U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/03/97 - 07/07/97 ** EVENT NUMBERS ** 32548 32583 32584 32585 32586 32587 32588 32589 32590 32591 32592 32593 32594 32595 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32548 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 06/27/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 04:19 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/27/97 | +------------------------------------------------+EVENT TIME: 01:27[EDT]| |NRC NOTIFIED BY: RUPPERT |LAST UPDATE DATE: 07/03/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FRANK COSTELLO RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI AND RCIC SUCTION SWAPOVER FROM CST TO SUPPRESSION POOL DURING TESTING | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "ON 6/27/97 AT 0127 HOURS, THE UNIT 2 HPCI SYSTEM WAS BEING TESTED | | FOLLOWING MAINTENANCE. ST-6-055-230-2, 'HPCI PUMP, VALVE AND FLOW TEST,' | | WAS BEING PERFORMED IN ORDER TO DECLARE THE HPCI SYSTEM OPERABLE. DURING | | PERFORMANCE OF THE TEST, A FALSE CONDENSATE STORAGE TANK (CST) LOW LEVEL | | SIGNAL (BELIEVED TO BE DUE TO ENTRAPPED AIR IN THE SYSTEM) CAUSED THE | | SUCTIONS OF BOTH THE HPCI AND RCIC SYSTEMS TO SWAP FROM THEIR NORMAL WATER | | SUPPLY (CST) TO THEIR ALTERNATE SUPPLY (SUPPRESSION POOL). THE SWAPOVER | | COMPLETED AND ALL VALVES OPERATED AS EXPECTED. THE HPCI SYSTEM WAS | | SECURED. BOTH THE HPCI AND RCIC SYSTEMS WERE REALIGNED TO THEIR NORMAL | | WATER SUPPLY. HPCI AND RCIC SUCTION LINES WERE FILLED AND VENTED. | | ENGINEERING IS CURRENTLY INVESTIGATING AND EVALUATING THE CAUSE OF THIS | | EVENT." | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1439 ON 07/03/97, FROM TONKINSON TAKEN BY WEAVER * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED ON THE FOLLOWING | | EXPLANATION WHICH WAS PROVIDED BY FACSIMILE FROM THE LICENSEE: | | | | "IT WAS DETERMINED THAT THE ACTUATION WAS CAUSED BY ENTRAPPED AIR. AS THE | | AIR PASSED THE CST LEVEL AUTOMATIC SUCTION TRANSFER, A LOW LEVEL SIGNAL WAS | | GENERATED. UPON REVIEW OF THE DESIGN BASES FOR THE LOW CST LEVEL AUTOMATIC | | SUCTION TRANSFER, IT WAS DETERMINED THAT THIS FEATURE ONLY SUPPORTS THE | | OPERABILITY OF THE HPCI SYSTEM (BY ENSURING A USABLE VOLUME OF WATER). | | THE LOW LEVEL TRANSFER FEATURE IS, THEREFORE, NOT AN [ENGINEERED SAFETY | | FEATURE]. FURTHERMORE, A REVIEW OF THE TEST PERFORMANCE DATA INDICATED | | THAT THE HPCI SYSTEM WAS ABLE TO PERFORM ITS DESIGN SAFETY FUNCTION IN THE | | AS-FOUND CONDITION. THIS SITUATION, THEREFORE, [WAS] DETERMINED [TO BE] | | NOT REPORTABLE." | | | | THE OPERATIONS OFFICER NOTIFIED THE R1DO (MOHAMED SHANBAKY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32583 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/03/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 03:56 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 03:43[EDT]| |NRC NOTIFIED BY: JOHN THOMAS |LAST UPDATE DATE: 07/03/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |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 N 0 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN TO MODE 5 DUE TO THE UNISOLATION | | OF A RESIDUAL HEAT REMOVAL (RHR) SAMPLE SYSTEM PIPING PENETRATION FOR | | REQUIRED CHEMISTRY SAMPLING. | | | | IN ORDER TO ENSURE CONTAINMENT PIPING PENETRATION INTEGRITY DURING | | POSTULATED ACCIDENTS WHILE UNIT 1 IS OPERATING IN MODES 1 THROUGH 4, THE | | LICENSEE MAINTAINS RHR SAMPLE SYSTEM PIPING PENETRATION #97-1 ISOLATED AND | | DRAINED. THIS IS A THERMAL OVERPRESSURE PROTECTION CONCERN BECAUSE THERE | | ARE NO RELIEF VALVES IN THIS LINE. | | | | PREPARATIONS FOR PLACING THE RHR SYSTEM IN SERVICE REQUIRE THE LICENSEE TO | | OBTAIN AN RHR CHEMISTRY SAMPLE VIA PENETRATION #97-1. IN ORDER TO OBTAIN | | THIS SAMPLE, THE LICENSEE IS CURRENTLY IN THE PROCESS OF COOLING UNIT 1 | | DOWN FROM MODE 3 (HOT STANDBY) TO MODE 5 (COLD SHUTDOWN). | | | | PENETRATION #97-1 WAS UNISOLATED AT 0343 TO ENABLE CHEMISTRY SAMPLING, | | AND THIS RESULTED IN A TECHNICAL SPECIFICATION 3.6.1.1 ENTRY. THE ACTION | | STATEMENT FOR THIS TECHNICAL SPECIFICATION REQUIRES THE RESTORATION OF | | INTEGRITY WITHIN ONE HOUR OR A UNIT SHUTDOWN TO MODE 5. THE LICENSEE | | BELIEVES THAT THE PENETRATION WILL NOT BE ISOLATED AND DRAINED WITHIN | | ONE HOUR. ACCORDINGLY, A TECHNICAL SPECIFICATION REQUIRED SHUTDOWN WAS | | COMMENCED. (THE LICENSEE WAS AWARE OF THESE REQUIREMENTS PRIOR TO THE | | TIME THAT PENETRATION #97-1 WAS UNISOLATED.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32584 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 07/03/97 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 09:49 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 08:22[CDT]| |NRC NOTIFIED BY: DAVE SLAGER |LAST UPDATE DATE: 07/03/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 95 POWER OPERATION | 95 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF THE PROCESS COMPUTER AND SAFETY PARAMETER DISPLAY SYSTEM DISPLAYS | | DUE TO HIGH COMPUTER ROOM TEMPERATURES. | | | | THE LICENSEE RECEIVED INDICATION OF HIGH COMPUTER ROOM TEMPERATURES, AND A | | LOSS OF THE PROCESS COMPUTER AND SAFETY PARAMETER DISPLAY SYSTEM DISPLAYS | | OCCURRED APPROXIMATELY ONE MINUTE LATER. APPARENTLY, NEITHER THE NORMAL | | OR BACKUP HVAC SYSTEM WAS PROVIDING COOLING TO THE COMPUTER ROOM. THE | | LICENSEE'S INITIAL INVESTIGATION INDICATED THAT THIS WAS A MAJOR CONCERN. | | | | EFFORTS ARE CURRENTLY UNDERWAY TO PROVIDE ADDITIONAL COOLING TO THE | | COMPUTER ROOM FROM ALTERNATE SOURCES, AND THE LICENSEE'S ROOT CAUSE | | INVESTIGATION IS IN PROGRESS. THE LICENSEE ALSO PLANS TO PERFORM | | EVALUATIONS OF THE EFFECTS ON THE COMPUTERS WHEN TEMPERATURES RETURN TO | | NORMAL RANGE. | | | | AT THE TIME OF THIS NOTIFICATION, COMPUTER ROOM TEMPERATURE WAS AT 95øF | | AND DECREASING. THE TEMPERATURE HAD PEAKED AT APPROXIMATELY 98øF. | | | | AT THE PRESENT TIME, THE LICENSEE IS UTILIZING NUMEROUS OTHER METHODS TO | | MONITOR THE STATUS OF UNITS 2 AND 3. THE LICENSEE STATED THAT THERE WERE | | NO PROBLEMS WITH CONTROL ROOM ANNUNCIATORS AND THAT ALL OTHER SYSTEMS WERE | | PERFORMING AS EXPECTED. UNITS 2 AND 3 ARE NOT CURRENTLY IN ANY TECHNICAL | | SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT OF THIS EVENT. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY | | STATE OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32585 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: EMORY UNIVERSITY CLINIC |NOTIFICATION DATE: 07/03/97 | | CITY: ATLANTA REGION: 2 |NOTIFICATION TIME: 14:10 [ET]| | COUNTY: FULTON STATE: GA |EVENT DATE: 06/30/97 | |LICENSE#: GA 153-1 AGREEMENT: Y |EVENT TIME: 17:30[EDT]| | DOCKET: |LAST UPDATE DATE: 07/03/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | |DON COOL (NMSS) EO | +------------------------------------------------+ | |NRC NOTIFIED BY: TOM HILL | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LEAKING 5-MILLICURIE PROTOTYPE STRONTIUM-90 SOURCE AT EMORY UNIVERSITY | | | | THE GEORGIA DEPARTMENT OF NATURAL RESOURCES RECEIVED A REPORT FROM EMORY | | UNIVERSITY CLINIC REGARDING A LEAKING PROTOTYPE STRONTIUM-90 SOURCE | | (APPROXIMATELY 5 MILLICURIES) USED AS A STANDARD. A SURVEY OF AN EMPTY | | VIAL AFTER TRANSFERRING THE SOURCE TO A PIG FOUND THE VIAL CONTAMINATED. | | ADDITIONAL SURVEYS IDENTIFIED THAT THE ROOM (BOTH THE FLOOR AND COUNTER) | | WERE ALSO CONTAMINATED. THE SOURCE WHICH WAS MANUFACTURED BY BEBIG | | (LOCATED IN ILLINOIS) IS OWNED BY NOVOSTE AND USED BY THE BROAD LICENSE OF | | EMORY UNIVERSITY. NOVOSTE HAD SENT SOURCES TO ONE OTHER BROAD LICENSEE IN | | THE UNITED STATES AND TO TWO OTHER USERS OUTSIDE THE UNITED STATES. THE | | LICENSEE SUSPECTS THAT THE SOURCE WAS DAMAGED BY THE NATIONAL INSTITUTE OF | | STANDARDS AND TECHNOLOGY DURING TESTING BETWEEN MARCH 23 AND MAY 15, 1995. | | THE STATE OF ILLINOIS WAS NOTIFIED IN THE EVENT THEY HAD A SOURCE | | EVALUATION IN PROCESS OR SHOULD RECEIVE A SOURCE EVALUATION REQUEST. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32586 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 07/03/97 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 14:23 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 13:31[EDT]| |NRC NOTIFIED BY: LANCE FRITZ |LAST UPDATE DATE: 07/03/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |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 | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECH SPEC REQUIRED SHUTDOWN COMMENCED AFTER DECLARING THE REFUELING WATER | | STORAGE TANK (RWST) INOPERABLE DUE TO LOW BORON CONCENTRATION. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 1313 EDT, THE CONTROL ROOM WAS NOTIFIED THAT THE RWST BORON | | CONCENTRATION WAS 2,695 PPM BORON. (THE TECH SPEC VALUE IS 2,700 PPM.) THE | | RWST WAS DECLARED INOPERABLE AND THE FOLLOWING TECH SPECS WERE ENTERED: | | 3.1.2.6, 3.1.2.2, AND 3.5.4. THE MOST RESTRICTIVE [TECH SPEC A/S] CALL[ED] | | FOR THE RETURN TO OPERABLE STATUS WITHIN 1 HOUR OR BE IN HOT STANDBY IN THE | | NEXT 6 HOURS AND COLD SHUTDOWN WITHIN THE FOLLOWING 30 HOURS. PLANT | | SHUTDOWN WAS COMMENCED AT 1331 EDT, AND 2,000 GALLONS OF BORIC ACID WAS | | INITIALLY ADDED TO THE RWST. PLANT SHUTDOWN CONTINUES AS OF THIS REPORT." | | | | CHEMISTRY IDENTIFIED THE LOW BORON CONCENTRATION DURING ROUTINE WEEKLY | | SAMPLING. A SECOND SAMPLE WAS TAKEN WHICH CONFIRMED THE INITIAL RESULTS. | | THE LICENSEE WAS UNABLE TO IDENTIFY THE CAUSE AND IS CONDUCTING AN | | INVESTIGATION. A FOLLOWUP SAMPLE (AFTER ADDING THE 2,000 GALLONS OF BORIC | | ACID) WILL BE DRAWN IN ABOUT 2-1/2 HOURS. THE LICENSEE PLANS TO ISSUE A | | PRESS RELEASE AND HAS INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1529 EDT ON 07/03/97, FROM LANCE FRITZ TO S. SANDIN * * * | | | | THE LICENSEE EXITED THE ABOVE TECH SPEC A/S AT 1512 EDT AFTER 4 CONSECUTIVE | | RWST SAMPLES VERIFIED THE BORON CONCENTRATION >2,700 PPM. THE UNIT IS | | CURRENTLY AT ABOUT 93% POWER. THE LICENSEE PLANS TO INFORM THE NRC | | RESIDENT INSPECTOR. THE NRC OPERATIONS OFFICER NOTIFIED THE R1DO (MOHAMED | | SHANBAKY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32587 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 07/03/97 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 19:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 16:08[PDT]| |NRC NOTIFIED BY: GARY ANDERSON |LAST UPDATE DATE: 07/03/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES 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 | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED THAT THE AUXILIARY SALTWATER PUMPS COULD BE | | RENDERED INOPERABLE UNDER CERTAIN FLOODING CONDITIONS DUE TO BLOCKED FLOOR | | DRAIN CHECK VALVES. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON JULY 3, 1997, [THE LICENSEE] DETERMINED THAT THE UNIT 1 AND 2 AUXILIARY | | SALTWATER (ASW) SYSTEMS HAD BEEN INOPERABLE DUE TO CHECK VALVES IN THE ASW | | PUMP VAULT DRAIN LINES NOT BEING FUNCTIONAL. THE DISCS ON [THREE] OF | | [FOUR] VALVES WERE FOUND BLOCKED OPEN BY DEBRIS AND CORROSION PRODUCTS. THE | | VALVES WERE LAST VERIFIED OPERABLE IN JULY AND AUGUST OF 1996. | | | | THE PUMP ROOM VAULTS ARE DESIGNED TO BE WATER TIGHT TO PREVENT DAMAGE TO | | THE ASW PUMP MOTORS DURING POSSIBLE FLOODING CONDITIONS. THESE EVENTS ARE: | | | | * A TSUNAMI FLOODING THE INTAKE | | * A MODERATE ENERGY LINE BREAK (MELB) IN THE CIRCULATING WATER SYSTEM | | * A SEISMICALLY INDUCED BREAK IN THE CIRCULATING WATER SYSTEM | | | | CHECK VALVES IN THE ASW DRAIN LINES PREVENT REVERSE FLOW WHICH COULD OCCUR | | AS A RESULT OF FLOODING FROM THE ABOVE EVENTS. FLOODING OF THE ASW PUMP | | VAULTS COULD RENDER THE ASW PUMP MOTORS INOPERABLE. | | | | SHOULD THE CHECK VALVES BE UNABLE TO OPEN PROPERLY, WATER SPILLING FROM A | | BREAK IN THE ASW PUMP DISCHARGE LINE WOULD NOT DRAIN PROPERLY AND COULD | | FLOOD THE VAULTS RENDERING THE ASW PUMP MOTORS INOPERABLE. | | | | EACH OF THE VALVES HAS BEEN INSPECTED AND CLEANED, OR REPLACED, BETWEEN | | JUNE 26, 1997, AND JULY 3, 1997, AND ARE CURRENTLY OPERABLE. | | | | [THE LICENSEE] REVIEWED THIS CONDITION ON JULY 3, 1997, AND DETERMINED THAT | | THIS REPRESENTED A CONDITION OUTSIDE THE DESIGN BASIS OF THE PLANT. THIS | | [WAS] DETERMINED TO BE REPORTABLE [PER] 10 CFR 50.72(b)(1)(ii)(B)." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32588 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 07/03/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 19:21 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 15:57[CDT]| |NRC NOTIFIED BY: RICK PARLATO |LAST UPDATE DATE: 07/03/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED ADDITIONAL SECTIONS OF PIPING SUBJECT TO THERMALLY | | INDUCED OVERPRESSURIZATION DURING FOLLOWUP REVIEW TO NRC GENERIC LETTER | | 96-06. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "FOLLOWUP REVIEWS, DUE TO [LICENSEE EVENT REPORT] 266/97-018-00, IDENTIFIED | | SEVERAL ISOLATED PIPE SECTIONS INSIDE CONTAINMENT THAT MAY OVER PRESSURIZE | | DUE TO HEATING IN A POST-ACCIDENT ENVIRONMENT. THESE SECTIONS ARE [AS | | FOLLOWS]: | | | | 1. DEMINERALIZED WATER FROM CHECK VALVES 1(2)-529 | | 2. DEMINERALIZED WATER FROM ISOLATION VALVES 1(2)-11 | | 3. STEAM GENERATOR PRIMARY SIDE HOT AND COLD LEG VENTS | | 4. REACTOR VESSEL LEVEL INDICATION SYSTEM - 5 SECTIONS/UNIT | | 5. [SAFETY INJECTION] ACCUMULATOR LOCAL SAMPLE LINES (UNIT 1 AND 2) | | 6. [REACTOR COOLANT PUMP] #1 SEAL BYPASS LINE (UNIT 1 AND 2) | | 7. EXCESS LETDOWN LINE (UNIT 1 AND 2) | | 8. REFUELING CAVITY DRAIN LINE (UNIT 1 AND 2)." | | | | THE LICENSEE IDENTIFIED THAT CORRECTIVE ACTIONS ARE TO BE DETERMINED. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32589 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 07/03/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 21:18 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 19:42[EDT]| |NRC NOTIFIED BY: L. MOFFATT |LAST UPDATE DATE: 07/03/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONDITION WHICH COULD AFFECT THE ABILITY OF BOTH | | EMERGENCY DIESEL GENERATORS (EDG) TO CARRY GREATER THAN 3,000 KW. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING AN ONGOING REVIEW OF THE CAPABILITY OF THE CRYSTAL RIVER UNIT 3 | | EMERGENCY DIESEL GENERATORS (EGDG-1A/B), QUESTIONS AROSE CONCERNING AMBIENT | | AIR TEMPERATURE IN THE EDG CONTROL ROOMS AND ENGINE ROOMS. ELEVATED | | TEMPERATURES WERE NOTED IN THE CONTROL ROOMS AND ENGINE ROOMS DURING | | TESTING CONDUCTED IN EARLY JUNE 1997. THE ELEVATED ROOM TEMPERATURES WERE | | DETERMINED TO HAVE PLACED THE PLANT OUTSIDE THE DESIGN BASIS, AND [A | | LICENSEE EVENT REPORT] HAS BEEN SUBMITTED ON THIS ISSUE. | | | | FURTHER RESEARCH HAS DEMONSTRATED THAT A PORTION OF THE EDG RADIATOR | | EXHAUST AIR IS RECIRCULATING BACK TO THE RADIATOR INLET AND CAUSING THE | | AVERAGE OUTSIDE AIR TEMPERATURE BEING SUPPLIED TO THE EDG COMPONENTS TO | | INCREASE. THIS AFFECTS THE SUPPLY AIR TEMPERATURE TO THE RADIATOR, THE | | ENGINE ROOM (INCLUDING THE GENERATOR AND OTHER COMPONENTS), CONTROL ROOM | | VENTILATION AIR, AND ENGINE ROOM COMBUSTION AIR FOR BOTH EDGs. THE | | INCREASED SUPPLY AIR TEMPERATURE COULD ALLOW THE DESIGN BASIS TEMPERATURES | | TO BE EXCEEDED FOR ALL OF THESE AREAS/COMPONENTS. | | | | INFORMATION HAS BEEN RECEIVED FROM THE EDG VENDOR [COLT] INDICATING THAT | | THE MAXIMUM LOAD WHICH COULD BE CARRIED BY EACH EDG GIVEN THESE SUPPLY AIR | | TEMPERATURES IS 3,000 KILOWATTS. THIS CAPABILITY IS ABOVE THE MAXIMUM | | EXPECTED LOADING IN THE CURRENT PLANT CONDITION (MODE 5, COLD SHUTDOWN); | | HOWEVER, THIS IS BELOW THE MAXIMUM EXPECTED LOADING REQUIRED TO MITIGATE | | VARIOUS ACCIDENTS WHILE ON LINE. | | | | THIS EVENT IS 4-HOUR REPORTABLE IN ACCORDANCE WITH 10CFR50.72(b)(2)(i) AS | | AN EVENT FOUND WHILE THE REACTOR IS SHUTDOWN THAT, HAD IT BEEN FOUND WHILE | | THE REACTOR WAS IN OPERATION, WOULD HAVE RESULTED IN THE NUCLEAR POWER | | PLANT, INCLUDING ITS PRINCIPAL SAFETY BARRIERS, BEING SERIOUSLY DEGRADED. | | IN ADDITION, THE EVENT IS 4-HOUR REPORTABLE IN ACCORDANCE WITH | | 10CFR50.72(b)(2)(iii)(D) AS AN EVENT OR CONDITION THAT ALONE COULD HAVE | | PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF STRUCTURES OR SYSTEMS | | THAT ARE NEEDED TO MITIGATE THE CONSEQUENCES OF AN ACCIDENT. | | | | A MODIFICATION IS BEING DEVELOPED TO ELIMINATE THIS AIR RECIRCULATION | | EFFECT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32590 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 07/04/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 19:05 [ET]| |RX TYPE: [3] CE |EVENT DATE: 07/04/97 | +------------------------------------------------+EVENT TIME: 17:50[CDT]| |NRC NOTIFIED BY: EDWARD AVILES |LAST UPDATE DATE: 07/04/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BILL JONES RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SECURITY EVENT - POTENTIAL UNDETECTED ENTRY OF CONTRACT EMPLOYEE INTO VITAL | | AREA | | | | IMMEDIATE COMPENSATORY MEASURES WERE NOT TAKEN UPON DISCOVERY. COMPENSATORY | | MEASURES ARE NOW FULLY IMPLEMENTED. (REFER TO THE HOO LOG FOR DETAILS.) | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32591 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ROBINSON REGION: 2 |NOTIFICATION DATE: 07/05/97 | |UNIT: [2] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:37 [ET]| |RX TYPE: [2] W-3-LP |EVENT DATE: 07/05/97 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: KEN JONES |LAST UPDATE DATE: 07/05/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE 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 +------------------------------------------------------------------------------+ | CONTAINMENT TEMPERATURE EXCEEDS THE UFSAR INPUT USED IN THE CONTAINMENT | | ANALYSIS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WITH REGARD TO THE DESIGN BASIS OF THE REACTOR CONTAINMENT AND ITS | | VENTILATION SYSTEM, THE UPDATED FINAL SAFETY ANALYSIS REPORT [UFSAR] STATES | | THAT THE CONTAINMENT BUILDING VENTILATION SYSTEM IS DESIGNED TO REMOVE HEAT | | LOADS AND MAINTAIN TEMPERATURE OF 120 DEGREES [F] OR LESS. AS AN INITIAL | | CONDITION FOR THE CONTAINMENT ANALYSIS, THE UFSAR STATES THAT THE | | CONTAINMENT TEMPERATURE IS AT 120 DEGREES F. BASED ON TEMPERATURE | | MEASUREMENTS PERFORMED ON JULY 5 AT 1600 HOURS, THE CONTAINMENT TEMPERATURE | | WAS INDICATED TO BE 120.51 DEGREES F. THEREFORE, THE CONTAINMENT IS NOT | | CONSIDERED TO BE OPERATING WITHIN THE UFSAR DESIGN. THE TECHNICAL | | SPECIFICATIONS DO NOT SPECIFY A MAXIMUM CONTAINMENT TEMPERATURE LIMIT. | | STATION MANAGEMENT HAS IMPOSED AN ADMINISTRATIVE OPERATING RESTRICTION | | THAT REQUIRES THAT THE PLANT BE PLACED IN THE HOT SHUTDOWN CONDITION WITHIN | | 8 HOURS OF EXCEEDING 120 DEGREES F. ACTIONS WILL BE TAKEN TO RESTORE THE | | TEMPERATURE TO WITHIN LIMITS DURING THE 8-HOUR TIME PERIOD. HOWEVER, | | SUFFICIENT TIME WILL BE RESERVED TO ENSURE AN ORDERLY SHUTDOWN BY THE END | | OF THE 8-HOUR TIME PERIOD." | | | | THE LICENSEE NOTED THAT THE WEATHER HAS BEEN EXTREMELY HOT FOR THE PAST | | 4 DAYS WHICH HAS INCREASED LAKE TEMPERATURES. THE CURRENT CONTAINMENT | | TEMPERATURE IS 119.9øF AND TRENDING DOWNWARD DUE TO A SLOWLY DECREASING | | CIRCULATING WATER (CW) INLET TEMPERATURES. (THERE IS ABOUT A 1-1/2 TO | | 2-HOUR LAG BETWEEN AN OBSERVED DECREASE IN CW INLET TEMPERATURE AND | | CONTAINMENT TEMPERATURE.) AS A COMPENSATORY MEASURE, THE LICENSEE CAN | | INITIATE A CONTAINMENT PURGE TO REDUCE CONTAINMENT TEMPERATURES. (A | | 0.7-DEGREE F DECREASE IN CONTAINMENT TEMPERATURE WAS OBSERVED WHEN A PURGE | | WAS PERFORMED 4 DAYS AGO.) THE 8-HOUR ADMINISTRATIVE LIMIT WAS ADOPTED | | BASED ON THE GUIDANCE PROVIDED IN THE IMPROVED TECH SPECS WHICH HAS NOT | | BEEN APPROVED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2222 EDT ON 07/05/97, FROM DAVID COATES TO S. SANDIN * * * | | | | THE LICENSEE EXITED THE 8-HOUR ADMINISTRATIVE LIMIT AT 2000 EDT. THE | | VOLUMETRIC WEIGHTED TEMPERATURE AVERAGE CALCULATED AT 2200 EDT WAS 119.892 | | DEGREES F. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE OPERATIONS | | OFFICER NOTIFIED THE R2DO (ED McALPINE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32592 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 07/05/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 21:20 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/05/97 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: JEFFREY P. SIPE |LAST UPDATE DATE: 07/05/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED NON-SEISMICALLY QUALIFIED RELAYS WHICH COULD AFFECT | | THE OPERABILITY OF UNIT 1 EMERGENCY DIESEL GENERATORS. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THE BEAVER VALLEY UFSAR SECTION 9.10 STATES THE FOLLOWING REGARDING FIRE | | PROTECTION DESIGN: 'THE FIRE PROTECTION SYSTEM IS DESIGNED ON THE BASIS | | THAT RUPTURE OR INADVERTENT OPERATION WILL NOT SIGNIFICANTLY IMPAIR THE | | SAFETY CAPABILITY OF STRUCTURES, SYSTEMS, OR COMPONENTS IMPORTANT TO SAFETY | | OR DESIGNED TO SEISMIC CATEGORY 1 REQUIREMENTS.' | | | | IT HAS BEEN DETERMINED THAT INADVERTENT OPERATION OF THE EMERGENCY DIESEL | | GENERATORS (#EE-EG-1 & 2) FIRE PROTECTION SYSTEM DUE TO SEISMIC MOTION | | COULD ADVERSELY AFFECT THE ABILITY OF THE EMERGENCY DIESEL GENERATORS TO | | FUNCTION DUE TO CO2 FLOODING AND AIR DISPLACEMENT. CHATTERING OF CONTROL | | CIRCUIT RELAYS THAT LACK SEISMIC QUALIFICATION COULD ACTUATE THE CO2 | | SYSTEM. | | | | THE CO2 SYSTEM IN EACH DIESEL GENERATOR ROOM HAS BEEN PLACED IN THE | | 'ABNORMAL' MODE. THIS PREVENTS AUTOMATIC OPERATION FROM THE SUSPECT | | RELAYS, BUT [IT] STILL PROVIDES FIRE ALARM CAPABILITY TO THE CONTROL ROOM | | IN THE EVENT OF A FIRE IN THE DIESEL GENERATOR ROOMS. THE FIRE PROTECTION | | PROGRAM REQUIRES A CONTINUOUS FIRE WATCH WITH BACKUP SUPPRESSION CAPABILITY | | IN EACH DIESEL GENERATOR ROOM WHILE THE CO2 SYSTEM IS INOPERABLE. THE | | REQUIRED FIRE WATCHES ARE IN PLACE WITH BACKUP SUPPRESSION." | | | | LONG-TERM CORRECTIVE ACTION IS TO REPLACE SUSPECT RELAYS WITH SEISMICALLY | | QUALIFIED RELAYS. THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32593 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 07/06/97 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 00:07 [ET]| |RX TYPE: [1] CE |EVENT DATE: 07/04/97 | +------------------------------------------------+EVENT TIME: 07:30[EDT]| |NRC NOTIFIED BY: LARRY GRIMARD |LAST UPDATE DATE: 07/06/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY RDO | |NINF INFORMATION ONLY | | | |NEIL SHEEHAN, R1 PAO | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - LICENSEE REQUESTED A CORRECTION TO AN ERRONEOUS LOCAL NEWSPAPER ARTICLE - | | | | ON 07/04/97, AN ARTICLE ABOUT MAINE YANKEE APPEARED IN THE PORTLAND PRESS | | HERALD NEWSPAPER. THE ARTICLE INCLUDED AN ERRONEOUS STATEMENT THAT WATER | | HAD MISTAKENLY BEEN DRAINED FROM A POOL (CAVITY) THAT CONTAINED SPENT FUEL | | RODS (THE SPENT FUEL POOL). IN FACT, NO WATER HAD BEEN TRANSFERRED FROM A | | CAVITY CONTAINING SPENT FUEL RODS. THE CAVITY IN QUESTION (KNOWN AS THE | | UPENDER PIT) IS AN AREA USED ONLY FOR THE TRANSFER OF FUEL ASSEMBLIES FROM | | THE REACTOR VESSEL TO THE SPENT FUEL POOL. THERE ARE NO SPENT FUEL RODS | | STORED IN THE UPENDER PIT. THIS PIT IS SIMPLY A TRANSFER POINT. THIS | | TRANSFER TYPICALLY OCCURS DURING REFUELING. | | | | THE LICENSEE PUBLIC AFFAIRS OFFICER SENT A MEMORANDUM TO NEWSPAPER | | OFFICIALS REQUESTING A CORRECTION TO THE NEWSPAPER ARTICLE. | | | | THE LICENSEE NOTIFIED THE NRC OPERATIONS OFFICER OF THIS REQUEST. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32594 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 07/06/97 | |UNIT: [ ] [2] [ ] STATE: SC |NOTIFICATION TIME: 10:46 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 07/06/97 | +------------------------------------------------+EVENT TIME: 06:52[EDT]| |NRC NOTIFIED BY: MIKE HILL |LAST UPDATE DATE: 07/06/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -AUTO REACTOR/MAIN TURBINE TRIP FROM 100% POWER DUE TO A GRID DISTURBANCE- | | | | A GRID DISTURBANCE CAUSED A 51VR (X PHASE) OVERCURRENT RELAY TO ACTUATE | | WHICH CAUSED A MAIN GENERATOR BACKUP LOCKOUT. THIS IN TURN CAUSED THE MAIN | | TURBINE TO TRIP WHICH CAUSED THE REACTOR TO TRIP FROM 100% POWER. ALL | | CONTROL RODS INSERTED COMPLETELY. | | | | THE PRESSURIZER LEVEL DROPPED TO LESS THAN 60 INCHES (NORMAL OPERATING | | LEVEL IS 220 INCHES). THE #2B HIGH PRESSURE INJECTION (HPI) PUMP | | AUTOMATICALLY STARTED DUE TO LOW REACTOR COOLANT (RC) PUMP SEAL INJECTION | | FLOW AND CONTROL ROOM OPERATORS MANUALLY STARTED THE #2C HPI PUMP TO | | RESTORE PRESSURIZER LEVEL TO ITS NORMAL RANGE. CONTROL ROOM OPERATORS | | SHIFTED THE SUCTIONS OF THE HPI PUMPS FROM THE LETDOWN STORAGE TANK TO THE | | REFUELING WATER STORAGE TANK FOR APPROXIMATELY FOUR MINUTES. THE HPI PUMPS | | WERE SECURED WHEN THE PRESSURIZER LEVEL WAS RESTORED TO ITS NORMAL | | OPERATING RANGE. | | | | STEAM IS BEING DUMPED TO THE MAIN CONDENSER. UNIT 2 IS STABLE IN MODE 4 | | (HOT SHUTDOWN). | | | | THE LICENSEE IS INVESTIGATING THE ROOT CAUSE OF THIS EVENT AND PLANS TO | | SUBMIT A LICENSEE EVENT REPORT TO THE NRC. | | | | THIS EVENT HAD NO EFFECT ON UNIT 1 (70% POWER) OR UNIT 3 (95% POWER). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1205 ON 07/06/97, FROM MIKE HALL ENTERED BY JOLLIFFE * * * | | | | UPON FURTHER INVESTIGATION, THE LICENSEE DETERMINED THAT THE INITIATING | | SIGNAL FOR THE REACTOR TRIP WAS AN UNDERVOLTAGE SIGNAL ON ALL FOUR RC PUMPS | | FOR LONGER THAN 200 MILLISECONDS FROM THE POWER-TO-RC PUMP TRIP CONTROL | | CIRCUITRY. A REACTOR TRIP SIGNAL IS ONLY GENERATED UPON AN UNDERVOLTAGE | | SIGNAL ON MORE THAN ONE RC PUMP. ALL FOUR RC PUMPS REMAINED RUNNING | | THROUGHOUT THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R2DO (ED McALPINE). | | | | * * * UPDATE AT 1915 ON 07/06/97, FROM MIKE HALL TO S. SANDIN * * * | | | | THE FOLLOWING ADDITIONAL INFORMATION WAS RECEIVED BY FACSIMILE: | | | | "THE FOLLOWING INFORMATION IS PRELIMINARY. INVESTIGATION IS STILL IN | | PROGRESS. FURTHER DETAILS WILL BE PROVIDED BY THE LICENSEE EVENT REPORT. | | | | JOCASSEE HYDRO STATION WAS PUMPING BACK TO LAKE JOCASSEE WITH ALL [FOUR] | | HYDRO UNITS (160 MW/UNIT). DUE TO SWITCHING PROBLEMS AT JOCASSEE HYDRO | | STATION, HYDRO UNITS 1 & 3 TRIPPED. AN OVERCURRENT CONDITION WAS CREATED | | AT THE JOCASSEE SWITCHYARD. THE JOCASSEE SWITCHYARD AND THE OCONEE 230-KV | | SWITCHYARD HAVE DIRECT TIES. THIS OVERCURRENT WAS SENSED AT OCONEE AND | | THIS LED TO THE UNIT 2 MAIN GENERATOR BACKUP LOCKOUT. | | | | UNIT 2 TRIPPED DUE TO THE ACTUATION OF [REACTOR PROTECTION SYSTEM (RPS)] | | POWER/RC PUMP TRIP - CHANNELS A, B, C, AND D. DURING THE GRID DISTURBANCE, | | THE POWER/RC PUMP MONITORS SENSED AN UNDERVOLTAGE CONDITION ON ALL [FOUR | | RC] PUMPS AND, THEREFORE, ACTUATED AN RPS TRIP. RPS CHANNELS A, B, C, AND | | D ALSO RECEIVED AN ANTICIPATORY TRIP SIGNAL DUE TO THE MAIN TURBINE | | TRIPPING. THE RPS POWER/RC PUMP TRIP WAS RECEIVED FIRST." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE OPERATIONS OFFICER NOTIFIED THE R2DO (ED McALPINE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32595 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 07/06/97 | |UNIT: [1] [ ] [ ] STATE: AL |NOTIFICATION TIME: 12:58 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 07/06/97 | +------------------------------------------------+EVENT TIME: 10:27[CDT]| |NRC NOTIFIED BY: BILL ARENS |LAST UPDATE DATE: 07/06/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 1 ENTERED TECH SPEC 3.0.3 DUE TO BOTH TRAINS OF TURBINE BUILDING | | SERVICE WATER INOPERABLE. | | | | I&C TECHNICIANS WERE TROUBLESHOOTING ANNUNCIATOR #AF-5 (SERVICE WATER TO | | TURBINE BUILDING HIGH FLOW ÷ 11500 GPM). THIS ANNUNCIATOR RECEIVES INPUT | | FROM FLOW SWITCHES IN BOTH THE "A" AND "B" TRAIN TURBINE BUILDING SERVICE | | WATER (TBSW) SUPPLY HEADERS. I&C TECHNICIANS WERE BRIEFED THAT | | TROUBLESHOOTING WOULD BE INITIALLY LIMITED TO THE "B" TRAIN TBSW WHICH HAD | | BEEN DECLARED INOPERABLE ON 07/05/97. | | | | HOWEVER, TESTING ON THE "A" TRAIN SWITCHES WAS PERFORMED A FEW MINUTES | | PRIOR TO 1027 CDT BEFORE OPERATIONS RETURNED THE "B" TRAIN TO SERVICE. | | OPERATORS IN THE CONTROL ROOM OBSERVED THAT AN "A" TRAIN SUPPLY MOV | | REPOSITIONED CLOSED. THIS ISOLATED SERVICE WATER TO VARIOUS EQUIPMENT | | INCLUDING THE MAIN LUBE OIL AND HYDROGEN COOLERS. OPERATORS TOOK ACTION | | PER ABNORMAL OPERATING PROCEDURE 7.0, "LOSS OF TURBINE BUILDING SERVICE | | WATER," REOPENED THE MOV, AND RESTORED TURBINE BUILDING SERVICE WATER FLOW. | | | | AT 1027 CDT, THE SUPPLY BREAKER FOR THIS MOV WAS OPENED TO PREVENT A | | RECURRENCE DURING SUBSEQUENT TROUBLESHOOTING. THIS ACTION RENDERED | | THE "A" TRAIN TBSW INOPERABLE. WITH BOTH TRAINS OF TBSW OUT OF SERVICE, | | UNIT 1 ENTERED TECH SPEC 3.0.3 WHICH ALLOWS ONE HOUR TO RETURN ONE TRAIN TO | | SERVICE OR TO BEGIN AN ORDERLY PLANT SHUTDOWN. | | | | AT 1106 CDT, THE "B" TRAIN TBSW WAS RETURNED TO SERVICE AND TECH SPEC 3.0.3 | | WAS EXITED. THE LICENSEE ATTRIBUTES THE ROOT CAUSE TO PERSONNEL ERROR. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+