U.S. Nuclear Regulatory Commission Operations Center Event Reports For 10/31/96 - 11/01/96 ** EVENT NUMBERS ** 31079 31163 31216 31224 31256 31257 31258 31259 31260 31261 31262 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31079 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 10/01/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:50 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/01/96 | +------------------------------------------------+EVENT TIME: 10:25[CDT]| |NRC NOTIFIED BY: BART CROW |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |IAN BARNES 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 +------------------------------------------------------------------------------+ | INOPERABILITY OF THE CONTROL ROOM EMERGENCY FILTER SYSTEM (CREFS) | | | | AT 1025 CDT, THE LICENSEE DECLARED THE CREFS TO BE INOPERABLE BECAUSE THE | | ACCEPTANCE CRITERIA OF SURVEILLANCE PROCEDURE 6.PRM.316, CONTROL ROOM | | VENTILATION SYSTEM KNOWN SOURCE CALIBRATION, WERE NOT MET. AT COOPER, | | CREFS IS A SINGLE TRAIN SYSTEM WHOSE FUNCTIONALITY IS CREDITED WITH | | MITIGATING THE CONSEQUENCES OF AN ACCIDENT. | | | | CREFS OPERABILITY REQUIRES THE FUNCTIONALITY OF RMV-RM-1, WHICH INITIATES | | THE CREFS ALIGNMENT TO ITS SAFETY MODE OF OPERATION UPON EXCEEDING THE | | RADIATION SETPOINT OF ANY OF ITS THREE PARAMETERS (GASEOUS, PARTICULATE, OR | | IODINE). TECHNICAL SPECIFICATION 4.2.D.4 REQUIRES RMV-RM-1 TO BE | | CALIBRATED ONCE EVERY THREE MONTHS. DURING PERFORMANCE OF THE CALIBRATION, | | THE AS-FOUND RESULTS OF THE PARTICULATE CHANNEL INDICATED THAT THE | | APPROPRIATE EXTENT OF THE ISOTOPIC SPECTRUM WAS NOT BEING SURVEYED. PENDING | | THE RESOLUTION OF THIS ISSUE, THE CREFS WAS DECLARED INOPERABLE IN | | ACCORDANCE WITH TECHNICAL SPECIFICATION 3.12.A.2, AND A 7-DAY LIMITING | | CONDITION FOR OPERATION WAS ENTERED. FURTHER INVESTIGATIONS ARE BEING | | PERFORMED TO DETERMINE IF THE CREFS COULD STILL BE CONSIDERED FUNCTIONAL | | DESPITE THE NON-CONSERVATISM OF THIS CONDITION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1106 ON 10/31/96, FROM CROW TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. AFTER REVIEWING THE SOURCE | | TERMS ASSOCIATED WITH ACCIDENTS FOR WHICH CREDIT IS TAKEN FOR THE CREFS, | | THE LICENSEE DETERMINED THAT THE PARTICULATE CONTRIBUTION TO THE SOURCE | | TERM IS LOW RELATIVE TO THE IODINE AND GASEOUS CONCENTRATIONS. ANALYSES OF | | THESE SOURCE TERMS HAS RESULTED IN THE CONCLUSION THAT RMV-RM-1 WOULD HAVE | | BEEN CAPABLE OF CAUSING THE CREDITED CREFS ACTUATIONS WITHOUT RELIANCE ON | | THE FUNCTIONALITY OF THE PARTICULATE CHANNEL. THEREFORE, SINCE CREFS WAS | | STILL ABLE TO MITIGATE THE CONSEQUENCES OF THESE ACCIDENTS CONSISTENT WITH | | THE CURRENT LICENSING BASIS, THIS NOTIFICATION IS RETRACTED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. THE NRC OPERATIONS CENTER | | NOTIFIED THE R4DO (TAPIA). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31163 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 10/16/96 | |UNIT: [1] [2] [ ] STATE: FL |NOTIFICATION TIME: 16:17 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 10/07/96 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: W.G. WHITE |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A TERMINATED EMPLOYEE'S SITE ACCESS WAS NOT SUSPENDED. HIS ACCESS HAS NOW | | BEEN SUSPENDED, AND THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. (REFER TO | | THE HOO LOG FOR DETAILS.) | | | | * * * UPDATE AT 1010 ON 10/31/96 FROM CZARNECKI ENTERED BY JOLLIFFE * * * | | | | AFTER REVIEWING SECURITY AND PERSONNEL RECORDS, PLANT SECURITY DEPARTMENT | | PERSONNEL DISCOVERED THAT A SECOND TEMPORARY LICENSEE EMPLOYEE'S SITE | | ACCESS AUTHORIZATION HAD NOT BEEN TERMINATED ON THE SAME DAY THE INDIVIDUAL | | HAD BEEN TERMINATED BUT WAS TERMINATED AT A LATER DATE. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. REFER TO THE HOO LOG | | FOR ADDITIONAL DETAILS. THE HOO NOTIFIED R2DO LESSER. | | | | * * * 1534 OCTOBER 31, 1996, UPDATE FROM CZARNECKI RECEIVED BY TROCINE * * | | | | THE LICENSEE IS RETRACTING THE UPDATE THAT WAS MADE AT 1010 THIS MORNING. | | THE TERMINATION DATE FOR THE SECOND INDIVIDUAL WAS INCORRECT, AND THE | | ACCESS AUTHORIZATION TERMINATION DATE WAS ACTUALLY BEFORE THE CORRECT | | EMPLOYEE TERMINATION DATE. (THE INITIAL PORTION OF THIS EVENT THAT WAS | | REPORTED ON OCTOBER 16, 1996, HAS NOT BEEN RETRACTED.) | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND MAY NOTIFY THE | | REGION 2 OFFICE. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (LESSER). | | (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE NUMBER AND FOR | | ADDITIONAL DETAILS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31216 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UTAH DIVISION OF RADIATION CONTROL |NOTIFICATION DATE: 10/25/96 | | CITY: MIDVALE REGION: 4 |NOTIFICATION TIME: 17:10 [ET]| | COUNTY: SALT LAKE STATE: UT |EVENT DATE: 10/25/96 | |LICENSE#: UT1800298 AGREEMENT: Y |EVENT TIME: 00:00[MDT]| | DOCKET: |LAST UPDATE DATE: 10/31/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |VANDENBURGH RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JULIE FELICE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | APPLIED GEOTECHNICAL ENGINEERING CONSULTANTS, INC, A STATE OF UTAH | | LICENSEE, REPORTED THE THEFT OF A TROXLER MODEL-3430 MOISTURE/DENSITY GAUGE | | (S/N 19705). THE UNIT WAS PLACED IN A LOCKED CABINET AT THE LICENSEE'S | | FACILITY IN MIDVALE ON 09/04/96. THE UNIT WAS DISCOVERED MISSING DURING AN | | AUDIT PERFORMED DURING THE SECOND WEEK OF OCTOBER. THE LICENSEE HAS | | CONTACTED ALL TECHNICIANS TO SEE IF ONE OF THEM HAD REMOVED THE UNIT. THE | | LICENSEE'S CONTRACTOR FOR CALIBRATING THE UNITS WAS ALSO CONTACTED. | | | | THE LICENSEE HAS REPORTED THE STOLEN UNIT TO THE MIDVALE POLICE DEPARTMENT | | (CASE NO. 96-4130). THE STATE PLANS TO ISSUE A PRESS RELEASE. | | | | * * * 1808 OCTOBER 31, 1996, UPDATE FROM FELICE RECEIVED BY TROCINE * * * | | | | THE MISSING GAUGE WAS RECOVERED AT THE LICENSEE'S FACILITY ON OCTOBER 30, | | 1996. THE PRESS RELEASE HAD NOT YET BEEN ISSUED AND WILL NO LONGER BE | | ISSUED AS A RESULT OF THIS DISCOVERY. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R4DO (TAPIA). (REFER TO THE HOO LOG | | FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31224 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 10/27/96 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 10:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/27/96 | +------------------------------------------------+EVENT TIME: 08:48[CST]| |NRC NOTIFIED BY: GREG SMITH |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE JORGENSEN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SECURITY EVENT - VITAL AREA BARRIER OPENED FOR 5 MINUTES W/O GUARD POSTED | | | | A 10 FEET X 10 FEET HATCH IN THE SERVICE WATER PUMP INTAKE CRIB HOUSE WAS | | OPENED WITHOUT A SECURITY GUARD BEING POSTED AT THE OPENING. A SECURITY | | GUARD WAS POSTED 5 MINUTES AFTER THE HATCH WAS OPENED. A LICENSEE | | EMPLOYEE HAD BEEN PRESENT AT THIS VITAL AREA BARRIER OPENING FOR THE | | ENTIRE 5 MINUTES. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1145 ON 10/31/96, FROM PLUTCHAK TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE LICENSEE REPORTED THAT | | THIS EVENT WAS PROPERLY COMPENSATED WITHIN THE TIME ALLOTTED IN THE | | SECURITY PLAN. FURTHER, A BADGED INDIVIDUAL WAS IN THE AREA, SO NO | | OPPORTUNITY FOR UNDETECTED ACCESS WAS POSSIBLE. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R3DO (HILAND). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31256 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 10/31/96 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 00:27 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 10/30/96 | +------------------------------------------------+EVENT TIME: 22:25[CST]| |NRC NOTIFIED BY: BILL HENNIG |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 +------------------------------------------------------------------------------+ | - 1 OF 2 PRESSURIZER SAFETY VALVES FAILED ITS INITIAL SETPOINT TEST - | | | | WITH UNIT 2 DEFUELED, 1 OF 2 PRESSURIZER SAFETY VALVES, #2RC-434, FAILED | | ITS INITIAL SETPOINT TEST AT WYLE LABS. THE SAFETY VALVE LIFTED AT | | 2564 PSIG WHEN TESTED AT 90øF WHICH IS 5 PSIG ABOVE THE SETTING OF | | 2485 PSIG +3%. WHEN THE VALVE WAS TESTED AT 140øF, ITS SETPOINT WAS 1.3% | | LOWER. THIS VALVE WAS TESTED PER ASME B&PV CODE SECTION XI AND OM-1-1981. | | | | THE OTHER UNIT 2 SAFETY VALVE, #2RC-435, WILL BE REMOVED, SHIPPED TO WYLE | | LABS, AND TESTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31257 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 10/31/96 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 03:15 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/31/96 | +------------------------------------------------+EVENT TIME: 03:00[EST]| |NRC NOTIFIED BY: SPENCER HACKNEY |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MARK LESSER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 97 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC REQUIRED PLANT SHUTDOWN DUE TO INOP 125 VOLT VITAL BATTERY - | | | | ONE OF FOUR 125 VOLT VITAL BATTERIES (CHANNEL 3) FAILED THE REQUIRED | | TEST CRITERIA FOR A MODIFIED PERFORMANCE TEST. AT 0956 ON 10/28/96, | | THE LICENSEE DECLARED THE BATTERY INOPERABLE (ALTHOUGH IT IS FUNCTIONAL). | | TECH SPEC LCO A/S 3.8.2.1 REQUIRES THE LICENSEE TO RESTORE THE INOPERABLE | | VITAL BATTERY TO OPERABLE STATUS WITHIN 72 HOURS WHILE UNIT 2 IS IN MODES | | 1 THROUGH 4 OR TO SHUT UNIT 2 DOWN TO HOT STANDBY MODE WITHIN 6 HOURS AND | | COLD SHUTDOWN MODE WITHIN THE FOLLOWING 30 HOURS. | | | | AT 0300 ON 10/31/96, THE LICENSEE BEGAN SHUTTING UNIT 2 DOWN FROM 100% | | POWER. | | | | THIS BATTERY ALSO SUPPLIES POWER TO UNIT 1. | | | | THE LICENSEE PLANS TO REPLACE THE BATTERY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | NOTE: UNIT 1 IS ALSO BEING SHUT DOWN DUE TO THIS INOPERABLE BATTERY. | | SEE EVENT #31253. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31258 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 10/31/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 12:35 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/31/96 | +------------------------------------------------+EVENT TIME: 12:31[EST]| |NRC NOTIFIED BY: MONTALVO AND SILBERQUIT |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MOHAMED SHANBAKY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR THE LOSS OF THE '2A' EMERGENCY DIESEL GENERATOR (EDG) DURING | | A HYPOTHETICAL EVENT INVOLVING A LOSS OF OFFSITE POWER (LOOP) COINCIDENT | | WITH A DESIGN BASIS LOSS OF COOLANT ACCIDENT (LOCA) AND THE FAILURE OF THE | | '2B' EDG | | | | THE LICENSEE HAS BEEN IN THE PROCESS OF REVISING THE EDG ACCIDENT LOADING | | ANALYSIS AND HAS REVISED THE COMPUTER SIMULATION OF THE EDG RESPONSE TO | | LOADING OF THE EMERGENCY CORE COOLING SYSTEM LOADS. DURING THIS PROCESS, | | THE LICENSEE DISCOVERED A CONDITION THAT COULD RESULT IN THE LOSS OF THE | | '2A' EDG DURING A HYPOTHETICAL EVENT INVOLVING A LOOP COINCIDENT WITH A | | DESIGN BASIS LARGE BREAK LOCA AND THE FAILURE OF THE '2B' EDG. AT THIS | | FACILITY, THE '2A' EDG SUPPLIES POWER TO SAFETY INJECTION TRAIN 'B', AND | | THE '2B' EDG SUPPLIES POWER TO SAFETY INJECTION TRAIN 'A'. | | | | THE LICENSEE'S MODEL OF AN EVENT INVOLVING A LOOP/LOCA WITH A FAILURE OF | | THE '2B' EDG HAS DETERMINED THAT THE INITIAL LOADING SEQUENCE FOR THE '2A' | | EDG WOULD BE SUCCESSFUL. ONE OF THE SUBSEQUENT STEPS THAT WAS MODELED | | INVOLVED THE SWITCHING OF HIGH PRESSURE SAFETY INJECTION (HPSI) OVER TO | | SUMP RECIRCULATION PER THE EMERGENCY OPERATING PROCEDURES. DURING THIS | | PROCESS, THE 'B' HPSI PUMP WOULD BE RESTARTED FOLLOWING HPSI SYSTEM | | RE-ALIGNMENT TO THE CONTAINMENT SUMP. WHEN THIS OCCURS, THE MODEL HAS | | SHOWN THAT IT TAKES APPROXIMATELY 13.5 TO 14 SECONDS FOR THE PUMP TO | | RESTART. ALTHOUGH THE COMPUTER ANALYSIS SHOWS THAT THE PUMP WOULD | | SUCCESSFULLY START AFTER 14 SECONDS, THE AUTHORS OF THE ANALYSIS ARE NOT | | CONFIDENT THAT THE ANALYSIS IS NOW REPLICATING THAT THE EQUIPMENT WILL | | FUNCTION BECAUSE OF THE EXCESSIVE AMOUNT OF TIME FOR THE HPSI PUMP TO | | RESTART. THE AUTHORS ARE NOT CONFIDENT THAT THE '2A' EDG WOULD SUCCEED IN | | STARTING THE 'B' HPSI PUMP AND BELIEVE THAT THIS WOULD CAUSE THE '2A' EDG | | TO FAIL. BECAUSE THE LICENSEE CANNOT CONCLUDE SUCCESSFUL PERFORMANCE, IT | | IS CONSIDERING THE '2A' EDG TO BE INOPERABLE. THE UNIT IS NOT CURRENTLY IN | | ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT | | OF THIS ISSUE BECAUSE OF THE CURRENT MODE OF OPERATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO NOTIFY THE | | STATE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31259 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 10/31/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 10/31/96 | +------------------------------------------------+EVENT TIME: 11:55[CST]| |NRC NOTIFIED BY: PHILLIP A. SHORT |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 +------------------------------------------------------------------------------+ | TESTING ADEQUACY ISSUE DUE TO THE IDENTIFICATION OF RESIDUAL WATER COVERING | | THE SEATING AREA OF FEEDWATER CONTAINMENT ISOLATION CHECK VALVES | | | | FEEDWATER CONTAINMENT ISOLATION CHECK VALVES 1B21FO32A AND 1B21FO32B MAY | | HAVE BEEN TESTED IN THE PAST WITH SOME AMOUNT OF RESIDUAL WATER COVERING | | THE SEATING AREA. DURING REPAIR OF A VALVE FOLLOWING LEAK RATE TESTING | | WATER WAS FOUND IN THE VALVE BODY COVERING PART OF THE DISC/SEAT AREA. THIS | | IS BELIEVED TO BE DUE TO THE SLOPE OF THE FEEDWATER PIPING AND THE LOCATION | | OF THE DRAIN VALVES. THE UNIT IS NOT CURRENTLY IN ANY TECHNICAL | | SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A RESULT OF THIS ISSUE. | | | | THE LICENSEE HAS GENERATED A STATION CONDITION REPORT TO RESOLVE THIS | | PROBLEM AND PLANS TO DOCUMENT THIS ISSUE AS A SUPPLEMENT TO THE LICENSEE | | EVENT REPORT FOR A PREVIOUS EVENT INVOLVING FEEDWATER VALVE LOCAL LEAK RATE | | TESTING FAILURES. (REFER TO EVENT NUMBER 31151 FOR ADDITIONAL | | INFORMATION.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31260 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 10/31/96 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 16:18 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 10/31/96 | +------------------------------------------------+EVENT TIME: 15:00[CST]| |NRC NOTIFIED BY: R. H. SCHEIDE |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOESEPH TAPIA 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 98 POWER OPERATION | 98 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT, WITH A CHANNEL OF THE PLANT PROTECTION SYSTEM PLACED IN | | TRIP CHANNEL BYPASS, A LOSS OF OFFSITE POWER COINCIDENT WITH A SINGLE | | FAILURE OF A DC BUS MAY CAUSE THE LOSS OF AUTOMATIC INITIATION OF CERTAIN | | FUNCTIONS OF THE ENGINEERED SAFETY FEATURES ACTUATION SYSTEM (ESFAS) | | | | THE LICENSEE IDENTIFIED A CONDITION WHICH, UNDER CERTAIN CIRCUMSTANCES, MAY | | PLACE THE PLANT OUTSIDE OF ITS DESIGN BASIS. WITH A CHANNEL OF THE PLANT | | PROTECTION SYSTEM PLACED IN TRIP CHANNEL BYPASS, A LOSS OF OFFSITE POWER | | COINCIDENT WITH A SINGLE FAILURE OF A DC BUS MAY CAUSE THE LOSS OF | | AUTOMATIC INITIATION OF EMERGENCY FEEDWATER, CONTAINMENT ISOLATION, OR | | CONTAINMENT SPRAY FUNCTIONS OF THE ESFAS. | | | | THE ORIGINAL UNIT 2 TECHNICAL SPECIFICATIONS ONLY ALLOW A CHANNEL TO BE | | PLACED IN BYPASS FOR 48 HOURS BECAUSE OF CONCERNS WITH POTENTIAL COMMON | | MODE FAILURES OF THE REMAINING 3 CHANNELS. AMENDMENT #159 TO THE UNIT 2 | | TECHNICAL SPECIFICATIONS APPROVED PLACING AN ESFAS CHANNEL IN TRIP CHANNEL | | BYPASS UNTIL STARTUP FOLLOWING THE NEXT COLD SHUTDOWN. THE JUSTIFICATION | | FOR APPROVAL OF AMENDMENT #159 INCLUDED A CONCLUSION THAT, WITH A CHANNEL | | IN BYPASS, THERE WERE NO SINGLE FAILURES WHICH WOULD PREVENT THE PLANT | | PROTECTION SYSTEM FROM PERFORMING ITS SAFETY FUNCTION. UNTIL THIS | | CONDITION CAN BE RESOLVED, ADMINISTRATIVE CONTROLS ARE BEING IMPLEMENTED TO | | LIMIT THE TIME A CHANNEL MAY BE IN BYPASS TO 48 HOURS CONSISTENT WITH THE | | UNIT 2 LICENSING BASIS BEFORE AMENDMENT #159 WAS ISSUED. FURTHER REVIEW IS | | ONGOING TO DETERMINE IF THERE ARE ADDITIONAL IMPACTS FROM THIS CONDITION. | | THE UNIT IS NOT CURRENTLY IN ANY TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION AS A RESULT OF THIS DISCOVERY. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31261 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 10/31/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 16:57 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 10/31/96 | +------------------------------------------------+EVENT TIME: 16:50[EST]| |NRC NOTIFIED BY: RAY MARTIN |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES JOYNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT COTTER PINS WERE MISSING FROM THE SPINDLE NUTS ON 2 OF 20 | | STEAM GENERATOR SAFETY RELIEF VALVES | | | | THE LICENSEE FOUND THAT COTTER PINS WERE MISSING FROM THE SPINDLE NUTS ON | | THE TOP OF 2 STEAM GENERATOR SAFETY RELIEF VALVES ON THE MAIN STEAM SYSTEM, | | AND THE SPINDLE NUT COTTER PINS ON THE REMAINING 18 STEAM GENERATOR SAFETY | | RELIEF VALVES WERE FOUND TO BE IN PLACE. THE FUNCTION OF THE SPINDLE NUT | | IS TO PROVIDE A CAP FOR THE MANUAL LIFTING LEVER TO PULL AGAINST WHEN THE | | VALVE IS BEING OPENED MANUALLY. WITHOUT THE COTTER PIN, THE SPINDLE NUT HAS | | A TENDENCY TO WALK DOWN THE SHAFT, AND WHEN THE VALVE OPENS, IT WILL NOT | | RECLOSE. THEREFORE, THIS WOULD CAUSE THE SAFETY VALVE TO FAIL OPEN. | | | | THE VALVES IN QUESTION WERE LOCATED ON THE MAIN STEAM LINE FROM ONE STEAM | | GENERATOR, AND THE LICENSEE'S DESIGN BASIS ASSUMES THAT ONLY ONE VALVE WILL | | FAIL OPEN. THE UNIT IS NOT CURRENTLY IN ANY TECHNICAL SPECIFICATION | | LIMITING CONDITIONS FOR OPERATION AS A RESULT OF THIS ISSUE BECAUSE OF THE | | UNIT'S CURRENT MODE OF OPERATION. | | | | THE LICENSEE INSPECTED THESE VALVES DUE TO SIMILAR INDUSTRY ISSUES THAT HAD | | BEEN IDENTIFIED AT OCONEE AND ARKANSAS NUCLEAR ONE. (REFER TO EVENT | | NUMBERS 31238 AND 31248 FOR DETAILS ON THE OCONEE EVENTS.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31262 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 10/31/96 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 19:16 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 10/31/96 | +------------------------------------------------+EVENT TIME: 17:30[CST]| |NRC NOTIFIED BY: JACK GRANT |LAST UPDATE DATE: 10/31/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOESEPH TAPIA RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF OIL AND GREASE LEVELS IN A NEUTRALIZATION BASIN | | SAMPLE ABOVE PERMIT LIMITS | | | | THE LICENSEE NOTIFIED THE STATE DEPARTMENT OF NATURAL RESOURCE CONSERVATION | | COMMISSION THAT A NEUTRALIZATION BASIN SAMPLE WAS TESTED TO BE ABOVE THE | | PERMIT LIMIT OF 20 PPM FOR OIL AND GREASE. THE LABORATORY INDICATED THAT | | THE SAMPLE WAS CLEAR BUT THAT THE TEST RESULTS WERE INDICATING 112 PPM OIL | | AND GREASE. THE LABORATORY WAS NOT SURE WHY THE INDICATION WAS THIS HIGH, | | AND AN INVESTIGATION IS ONGOING. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+