U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/03/95 - 03/06/95 ** EVENT NUMBERS ** 28470 28471 28472 28473 28474 28475 28476 28477 28478 28479 28480 28481 28482 28483 28484 28485 28486 28487 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28470 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 2 |NOTIFICATION DATE: 03/03/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 08:17 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 03/03/95 | +------------------------------------------------+EVENT TIME: 04:15[CST]| |NRC NOTIFIED BY: CLARK STAFFORD |LAST UPDATE DATE: 03/03/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM CLINE 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 REACTOR WATER CLEANUP SYSTEM ISOLATED ON A HIGH DELTA FLOW SIGNAL | | | | WHILE BACK WASHING THE BRAVO RWCU FILTER SYSTEM AN OPERATOR NOTICED STEAM | | ISSUING FROM THE PRECOAT TANK. A SHORT TIME LATER AN RWCU ISOLATION | | OCCURRED ON HIGH DELTA FLOW. THIS STOPPED THE STEAM LEAK. THE SET POINT | | FOR HIGH DELTA FLOW IS 79 GPM. NORMAL RWCU SYSTEM FLOW IS 460 GPM. | | | | THE RWCU SYSTEM IS CURRENTLY ISOLATED WHILE THE LICENSEE INVESTIGATES THE | | PROBLEM AND DETERMINES A COURSE OF ACTION. THE MOST LIKELY CAUSE | | IDENTIFIED IS A LEAKING ISOLATION VALVE IN THE FILTER SYSTEM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28471 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/03/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 11:12 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/03/95 | +------------------------------------------------+EVENT TIME: 09:15[CST]| |NRC NOTIFIED BY: MIKE DEBOARD |LAST UPDATE DATE: 03/03/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GREATER THAN 1% OF THE INSPECTED TUBES ON THE 1A S/G ARE DEFECTIVE | | | | ON FEBRUARY 23, 1995, A S/G TUBE INSERVICE INSPECTION WAS INITIATED ON | | UNIT 1. THE INITIAL SAMPLE SIZE OF 100% OF ALL AVAILABLE TUBES WAS | | SELECTED. ON MARCH 3, 1995, AT 0915 THE RESULTS OF THE SAMPLE INSPECTION | | RESULTED IN S/G 1A BEING CLASSIFIED INTO CATEGORY C-3 BASED ON 256 OF THE | | 4335 INSERVICE TUBES BEING DEFECTIVE. MOST OF THESE DEFECTIVE TUBES ARE | | DUE TO INDICATIONS AT THE HOT LEG TUBE SUPPORT PLATE REGIONS. | | | | SEE RELATED EVENTS # 28466 & 28476. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28472 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 03/03/95 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:42 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 03/03/95 | +------------------------------------------------+EVENT TIME: 12:35[EST]| |NRC NOTIFIED BY: R ALEJANDRO |LAST UPDATE DATE: 03/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PROCESS COMPUTER AND SAFETY PARAMETER DISPLAY SYSTEM (SPDS) OUT OF SERVICE | | > 4 HOURS FOR PLANNED MAINTENANCE. | | | | THE PROCESS COMPUTER AND THE SPDS WERE TAKEN OUT OF SERVICE FOR PLANNED | | MAINTENANCE AT 0835EST AND HAS BEEN OUT OF SERVICE FOR > THAN 4 HOURS. | | TOTAL ESTIMATED OUTAGE TIME IS 8 HOURS. IF THE OUTAGE TIME IS GREATER THAN | | 8 HOURS LICENSEE WILL ENTER TECH SPEC 6.2.2. (INCREASED PLANT MANNING). | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28473 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/03/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 15:55 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/03/95 | +------------------------------------------------+EVENT TIME: 14:30[CST]| |NRC NOTIFIED BY: STEFAN |LAST UPDATE DATE: 03/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCCORMICKBARGER RDO | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FLOOR DRAIN PIPING FROM THE AUXILIARY FEEDWATER (AFW) TUNNEL TO THE TENDON | | TUNNEL SUMP IS NOT BUILT AS PER DESIGN. | | | | BRAIDWOOD UNIT 1 ON 02/22/95 DISCOVERED THAT THEIR FLOOR DRAIN PIPING PER | | DESIGN COULD AFFECT OPERABILITY OF THEIR AFW SYSTEM AND REPORTED THIS EVENT | | (# 28424) TO THE OPERATION CENTER ON 02/22/95. UNIT 2 STARTED INVESTIGATING | | TO SEE IF THEY HAD THIS SAME PROBLEM AND FOUND THAT THEY HAD A DIFFERENT | | PROBLEM. THE FLOOR DRAIN PIPING FROM THE AFW TUNNEL TO THE TENDON SUMP WAS | | FOUND TO NOT BE BUILT AS PER DESIGN. THE FLOOR DRAIN LINE SHOULD HAVE CHECK | | VALVES INSTALLED TO PREVENT BACKFLOW IN THE EVENT OF A FLOOD. THE CHECK | | VALVES ARE NOT PRESENT. THIS COULD POTENTIALLY RENDER THE TWO AUXILIARY | | FEEDWATER CONTAINMENT ISOLATION VALVES 13A THROUGH 13H INOPERABLE. | | CORRECTIVE ACTION: LICENSEE HAS INSTALLED FLOOR DRAIN PLUGS IN THE MAIN | | STEAM TUNNEL FLOOR DRAIN (MAIN STEAM TUNNEL IS LOCATED ABOVE THE AUXILIARY | | FEEDWATER TUNNEL) AND ALL THE DRAINS LEADING TO THE SUMP. LICENSEE REMOVED | | THE SUMP COVER TO PREVENT SUMP PRESSURIZATION IN THE EVENT OF A FLOODING | | CONDITION. THIS PROBLEM DOES NOT AFFECT THE OPERABILITY OF THEIR MOTOR | | DRIVEN AUXILIARY FEEDWATER PUMP AND THEIR DIESEL DRIVEN AUXILIARY FEEDWATER | | PUMP. | | BRAIDWOOD UNIT 1 MIGHT NOT HAVE CHECK VALVES IN THE ABOVE MENTIONED SYSTEM. | | BRAIDWOOD UNIT 1 IS INVESTIGATING THIS POTENTIAL PROBLEM. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28474 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/03/95 | |UNIT: [1] [2] [3] STATE: AZ |NOTIFICATION TIME: 16:29 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/03/95 | +------------------------------------------------+EVENT TIME: 13:35[MST]| |NRC NOTIFIED BY: B EKLAND |LAST UPDATE DATE: 03/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 N 0 REFUELING | 0 REFUELING | | 3 | N Y 86 POWER OPERATION | 86 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATIONS ARE POTENTIALLY INADEQUATE IN MODE 3 | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE. | | | | "A CONDITION HAS BEEN IDENTIFIED THAT HAS THE POTENTIAL TO PLACE ALL THREE | | UNITS IN AN UNANALYZED CONDITION. AT THIS TIME NONE OF THE UNITS ARE IN | | THIS CONDITION, HOWEVER, THE UNITS HAVE BEEN IN THIS CONDITION IN THE PAST. | | THE CONDITION AFFECTS THE ADEQUACY OF THE TEMPERATURE DEPENDENT SHUTDOWN | | MARGIN TECHNICAL SPECIFICATION WITH RESPECT TO A STEAM LINE BREAK EVENT. | | SPECIFICALLY, IN MODE 3, WITH PRESSURIZER PRESSURE BELOW 1837 psia, ONLY | | ONE HIGH PRESSURE SAFETY INJECTION (HPSI) PUMP IS REQUIRED TO BE OPERABLE. | | IN ADDITION, THE SIAS SETPOINT IS ALLOWED TO BE ADJUSTED TO WITHIN 400 psi | | OF THE CURRENT PRESSURIZER PRESSURE DURING MODE 3 COOLDOWN. | | THE CURRENT CALCULATION DETERMINED THAT IF THE SIAS SETPOINT IS BELOW | | SATURATION PRESSURE FOR THE CORRESPONDING REACTOR VESSEL UPPER HEAD | | TEMPERATURE, A VOID COULD FORM IN THE UPPER HEAD DURING POST STEAM BREAK | | DEPRESSURIZATION. THIS COULD SLOW DOWN THE RATE OF DEPRESSURIZATION SUCH | | THAT SIAS WILL NOT OCCUR IN TIME TO PROVIDE ADEQUATE BORATION. ALSO, IF A | | SINGLE FAILURE OF ONE HPSI PUMP IS ASSUMED IN THE ANALYSIS, THIS WILL MEAN | | NEITHER HPSI TRAIN WILL BE AVAILABLE (AUTOMATICALLY) FOR EVENT MITIGATION. | | THE CALCULATION CONCLUDED THAT FROM A PROBABILISTIC PERSPECTIVE, IT IS | | UNLIKELY THAT A STEAM LINE BREAK WILL OCCUR IN MODE 3 WITH T COLD GREATER | | THAN 500 DEGREES F WITH ONLY ONE OPERABLE HPSI PUMP, AND THAT THERE WAS NO | | SIGNIFICANT RISK IN LEAVING THE TECHNICAL SPECIFICATION UNCHANGED, HOWEVER, | | THIS CONCLUSION DOES NOT PRESERVE THE ASSUMPTIONS USED IN THE CALCULATION. | | | | ADMINISTRATIVE CONTROLS HAVE BEEN ESTABLISHED TO COUNTER PENDING FURTHER | | EVALUATION. 1) ADMINISTRATIVELY APPLY LCO 3.5.2 DURING ANY MODE 3 | | OPERATION, AS OPPOSED TO ONLY MODE 3 GREATER THAN 1837 psia, 2) ENSURE | | PRESSURIZER PRESSURE IS MAINTAINED AT 1700 psia OR GREATER ANY TIME IN MODE | | 3 WITH T COLD ABOVE 500 DEGREES F. | | | | FURTHER INVESTIGATION RAISED AN ADDITIONAL CONCERN THAT TECHNICAL | | SPECIFICATION 3.1.1.1 (POWER DEPENDENT INSERTION LIMIT) MAY NOT PRESERVE | | ADEQUATE SHUTDOWN MARGIN OF A UNIT IS IN MODE 3, ALL RODS IN, AND A STEAM | | LINE BREAK OCCURS. | | | | AS AN IMMEDIATE CORRECTIVE ACTION, THE OPERABILITY REQUIREMENT OF TECHNICAL | | SPECIFICATION 3.1.1.2 (SHUTDOWN MARGIN IN MODES 3 THROUGH 5) WILL BE | | APPLIED FOR ANY UNIT IN MODE 3. THIS ADMINISTRATIVE CONTROL BOUNDS THIS | | CONDITION PENDING FURTHER EVALUATION. IF NECESSARY, A TECHNICAL | | SPECIFICATION CHANGE WILL BE SUBMITTED." | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28475 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/03/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 18:44 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/03/95 | +------------------------------------------------+EVENT TIME: 18:37[EST]| |NRC NOTIFIED BY: SUDIGALA |LAST UPDATE DATE: 03/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SEISMIC EVENT COULD CAUSE LOSS OF VENTILATION COOLING TO 480 VOLT AND 4160 | | VOLT SWITCHGEAR ROOMS. | | | | ENGINEERING WAS REVIEWING SYSTEM DIAGRAMS WHEN THEY NOTICED THAT THE SMOKE | | DETECTORS LOCATED IN THE 480 VOLT SWITCHGEAR ROOMS AND THE 4160 VOLT | | SWITCHGEAR ROOMS WERE NOT SEISMICALLY QUALIFIED. IF A SEISMIC EVENT | | OCCURRED THIS COULD CAUSE THE LOSS OF THE SMOKE DETECTORS WHICH WOULD THEN | | CAUSE THE LOSS OF VENTILATION COOLING TO THE SWITCHGEAR ROOMS. LOSS OF | | COOLING TO THE SWITCHGEAR ROOMS COULD CAUSE LOSS OF VITAL AND NON VITAL 480 | | VOLT AND 4160 VOLT POWER SUPPLIES. EMERGENCY DIESEL GENERATORS WOULD NOT BE | | AFFECTED BY THIS SCENARIO. LICENSEE IS INVESTIGATING WHAT CORRECTIVE | | ACTIONS HAVE TO BE TAKEN TO CORRECT THIS PROBLEM. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28476 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 03/03/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 21:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/03/95 | +------------------------------------------------+EVENT TIME: 19:45[CST]| |NRC NOTIFIED BY: STEFAN |LAST UPDATE DATE: 03/03/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCCORMICKBARGER RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | GREATER THAN 1% OF THE INSPECTED TUBES ON 1D STEAM GENERATOR (S/G) ARE | | DEFECTIVE. | | | | ON FEBRUARY 23, 1995, A S/G TUBE INSERVICE INSPECTION WAS INITIATED ON UNIT | | 1. THE INITIAL SAMPLE SIZE OF 100% OF ALL AVAILABLE TUBES WAS SELECTED. ON | | MARCH 3, 1995, AT 1945 THE RESULTS OF THE SAMPLE INSPECTION RESULTED IN S/G | | 1D BEING CLASSIFIED INTO CATEGORY C-3 BASED ON 190 OF THE 4407 INSERVICE | | TUBES BEING DEFECTIVE. MOST OF THESE DEFECTIVE TUBES ARE DUE TO INDICATIONS | | AT THE HOT LEG TUBE SUPPORT REGIONS. | | | | SEE RELATED EVENT # 28466 & # 28471. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28477 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/04/95 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 10:09 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 07:56[CST]| |NRC NOTIFIED BY: MICHAEL ROSSEAU |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 1 STARTUP | 1 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE 'B' TRAIN SAFEGUARD COMPONENTS WERE DECLARED INOPERABLE DUE TO A BLOWN | | FUSE IN THE 125 VOLT DC CONTROL POWER. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | "ON MARCH 4, 1995 IT WAS DISCOVERED THAT THE 'B' TRAIN SAFEGUARDS SYSTEM DC | | CONTROL POWER INDICATING LAMP WAS BURNED OUT. AT 07:56 (CT) WHILE | | ATTEMPTING TO REPLACE THE LAMP IT SHORTED AND BLEW A 10 AMPERE FUSE IN THE | | 125 VOLT DC CONTROL POWER CIRCUIT. THIS DISABLED THE AUTOMATIC ACTUATION | | OF THE 'B' TRAIN SAFEGUARDS COMPONENTS. TECHNICAL SPECIFICATION 15.3.0 WAS | | ENTERED AT 07:56 REQUIRING THE UNIT TO BE IN HOT SHUTDOWN WITHIN 3 HOURS. | | EFFORTS ARE UNDERWAY TO REPLACE THE BULB. FURTHER NOTIFICATION WILL BE | | MADE WHEN REPAIRS ARE MADE AND IF SHUTDOWN IS REQUIRED." END OF TEXT. | | | | AT THE TIME OF THE PROBLEM THE UNIT WAS IN A NORMAL STARTUP, WITH THE | | REACTOR CRITICAL AND AT THE POINT OF ADDING HEAT. THE 'A' TRAIN ECCS AND | | ALL EDGs ARE OPERABLE. THE 'B' TRAIN ECCS ARE AVAILABLE ALTHOUGH THEY | | WOULD NOT AUTOMATICALLY ACTUATE ON AN ESF SIGNAL. IF THE LICENSEE HAS TO | | ENTER HOT SHUTDOWN CONDITIONS BECAUSE OF THE PROBLEM THEY MUST DECLARE AN | | UNUSUAL EVENT PER THEIR EMERGENCY PLAN. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE THE PROBLEM AND CORRECTIVE | | ACTIONS. THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1058 3/4/95 FROM ROSSEAU TAKEN BY SEBROSKY * * * | | THE UNIT EXITED THE LCO AT 09:35 CT WHEN THE SOCKET AND FUSE WERE REPLACED | | FOR THE 'B' TRAIN 125 VOLT DC CONTROL POWER CIRCUIT. THE BULB HAS BEEN | | REMOVED AND IS NOT NEEDED FOR THE SYSTEM TO BE CONSIDERED OPERABLE. HOO | | NOTIFIED R3DO(MCCORMICKBARGER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28478 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 03/04/95 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 11:16 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 07:20[CST]| |NRC NOTIFIED BY: WAYNE BENTLY |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM MCCORMICKBARGER 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO MAIN STEAM LINE DRAIN VALVES FAILED THEIR LOCAL LEAK RATE TEST. | | | | TWO MAIN STEAM DRAIN VALVES (MOV-4423 AND MOV-4424) FAILED THEIR LOCAL LEAK | | RATE TEST. THE ALLOWABLE LEAKAGE IS 3000 STANDARD CUBIC CENTIMETERS PER | | MINUTE (SCCM). ONE VALVE LEAKED AT 7000 SCCM AND THE OTHER VALVE LEAKED AT | | 14,000 SCCM. THE VALVES ARE IN SERIES AND ARE USED TO EQUALIZE AROUND THE | | MSIVS AND ALSO TO PROVIDE A DRAIN PATH TO THE MAIN CONDENSER. | | | | THE LICENSEE WILL REPAIR THE VALVES. THE LICENSEE HAS BEEN PERFORMING LOCAL | | LEAK RATE TESTS AND THIS IS THE FIRST OCCURRENCE WHERE TWO VALVES IN SERIES | | FAILED THEIR LOCAL LEAK RATE TEST. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28479 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 03/04/95 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 16:52 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 15:58[EST]| |NRC NOTIFIED BY: LEWIS |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE INJECTION (HPCI) DECLARED INOPERABLE DURING PERFORMANCE | | OF HPCI QUARTERLY PUMP & VALVE FLOW SURVEILLANCE TEST. | | | | DURING PERFORMANCE OF HPCI QUARTERLY PUMP & VALVE FLOW SURVEILLANCE TEST | | HPCI PUMP DIFFERENTIAL PRESSURE FAILED TO FALL INTO ITS ACCEPTABLE RANGE | | (1246psid - 1259psid). HPCI PUMP DIFFERENTIAL PRESSURE WAS 1272psid. | | LICENSEE DECLARED HPCI INOPERABLE AND ENTERED TECH SPEC 3.5.C.i (7 DAYS TO | | GET HPCI BACK OR SHUTDOWN). REACTOR CORE ISOLATION COOLING PUMP (RCIC) AND | | ALL OTHER EMERGENCY CORE COOLING SYSTEMS ARE FULLY OPERABLE. THE ELECTRICAL | | GRID IS STABLE AND THEIR EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE. | | LICENSEE THINKS THAT HPCI PUMP DISCHARGE PRESSURE GAGE IS OUT OF | | CALIBRATION. LICENSEE IS HAVING THE GAGE RECALIBRATED. AFTER THE GAGE IS | | RECALIBRATED LICENSEE WILL REPERFORM THE HPCI PUMP DIFFERENTIAL PRESSURE | | PART OF THE SURVEILLANCE TEST PROCEDURE. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28480 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 03/04/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 17:49 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 17:08[EST]| |NRC NOTIFIED BY: BERGIN |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IT HAS BEEN DETERMINED THAT THIS EVENT REPORT SHOULD HAVE BEEN REPORTED TO | | THE OPERATIONS CENTER ON APRIL 9, 1994. | | | | LAST 04/09/94 LICENSEE THOUGHT THAT THEY HAD FOUND A SITUATION WHERE THE | | HEAT LOADS PLACED ON REACTOR BUILDING CLOSED COOLING WATER SYSTEM (RBCCW) | | MIGHT EXCEED ITS DESIGN HEAT REMOVAL CAPACITY DURING THE SUMP RECIRCULATION | | PHASE AFTER A DESIGN BASES ACCIDENT. AT THAT TIME LICENSEE DETERMINED THAT | | THE ABOVE MENTIONED FINDING WAS NOT REPORTABLE. A REVIEW OF THE ABOVE | | PROBLEM PERFORMED BY THE LICENSEE ON 03/04/95 HAS DETERMINED THAT THEY | | SHOULD HAVE MADE AN EVENT NOTIFICATION CALL TO THE NRC OPERATIONS CENTER | | CONCERNING EXCEEDING THE DESIGN HEAT LOAD OF THEIR RBCCW DURING THE SUMP | | RECIRCULATION PHASE OF OPERATION AFTER A DESIGN BASES LOSS OF COOLANT | | ACCIDENT (LOCA). | | | | AFTER A DESIGN BASIS LOCA THE SOURCE OF COOLING WATER TO THE REACTOR | | COOLING SYSTEM (RCS) IS THE REFUELING WATER STORAGE TANK (RWST). WHEN RWST | | WATER LEVEL DECREASES DOWN TO 9.5% THE PLANT ENTERS THE SUMP RECIRCULATION | | MODE OF OPERATION. DURING THE SUMP RECIRCULATION MODE OF OPERATION THE | | MAXIMUM HEAT LOAD IS PLACED ON THE RBCCW SYSTEM (BECAUSE THE RBCCW SYSTEM | | REMOVES HEAT FROM THE SHUTDOWN COOLING HEAT EXCHANGERS). LICENSEE FOUND | | THAT THEIR ABNORMAL OPERATING PROCEDURES AND THAT THEIR EMERGENCY OPERATING | | PROCEDURES DID NOT ISOLATE NON-ESSENTIAL HEAT LOADS TO THE RBCCW SYSTEMS | | DURING THE SUMP RECIRCULATION MODE OF OPERATION (SHOULD ISOLATE REACTOR | | COOLANT PUMP HEAT LOADS AND REACTOR VESSEL SUPPORT COOLING LOADS). BY NOT | | ISOLATING THESE LOADS LICENSEE BACK ON 04/09/94 THOUGHT THAT THE RBCCW | | SYSTEM WOULD NOT BE ABLE TO REMOVE ENOUGH HEAT FROM THE SHUTDOWN COOLING | | HEAT EXCHANGERS AFTER A DESIGN BASES LOCA TO PROTECT THE INTEGRITY OF THE | | PLANT. THEREFORE THIS SITUATION SHOULD HAVE BEEN REPORTED TO THE OPERATIONS | | CENTER ON 04/09/94. | | | | SUBSEQUENT TO 04/09/94 AN ANALYSIS WAS PERFORMED BY THE LICENSEE THAT | | DETERMINED THAT THEIR RBCCW SYSTEM WOULD NOT EXCEED ITS DESIGN HEAT REMOVAL | | CAPACITY UNDER CERTAIN CONDITIONS. THE CONDITIONS ARE THAT THE REACTOR | | COOLANT PUMP & REACTOR VESSEL SUPPORT COOLING LOADS ARE NOT ISOLATED AFTER | | A DESIGN BASES ACCIDENT AND THE REACTOR PLANT IS IN THE SUMP RECIRCULATION | | MODE OF OPERATION. THEREFORE LICENSEE DID NOT CHANGE THEIR ABNORMAL AND | | EMERGENCY OPERATING PROCEDURES (ISOLATE NON ESSENTIAL COOLING LOADS). | | | | LICENSEE SAID THEY THINK THAT DURING THIS REFUELING OUTAGE THEY WILL | | PERFORM A FULL FLOW TEST OF THEIR RBCCW SYSTEM TO PROVE THAT IT CAN HANDLE | | ESSENTIAL AND NON ESSENTIAL HEAT LOADS AFTER A DESIGN BASES ACCIDENT WHEN | | THE SHUTDOWN HEAT EXCHANGERS ARE USED TO REMOVE RCS HEAT DURING THE SUMP | | RECIRCULATION MODE OF OPERATION. LICENSEE NOTIFIED STATE AND LOCAL | | OFFICIALS OF THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28481 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 03/04/95 | |UNIT: [ ] [3] [ ] STATE: NY |NOTIFICATION TIME: 18:53 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 15:17[EST]| |NRC NOTIFIED BY: FROEBRICH |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 +------------------------------------------------------------------------------+ | HIGH HEAD SAFETY INJECTION FLOW MAY BE OUTSIDE OF ITS DESIGN LIMITS. | | | | ENGINEERING IDENTIFIED A CONDITION THAT MAY HAVE PLACED THE PLANT IN AN | | UNANALYZED CONDITION. A HIGH HEAD SAFETY INJECTION FLOW BALANCE TEST WAS | | COMPLETED DURING THE 1992 REFUELING OUTAGE. A REVIEW OF THE POST TEST | | CALIBRATION CHECKS REVEALED THAT SEVERAL OF THE DIFFERENTIAL PRESSURE | | CELLS, UTILIZED DURING THE TEST, WERE OUTSIDE OF THE REQUIRED 0.25% FULL | | SCALE ACCURACY, AND THIS MAY HAVE RESULTED IN THE HIGH HEAD SAFETY | | INJECTION FLOW BEING OUTSIDE THE PLANT DESIGN CRITERIA. PRIOR TO | | ESTABLISHING SAFETY INJECTION SYSTEM OPERABILITY, ENGINEERING WILL COMPLETE | | THE VERIFICATION TESTING AND PERFORM ANY NECESSARY CORRECTIVE ACTIONS TO | | ENSURE THE FLOW BALANCE IS WITHIN THE PLANT DESIGN CRITERIA AND SAFETY | | INJECTION PUMP OPERATING LIMITS. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28482 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 03/04/95 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 19:10 [ET]| |RX TYPE: [1] CE |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 16:15[EST]| |NRC NOTIFIED BY: MCDOUGOLD |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CIRCUMFERENTIAL CRACK (360 DEGREES) FOUND ON ONE STEAM GENERATOR TUBE IN | | STEAM GENERATOR # 2. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE. | | | | "DURING EDDY CURRENT TESTING OF STEAM GENERATOR #2, ONE TUBE WAS FOUND TO | | HAVE A CIRCUMFERENTIAL CRACK (360 DEGREES) THAT HAS AN AVERAGE THROUGH WALL | | OF 83%. AN AGREEMENT WAS MADE BETWEEN MAINE YANKEES AND THE NRC FOLLOWING | | THE 1994 STEAM GENERATOR OUTAGE THAT ANY ONE TUBE, EXCEEDING 79% THROUGH | | WALL FOR A CIRCUMFERENTIAL CRACK, WAS A SIGNIFICANT DEGRADATION TO A | | PRINCIPAL SAFETY BARRIER. THE CRACK WAS FOUND IN THE EXPANSION AREA BY THE | | TUBE SHEET WHICH HAD BEEN IDENTIFIED AS A PROBLEM AREA IN THE 1994 OUTAGE. | | SINCE THIS EVENT WAS FOUND WHILE THE REACTOR IS SHUTDOWN, IT IS REPORTABLE | | BY 10CFR50.72 (b) (2) (i). | | | | THE NRC IS SCHEDULED TO ARRIVE ON SITE WEDNESDAY, MARCH 8, 1995 BASED ON AN | | INVITATION BY MAINE YANKEE TO OBSERVE THE ON-GOING EDDY CURRENT TESTING OF | | 100% TUBES IN ALL THREE STEAM GENERATORS. IT SHOULD BE NOTED THAT EVEN | | THOUGH THESE TEST RESULTS ARE CONSIDERED ACCURATE, THEY ARE PRELIMINARY | | RESULTS AND EXPEDIENCY IS BEING USED FOR REPORTING PURPOSES. ADDITIONAL | | INFORMATION WILL BE SENT TO THE NRC VIA AN LER, AS REQUIRED BY 10CFR50.73 | | (a) (20 (ii), AND VIA THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT, | | AS REQUIRED BY OUR TECHNICAL SPECIFICATIONS. | | | | THE RESIDENT NRC INSPECTOR HAS BEEN INFORMED OF THIS DEFECTIVE TUBE AND | | THIS NOTIFICATION." | | | | LICENSEE HAS NOT COMPLETED EDDY CURRENT TESTING OF STEAM GENERATOR # 2. | | LICENSEE STILL HAS TO LOOK AT STEAM GRANTORS # 1 & # 3. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28483 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/04/95 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 19:49 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 18:03[CST]| |NRC NOTIFIED BY: DAVID MCNEILL |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LEAKING SERVICE WATER FLUME VALVE (CV-3824) COULD CAUSE EMERGENCY COOLING | | POND TO PROVIDE ONLY 10 DAYS OF COOLING SUPPLY TO THE PLANT INSTEAD OF 30 | | DAY COOLING WATER SUPPLY AS SPECIFIED IN THEIR UPDATED SAFETY ANALYSIS | | REPORT. | | | | WHILE PERFORMING MAINTENANCE ON THEIR SERVICE WATER SYSTEM THEY DISCOVERED | | THAT THEIR SERVICE WATER RETURN VALVE TO THE FLUME (CV-3824) HAD AN | | EXCESSIVE LEAK RATE. ENGINEERING DETERMINED THAT THE LEAKAGE RATE FROM THE | | SERVICE WATER RETURN VALVE TO THE FLUME WOULD ONLY PROVIDE 10 DAYS OF | | COOLING WATER TO UNIT 1 INSTEAD OF 30 DAYS OF COOLING WATER SUPPLY AS | | SPECIFIED IN THEIR UPDATED SAFETY ANALYSIS REPORT. THE VALVE HAS BEEN | | ISOLATED AND LICENSEE IS REPLACING THE SEAT OF THE VALVE. THIS VALVE BEING | | OUT OF SERVICE DOES NOT AFFECT UNIT 2 OPERATION. | | | | UNIT 1 & 2 DURING NORMAL OPERATION AND EMERGENCY OPERATION WOULD USE LAKE | | DARDANELLE FOR THEIR COOLING WATER SUPPLY BUT IF THE SOURCE OF WATER WAS | | LOST FROM LAKE DARDANELLE LICENSEE WOULD HAVE TO USE THEIR EMERGENCY | | COOLING POND WATER SUPPLY. | | | | UNIT 1 IS DEFUELED AT THIS TIME. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28484 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/04/95 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 19:49 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 18:03[CST]| |NRC NOTIFIED BY: WAYNE AHO |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | IF UNIT 2 HAD NEEDED TO USE THE EMERGENCY COOLING POND AT THE SAME TIME | | THAT UNIT 1 HAD TO USE THE EMERGENCY COOLING WATER POND THEN UPDATED SAFETY | | ANALYSIS REPORT REQUIREMENTS FOR A 30 DAY SUPPLY OF COOLING WATER TO UNIT 2 | | WOULD NOT HAVE BEEN MET DUE TO A LEAKING FLUME VALVE. | | | | SEE EVENT # 28484 FOR BACKGROUND INFORMATION. | | | | UNIT 1 SERVICE WATER RETURN TO FLUME VALVE (CV-3824) WOULD HAVE REDUCED | | INVENTORY ON THE EMERGENCY COOLING WATER POND AT A RATE FASTER THAN ASSUMED | | IN THE UPDATED SAFETY ANALYSIS REPORT. IF UNIT 1 CONTINUED TO USE THE | | EMERGENCY COOLING POND THE EMERGENCY COOLING POND WOULD HAVE BEEN | | UNAVAILABLE FOR UNIT 2 DUE TO LEAKAGE PAST CV-3824. UNIT 2 IS PRESENTLY | | NOT AFFECTED AT THIS TIME. | | UNIT 2 HAS A SEPARATE SERVICE WATER RETURN TO FLUME VALVE TO THE EMERGENCY | | COOLING POND AND SINCE UNIT 1 SERVICE WATER RETURN TO FLUME VALVE IS | | ISOLATED UNIT 2 IS NOT AFFECTED. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28485 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 03/04/95 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 23:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/04/95 | +------------------------------------------------+EVENT TIME: 22:25[EST]| |NRC NOTIFIED BY: MIKE GWIRTZ |LAST UPDATE DATE: 03/04/95 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO RELEASE OF AMMONIA EXCEEDING LIMITS. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "A NOTIFICATION WAS MADE TO THE NEW JERSEY DEPARTMENT OF ENVIRONMENTAL | | PROTECTION DUE TO A RELEASE OF WATER CONTAINING AMMONIA AT A LEVEL OF 3 | | PPM. THE AMOUNT RELEASED IS ESTIMATED AT 500 GALLONS. THE RELEASE WAS | | FROM WATER AND STEAM CONDENSATION FROM AN ATMOSPHERIC STEAM TRAP ENTERING A | | STORM DRAIN." END OF TEXT. | | | | THE LIMIT FOR AMMONIA IS 1.025 PPM. THE STEAM TRAPS ARE UPSTREAM OF THE | | MSIVS AND CAN BE ALIGNED TO THE CONDENSER OR TO ATMOSPHERE. THE LICENSEE | | HAS JUST RECENTLY CHANGED MODES FROM COLD SHUTDOWN TO HOT SHUTDOWN AND THE | | HEATUP RESULTED IN THE STEAM TRAPS DISCHARGING. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND LOCAL TOWNSHIP | | OFFICIALS OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28486 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 03/05/95 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 19:15 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 03/05/95 | +------------------------------------------------+EVENT TIME: 15:37[PST]| |NRC NOTIFIED BY: STANLEY PLEWA |LAST UPDATE DATE: 03/05/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |DCTB 73.71(b)(1) CONTRABAND |CECIL THOMAS EO | | |GENE MCPEEK (IAT) NRR | | |JOHN DAVIDSON (IAT) NRR | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | 3 | N Y 97 POWER OPERATION | 97 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ATTEMPTED INTRODUCTION OF A WEAPON INTO THE PROTECTED AREA. | | | | A SOUTHERN CALIFORNIA EDISON EMPLOYEE WHILE ENTERING THE PROTECTED AREA WAS | | FOUND TO HAVE A WEAPON. IMMEDIATE COMPENSATORY MEASURES WERE TAKEN ON | | DISCOVERY. LICENSEE NOTIFIED THE LOCAL FBI OF THIS INCIDENT. | | | | RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | **** SEE HOO LOG BOOK FOR FURTHER DETAILS**** | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28487 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 03/05/95 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 21:32 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 03/05/95 | +------------------------------------------------+EVENT TIME: 20:30[CST]| |NRC NOTIFIED BY: B HANSON |LAST UPDATE DATE: 03/05/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MCCORMICKBARGER RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REACTOR PLANT SHUTDOWN DUE TO UNIT 2 EMERGENCY | | DIESEL GENERATOR (EDG) BEING INOPERABLE. | | | | UNIT 2 COMMENCED A REACTOR PLANT SHUTDOWN PER TECH SPEC 3.9.2.C (RESTORE | | EDG WITHIN 7 DAYS OR BE IN A COLD SHUTDOWN CONDITION WITHIN 24 HOURS) AFTER | | DECLARING UNIT 2 EDG INOPERABLE AND NOT BEING ABLE TO RESTORE IT TO AN | | OPERABLE STATUS WITHIN 7 DAYS. UNIT 2 EDG FAILED ITS OPERABILITY | | SURVEILLANCE TEST DUE TO A BAD VOLTAGE REGULATOR AND WAS DECLARED | | INOPERABLE AT 1004 CST ON 02/27/95. LICENSEE IS REDUCING REACTOR POWER AT | | 100 MEGAWATTS ELECTRIC PER HOUR AND THEY SHOULD BE SHUTDOWN BY 0700 CST | | 03/06/95. ALL EMERGENCY CORE COOLING SYSTEMS FOR UNIT 2 ARE FULLY OPERABLE. | | ELECTRICAL GRID IS STABLE AND THE SWING EDG IS OPERABLE. UNIT 2 EDG IS | | AVAILABLE IF NEEDED BUT WOULD BE OPERATED IN ITS MANUAL MODE OF OPERATION | | IF NEEDED (UNIT 3 EDG IS FULLY OPERABLE). | | | | LICENSEE HAS FOUND A REPLACEMENT VOLTAGE REGULATOR BUT IN ORDER TO TEST THE | | REGULATOR THEY MUST DO A REGULAR INITIATION OF THE UNIT 2 EDG AND | | SEQUENCING OF ALL THE ECCS PUMPS TO ITS RESPECTED BUS. LICENSEE WILL NOT | | PERFORM THIS TEST WHILE ON LINE. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+