFORE, THIS WAS NOT A REPORTABLE EVENT . THE | | RI WAS INFORMED. REG 1 (PASCIAK) WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27053 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 04/07/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 11:31 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/07/94 | +------------------------------------------------+EVENT TIME: 10:47[EDT]| |NRC NOTIFIED BY: HEDMON |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: ALERT +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |GRIMES EO | | |SIMMERS FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 75 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM 25% POWER ON POWER LOW RANGE/HIGH FLUX | | SIGNAL AND A SAFETY INJECTION INITIATION ON LOW-LOW TAVG COINCIDENT WITH | | HIGH STEAM FLOW. | | | | THE LICENSEE WAS LOWERING REACTOR POWER BECAUSE OF THE LOSS OF SOME | | CIRCULATING WATER PUMPS AT THE TIME OF THE TRIP. POWER WAS LOWERED TO LESS | | THAN 10%, THUS AUTOMATICALLY INSTATING THE LOW POWER TRIP SET POINT OF 25%. | | THE LICENSEE HAS SPECULATED THAT OPERATORS BEGAN WITHDRAWING CONTROL RODS | | TO RESTORE A LOWER THAN NORMAL TAVG. POWER INCREASED TO 25%, AND A REACTOR | | TRIP WAS RECEIVED, ALL RODS FULLY INSERTED. | | | | A SAFETY INJECTION SIGNAL WAS RECEIVED BECAUSE OF A LOW LOW TAVG IN | | CONJUNCTION WITH HIGH STEAM FLOW SIGNAL. AT LEAST TWO MAIN STEAM ISOLATION | | VALVES AND TWO FEED WATER ISOLATION VALVES FAILED TO CLOSE AS REQUIRED, IN | | ADDITION, THE MAIN FEED PUMPS FAILED TO TRIP. THE SUBSEQUENT COOLDOWN OF | | THE REACTOR COOLANT SYSTEM CAUSED PRESSURIZER PRESSURE AND LEVEL TO DROP. A | | SECOND SAFETY INJECTION SIGNAL WAS RECEIVED ON LOW PRESSURIZER PRESSURE. | | | | THE PLANT WAS TAKEN SOLID BY THE HIGH HEAD SAFETY INJECTION PUMPS. THE | | POWER OPERATED RELIEF VALVES (PORVs) ON THE PRESSURIZER OPENED AND RELIEVED | | TO THE PRESSURIZER RELIEF TANK (PRT). THE BLOW OUT DISC ON THE PRT BLEW | | OUT TO PREVENT OVER PRESSURIZATION OF THE TANK. THE PRT RELIEVES TO THE | | CONTAINMENT. | | | | ***UPDATE AT 11:55 4/7/94 FROM HEDMON TO GOULD*** AT 11:26 THE "11" STEAM | | GENERATOR SAFETY VALVE LIFTED AND FULLY RESEATED. THE COOLDOWN RESULTED IN | | A DECREASE IN RCS PRESSURE. THIS WORKED IN CONJUNCTION WITH THE OVER | | FEEDING TO CAUSE THE SECOND SI SIGNAL. | | | | * * * UPDATE @ 13:53 4/7/94 FROM HEDMON TO MCGINTY * * * | | LICENSEE DECLARED A PRECAUTIONARY ALERT AT 13:16 4/7/94 TO HELP STAFF THE | | TSC IN RESPONSE TO THE ABOVE EVENT. | | | | * * * UPDATE AT 1602 EDT BY KARSCH * * * COMMISSIONER'S ASSISTANTS BRIEFING | | BRIEFER (WENSINGER) RGN 1, ATTENDEES AEOD (JORDAN & HOLAHAN), IRB | | (BROCKMAN), PA (BEECHER), SP (LOHAUS), EDO (TATUM), NRR EO (DENNIG), SECY | | (BATES), CA (MADDEN), ROGERS' (SORENSEN), SELIN'S (BAKER), REMICK'S | | (GOODMAN), DePLANQUE'S (RULAND), OTHERS NRR (DENBECK), NRR/RSB (COLLINS). | | | | THE LICENSEE HAS DRAWN A BUBBLE IN THE PRESSURIZER AND INTENDS TO LOWER | | PRESSURIZER LEVEL TO 50% AND BEGIN A NORMAL COOLDOWN TO COLD SHUTDOWN. | | | | | | ***UPDATE AT 20:31 BY GIGGETTS/OTT TO GOULD*** THE LICENSEE TERMINATED THE | | ALERT AND NOUE AT 20:20ET BASED ON PLANT COOLDOWN BEING IN PROGRESS. THEY | | ARE IN HOT STANDBY(483F AND 1500PSI). THE COOLDOWN RATE IS 25-30F/HR. THEY | | EXPECT TO BE IN MODE 4 BY MIDNIGHT. RI WAS NOTIFIED. | | | | THE FOLLOWING AGENCIES WERE NOTIFIED OF THE ALERT AND ITS TERMINATION: | | 1. DOE(VISNOSKY) | | 2. USDA(COOPER/GRAHAM) | | 3. HHS(BURGER) | | 4. FEMA(SIMMERS/CARR) | | 5. EPA(LYMON/CONKLIN) | | | | *** UPDATE DATE/TIME:4/8/94 @ 0410 BY:McGINTY *** | | AS OF 0410 EST ON 4/8/94, THE PLANT IS IN MODE 4 AT 370 psig AND 350F. | | PREPARATIONS ARE BEING MADE TO PLACE RHR ON SERVICE. THE LICENSEE | | ANTICIPATES REACHING COLD SHUTDOWN AT ABOUT NOON, TODAY. THE LICENSEE HAD | | NO NEW INFORMATION TO REPORT REGARDING THE EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27058 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/08/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:36 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 11:20[EDT]| |NRC NOTIFIED BY: BIGIARELLI |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD AN ECCS INITIATION SIGNAL DUE TO PERSONNEL ERROR DURING A | | RETEST OF A PLANT MODIFICATION. | | | | THIS OCCURRED WHILE THEY WERE PREPARING FOR RETEST OF A PLANT MODIFICATION | | WHICH REQUIRED SLEEVING OF RELAY CONTACTS THAT GIVE THE SIGNAL FOR HIGH | | DRYWELL PRESSURE FOR INITIATION OF ECCS. WHEN THEY STARTED THE TEST AND | | ACTUATED THE RELAY, THEY RECEIVED AN ECCS SIGNAL BECAUSE THE INCORRECT | | CONTACTS HAD BEEN SLEEVED. THEY RECEIVED A LPCI INITIATION SIGNAL(PUMPS | | STARTED BUT NO VALVE POSITION CHANGES OCCURRED SINCE THE VALVES WERE TAGGED | | OUT), CORE SPRAY INITIATION SIGNAL(VALVE POSITION CHANGES OCCURRED, BUT NO | | PUMPS STARTED SINCE THE PUMP BREAKERS WERE RACKED OUT) AND AUTO START | | SIGNAL TO THE GAS TURBINE, BUT IT WAS TERMINATED MANUALLY. ALL OF THESE | | SYSTEMS WERE RESET IMMEDIATELY. THE RI WILL BE INFORMED AND THE STATE AND | | LOCAL AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27059 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 04/08/94 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 12:00 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 07:58[CDT]| |NRC NOTIFIED BY: SCHUSSLER |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT ENTERED A 12 HR LCO ACTION STATEMENT TO BE IN HOT S/D DUE TO | | THEIR INABILITY TO COMPLETE MAINTENANCE WORK ON A CST LEVEL SWITCH WITHIN | | THE REQUIRED 24 HR TIME PERIOD. | | | | THIS OCCURRED WHEN THEY WERE PERFORMING MAINTENANCE ON A LEVEL SWITCH ON | | THE CONDENSATE STORAGE TANK WHICH CONTROLS THE SUCTION SOURCE FOR THE HPCI | | AND RCIC SYSTEMS. THEY WERE UNABLE TO COMPLETE THE MAINTENANCE ON THIS | | SWITCH WITHIN THE 24 HR PERIOD(ENDING AT 07:58CDT) DUE TO UNANTICIPATED | | PROBLEMS WITH REPAIRING OF THE SWITCH(A COVER PLATE HAD TO BE | | MANUFACTURED). THE SWITCH WAS FINALLY REPAIRED BY 10:47 AND THE LCO ACTION | | STATEMENT WAS EXITED. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27060 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 04/08/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: BAUER |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A PART 21 BASED ON THE PREMATURE FAILURE OF POWER | | SUPPLIES USED IN THE WESTINGHOUSE EAGLE-21 PLANT PROTECTION SYSTEM. | | | | THE POWER SUPPLIES THAT HAVE FAILED ARE MANUFACTURED BY ASTEC AMERICA AND | | ARE USED BY WESTINGHOUSE. A ROOT CAUSE INVESTIGATION CONCLUDED THAT THE | | FAILURE OF A CAPACITOR CAUSED THE LOSS OF VOLTAGE TO THE ASSOCIATED LOADS. | | THE DEFECTIVE CAPACITORS WERE SUPPLIED BY AVX TO ASTEC AMERICA OVER A | | SPECIFIC TIME PERIOD. THE CORRECTIVE ACTION OF REFURBISHING THE AFFECTED | | POWER SUPPLIES WITH NEW CAPACITORS HAS BEEN COMPLETED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27061 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 04/08/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:00 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: BAUER |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A PART 21 BASED ON THE FAILURE OF DOUGLAS-RANDALL | | TIME DELAY RELAYS USED IN THE WESTINGHOUSE EAGLE-21 PLANT PROTECTION | | SYSTEM. THE ROOT CAUSE INVESTIGATION CONCLUDED THAT THE FAILURE OF AN | | ALUMINUM ELECTROLYTIC CAPACITOR CAUSED THE FAILURE. THIS END OF LIFE | | FAILURE WAS ACCELERATED BY LOCALIZED HEATING WITHIN THE MODULE CAUSED BY A | | RESISTOR IN CLOSE PROXIMITY OF THE CAPACITOR. THE CORRECTIVE ACTION WAS TO | | RELOCATE THE RESISTOR TO THE OUTSIDE OF THE EPOXY MODULE TO SEPARATE IT | | FROM THE CAPACITOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 04/08/94 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 18:17 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 18:10[EDT]| |NRC NOTIFIED BY: TUITE |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED A CONDITION WHERE THE EXISTING VENTILATION FLOW | | USED TO MAINTAIN ENVIRONMENTAL QUALIFICATION(EQ) TEMPERATURE LIMIT DURING | | ACCIDENT CONDITIONS WAS INADEQUATE. | | | | IT WAS DETERMINED WHEN ASSUMING MAXIMUM DESIGN OUTSIDE AIR TEMPERATURE, THE | | EAST AND WEST CABLE VAULTS WOULD NOT HAVE ADEQUATE VENTILATION FLOW TO | | MAINTAIN THE EQ TEMPERATURE LIMIT DURING ACCIDENT CONDITIONS. THESE AREAS | | HOUSE EMERGENCY 480V MOTOR CONTROL CENTERS AND AC & DC DISTRIBUTION PANELS. | | USING THE CURRENT AMBIENT OUTSIDE TEMPERATURE, THE CALCULATED MAXIMUM | | TEMPERATURE REACHED AT POST ACCIDENT IN THE EAST CABLE VAULT WILL BE BELOW | | THE MAXIMUM EQ LIMIT FOR EQUIPMENT IN THE AREA. HOWEVER, PROJECTED MAXIMUM | | TEMPERATURE IN THE WEST CABLE VAULT WOULD EXCEED THE MAXIMUM EQ LIMIT. | | A VENTILATION REBALANCE IS IN PROGRESS TO RESTORE THE REQUIRED FLOW. THEY | | ARE REVIEWING TS LCO'S TO DETERMINE APPLICABILITY. THE RI WILL BE NOTIFIED. | | | | | | ***UPDATE AT 18:50 BY TUITE TO GOULD*** AT 18:15 THEY COMPLETED THE | | VENTILATION REBALANCE AND VERIFIED THAT THE WEST CABLE VAULT VENTILATION | | FLOW WAS ABOVE THE MINIMUM. THE FLOWS HAVE BEEN VERIFIED SATISFACTORY IN | | ALL AREAS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27063 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/08/94 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 21:49 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 18:30[PDT]| |NRC NOTIFIED BY: HINDS |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 2 STARTUP | 2 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS MADE A PRELIMINARY DETERMINATION THAT ELECTRICAL | | PENETRATIONS ASSOCIATED WITH THE PERSONNEL AND EMERGENCY PERSONNEL AIR | | LOCKS ARE NOT PROVIDED WITH REDUNDANT OVERCURRENT PROTECTION DEVICES. | | | | THESE ELECTRICAL PENETRATIONS SUPPLY POWER TO INSTRUMENTATION AND LIGHTING | | FOR THE AIR LOCKS. AS PER TS 3.8.4.2, THE LICENSEE IS REQUIRED TO CORRECT | | THIS CONDITION OF NOT HAVING OPERABLE OVERCURRENT PROTECTION DEVICES WITHIN | | 72 HRS OR DE-ENERGIZE THE CIRCUIT. UNTIL THEY CAN GET THE DESIGNED FUSES | | INSTALLED, THEY WILL CLEAR THESE CIRCUITS AND DE-ENERGIZE THEM. THE RI WILL | | BE INFORMED. | | | | HOO NOTE: SEE SIMILAR EVENT #27064 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27064 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/08/94 | |UNIT: [1] [ ] [ ] STATE: CA |NOTIFICATION TIME: 21:54 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/08/94 | +------------------------------------------------+EVENT TIME: 18:30[PDT]| |NRC NOTIFIED BY: HINDS |LAST UPDATE DATE: 04/08/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS MADE A PRELIMINARY DETERMINATION THAT THE ELECTRICAL | | PENETRATIONS ASSOCIATED WITH THE PERSONNEL AND EMERGENCY PERSONNEL AIR | | LOCKS ARE NOT PROVIDED WITH REDUNDANT OVERCURRENT PROTECTION DEVICES. | | | | THESE ELECTRICAL PENETRATIONS SUPPLY POWER TO INSTRUMENTATION AND LIGHTING | | FOR THE AIR LOCKS. AS PER TS THE LICENSEE CANNOT MAKE A MODE CHANGE TO MODE | | 4 UNTIL THIS CONDITION HAS BEEN CORRECTED. THEY WILL INSTALL THESE | | OVERCURRENT PROTECTION DEVICES PRIOR TO GOING TO MODE 4. THE RI WILL BE | | INFORMED. | | | | HOO NOTE: SEE EVENT #27063 | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27065 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/09/94 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 03:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/09/94 | +------------------------------------------------+EVENT TIME: 02:39[EDT]| |NRC NOTIFIED BY: ARMSTRONG |LAST UPDATE DATE: 04/09/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KERRY LANDIS 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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OPERATOR INADVERTENTLY GENERATED A FEEDWATER ISOLATION SIGNAL WHILE | | INVESTIGATING A PROBLEM WITH A RX TRIP BREAKER. | | | | UPON CLOSING OF REACTOR TRIP BREAKERS IN PREPARATION FOR A ROD DROP TEST, | | THE "B" REACTOR TRIP BREAKER FAILED TO CLOSE. DURING THE INVESTIGATION OF | | WHY THE "B" BREAKER FAILED TO CLOSE, THE ASOS (ASSISTANT SHIFT OPERATING | | SUPERVISOR) WAS SHOWING THE SOS HOW LOOSE THE REACTOR TRIP BREAKER "A" | | LATCH (BREAKER POSITION LOCKING LEVER) WAS IN COMPARISON TO THE "B" | | BREAKER'S LATCH. THE ASOS SUBSEQUENTLY MOVED THE BREAKER "A" LATCH TOO | | FAR, CAUSING THAT BREAKER TO TRIP. THIS CAUSED A FEEDWATER ISOLATION | | SIGNAL (ON RX TRIP WITH LOW Tavg OF 550F) SIGNAL TO BE GENERATED. THE | | FEEDWATER ISOLATION WAS RESET (THEY ARE IN LONG CYCLE CLEANUP), AND THE | | SYSTEM RESTORED TO NORMAL. | | | | THE LICENSEE WILL BE INVESTIGATING THE PROBLEM WITH THE RX TRIP BREAKER, | | AND INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27066 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 04/09/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 06:27 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/09/94 | +------------------------------------------------+EVENT TIME: 05:45[EDT]| |NRC NOTIFIED BY: BURKE |LAST UPDATE DATE: 04/09/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN ZWOLINSKI EO | | |EARL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HOPE CREEK DECLARED AN UNUSUAL EVENT DUE TO TRANSPORTING A CONTAMINATED, | | INJURED PERSON OFF-SITE TO THE HOSPITAL. | | | | AT 0545 EDT ON 4/9/94, AN UNUSUAL EVENT WAS DECLARED WHEN A CONTAMINATED | | INJURED WORKER WAS TRANSPORTED OFF-SITE TO THE HOSPITAL. THE INDIVIDUAL | | WAS WORKING ON THE REFUELING FLOOR, AND APPARENTLY PASSED OUT DUE TO HEAT | | EXHAUSTION. SURVEYS INDICATED 4 cpm CONTAMINATION ON THE WORKERS BODY, DUE | | TO COLLAPSING ON THE FLOOR OF THE REFUELING FLOOR. THE WORKER WAS | | TRANSPORTED OFF-SITE TO SALEM MEMORIAL HOSPITAL, AND THERE IS NO WORD YET | | ON HIS CONDITION. THE UNUSUAL EVENT WAS TERMINATED AT 0622 EDT ON 4/9/94, | | WHEN THE INDIVIDUAL REACHED THE HOSPITAL. THE LICENSEE WILL INFORM THE | | RESIDENT INSPECTOR, AND HAS INFORMED LAC TOWNSHIP AND THE STATES OF NEW | | JERSEY AND DELAWARE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27067 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: KEWAUNEE REGION: 3 |NOTIFICATION DATE: 04/09/94 | |UNIT: [1] [ ] [ ] STATE: WI |NOTIFICATION TIME: 11:22 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 04/09/94 | +------------------------------------------------+EVENT TIME: 07:00[CDT]| |NRC NOTIFIED BY: WEBB |LAST UPDATE DATE: 04/09/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ANALYSIS OF STEAM GENERATOR "A" EDDY CURRENT RESULTS, DETERMINED THAT | | ONE REGION IN STEAM GENERATOR "A" MEETS THE CRITERIA FOR CLASSIFICATION AS | | "C-3". A REGION IS CLASSIFIED AS "C-3" WHEN GREATER THAN 1% OF THE TUBES | | INSPECTED IN THAT REGION ARE DETERMINED TO BE DEFECTIVE. A DEFECTIVE TUBE | | IS ANY TUBE WITH AN INDICATION BELIEVED TO BE MORE THAN 50% THROUGH WALL. | | IN STEAM GENERATOR "A", 7 OF THE 226 (APPROXIMATELY 3.1%) UPPER SLEEVE | | EXPANSION JOINTS INSPECTED, WERE DETERMINED TO BE DEFECTIVE. NO OTHER | | REGIONS OF STEAM GENERATOR "A" HAVE BEEN CLASSIFIED AS "C-3" TO DATE, AND | | INSPECTION OF STEAM GENERATOR "B" HAS NOT COMMENCED. | | | | FOR CORRECTIVE ACTIONS; | | | | 1. THE SCOPE OF THE INSPECTION WILL BE EXPANDED TO INCLUDE THE REMAINING | | UPPER SLEEVE EXPANSION JOINTS (APPROXIMATELY 2000 MORE). | | | | 2. THE DEFECTIVE TUBES WILL BE PLUGGED. | | | | 3. AN ANALYSIS WILL BE PERFORMED TO ENSURE THAT THE PLUGGING RATE DOES NOT | | RESULT IN AN UNANALYZED CONDITION. | | | | A SCHEDULED NRC REGION III INSPECTION OF KEWAUNEE'S STEAM GENERATOR EDDY | | CURRENT METHODOLOGY AND RESULTS IS PLANNED FOR NEXT WEEK. THE DEFINITION | | FOR A DEFECTIVE TUBE IS CONTAINED IN THE TECHNICAL SPECIFICATIONS. THE | | LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27068 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 04/10/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 02:36 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 04/10/94 | +------------------------------------------------+EVENT TIME: 01:22[EDT]| |NRC NOTIFIED BY: WOOKEY |LAST UPDATE DATE: 04/10/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK 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 98 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RX SCRAM FROM 98% DURING TURBINE TESTING WHEN A HIGH LEVEL TRIP ON THE "C" | | MOISTURE SEPARATOR DRAIN TANK INITIATED A GENERATOR LOAD REJECT, AS | | DESIGNED. | | | | VERMONT YANKEE HAD REDUCED POWER SLIGHTLY (98%) TO PERFORM TURBINE TESTING. | | AFTER HAVING STROKED A COUPLE VALVES, A "C" MOISTURE SEPARATOR DRAIN TANK | | (MSDT) HIGH LEVEL TRIP OCCURRED, WHICH RESULTED IN A GENERATOR LOAD REJECT | | SCRAM. THE MSDT HIGH LEVEL TRIP RESULTED IN THE OPENING OF THE GENERATOR | | OUTPUT BREAKERS, TURBINE TRIP AND RX SCRAM, AS DESIGNED. SUBSEQUENTLY, ON | | THE RX VESSEL SHRINK, A PRIMARY CONTAINMENT ISOLATION SIGNAL (GROUPS 2, 3 | | AND 5) AND A STANDBY GAS TREATMENT SYSTEM AUTO START WERE INITIATED, AS | | EXPECTED. | | | | THE PLANT IS STABLE IN HOT SHUTDOWN, MAINTAINING PRESSURE WITH ONE BYPASS | | VALVE TO THE MAIN CONDENSER, AND FEEDING THE VESSEL WITH THE CONDENSATE AND | | FEED SYSTEM. ALL RODS FULLY INSERTED ON THE SCRAM, AND THERE WERE NO | | PROBLEMS WITH PRESSURE CONTROL AS A RESULT OF THE TRANSIENT. THERE WERE NO | | PROBLEMS WITH TRANSFERS TO OFF-SITE POWER SUPPLIES, AND ALL ECCS EQUIPMENT | | IS OPERATIONAL. THE LICENSEE WILL BE PERFORMING A THOROUGH POST-TRIP | | REVIEW, WITH A RESTART ESTIMATED AT THIS TIME IN ABOUT 24 HOURS. THE | | LICENSEE INFORMED THE RESIDENT INSPECTOR AND THE STATE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27069 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 04/10/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 13:02 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/10/94 | +------------------------------------------------+EVENT TIME: 11:45[CDT]| |NRC NOTIFIED BY: ACKERMAN |LAST UPDATE DATE: 04/10/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN ZWOLINSKI EO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL |BELCHER FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE TRANSPORTED A CONTAMINATED CONTRACT PERSONNEL TO AN OFFSITE | | MEDICAL FACILITY. | | | | THE CONTRACTOR PASSED OUT WHILE WORKING IN CONTAINMENT DUE TO HEAT | | EXHAUSTION. HE WAS TRANSPORTED TO ST JOSEPH'S MEDICAL CENTER IN JOLIET, | | ILL., ACCOMPANIED BY AN HP. THE RI WILL BE NOTIFIED. THE STATE WAS | | NOTIFIED. | | | | ***UPDATE AT 14:38 BY ACKERMAN TO GOULD*** THE PERSON WAS DE-CONTAMINATED | | (HIS RIGHT SHOULDER WAS READING 200CPM) AT THE HOSPITAL AND THE NOUE WAS | | TERMINATED AT 13:21CT. HIS CLOTHING IS BEING RETURNED TO THE SITE AND THE | | AMBULANCE AND HOSPITAL EMERGENCY ROOM WERE ALSO DE-CONTAMINATED. THE RI WAS | | INFORMED. THE RDO(BURGESS), EO(ZWOLINSKI) AND FEMA(SIMMERS) WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27070 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/10/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 17:37 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/10/94 | +------------------------------------------------+EVENT TIME: 16:13[EDT]| |NRC NOTIFIED BY: ROSS |LAST UPDATE DATE: 04/10/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WALTER PASCIAK RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN ZWOLINSKI EO | | |BAGWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE PLANT REPORTED THAT THEY HAD APPROXIMATELY A 50" DROP IN REACTOR VESSEL | | LEVEL DURING A SURVEILLANCE TEST DUE TO POSSIBLE PROCEDURE INADEQUACY. | | | | THIS OCCURRED DURING AN I&C REFUELING SURVEILLANCE(LPCI CONTAINMENT COOLING | | LOGIC TEST), WHILE THE "B" TRAIN OF LPCI WAS CROSS TIED TO SHUTDOWN | | COOLING. DURING THE PERFORMANCE OF THIS TEST, THE "A" TRAIN OF CONTAINMENT | | SPRAY VALVES WERE OPENED. THE CROSS TIE BETWEEN THE "A" & "B" LPCI TRAINS | | WAS ALSO OPENED. THIS CREATED A FLOW PATH FROM THE REACTOR VESSEL THROUGH | | SHUTDOWN COOLING, THROUGH "B" LPCI TO "A" LPCI CONTAINMENT SPRAYS. AFTER | | THIS LINEUP WAS MADE, THE OPERATOR NOTICED THAT THE REACTOR VESSEL LEVEL | | HAD GONE FROM 80" TO 20", AT THAT POINT THEY SECURED TESTING IMMEDIATELY. | | THIS CONDITION APPEARS TO HAVE BEEN CAUSED BY A PROCEDURE INADEQUACY AND | | THEY ARE INVESTIGATING WHAT CHANGES SHOULD BE MADE PRIOR TO CONTINUATION OF | | THE SURVEILLANCE. THE NOUE WAS DECLARED BECAUSE THEY FELT THAT ADDITIONAL | | PLANT AWARENESS WAS NEEDED. THE VESSEL LEVEL WAS RETURNED TO 80" AFTER THE | | TERMINATION OF THE TEST. THE RI, STATE AND LOCAL AGENCIES HAVE BEEN | | NOTIFIED. | | | | ***UPDATE AT 18:23 BY BERRY TO GOULD*** THE NOUE WAS TERMINATED AT 18:13 | | SINCE THEY WERE OUT OF AN INCREASED AWARENESS CONDITION. | | | | ***UPDATE AT 20:12 BY KENNEDY TO GOULD*** A QUESTION WAS ASKED ON THE | | ACTUAL WATER LEVEL REACHED AND ON THIS FOLLOWUP IT WAS STATED THAT IT WENT | | FROM 82" TO 6"(APPROX. 14,000 GAL.). | +------------------------------------------------------------------------------+