U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/12/96 - 11/13/96 ** EVENT NUMBERS ** 30081 31297 31316 31317 31318 31319 31320 31321 31322 31323 31324 31325 31326 31327 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30081 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LANE CONSTRUCTION CORP, MERIDAN, CT |NOTIFICATION DATE: 03/08/96 | | CITY: MERIDAN REGION: 1 |NOTIFICATION TIME: 09:37 [ET]| | COUNTY: STATE: CT |EVENT DATE: 03/08/96 | |LICENSE#: 06-06284-02 AGREEMENT: N |EVENT TIME: 09:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/12/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE DOERFLEIN RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JAY CRUICKSHANK | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STOLEN TROXLER SOIL MOISTURE DENSITY GAUGE WITH SOURCE INTACT - | | | | BETWEEN 1730 ON MARCH 7, 1996, AND 0900 ON MARCH 8, 1996, A TROXLER SOIL | | MOISTURE DENSITY GAUGE INSIDE ITS STORAGE CASE WAS STOLEN FROM A LOCKED | | CABINET INSIDE A LOCKED STORAGE AREA AT THE LANE CONSTRUCTION CORPORATION | | CORPORATE OFFICE IN MERIDEN, CONNECTICUT. THE CORRECT NUCLEAR SYMBOL WAS | | ON THE GAUGE AND ITS CASE. THE RADIOACTIVE SOURCE IS 8 MILLICURIES OF | | CESIUM-137 AND 40 MILLICURIES OF AMERICIUM-241. THE COST OF THE GAUGE IS | | APPROXIMATELY $5,500. | | | | THE LICENSEE NOTIFIED THE LOCAL POLICE AND WILL SUBMIT A WRITTEN REPORT TO | | THE NRC WITHIN 30 DAYS. | | | | NOTE: REFER TO THE HOO LOG FOR A LICENSEE CONTACT TELEPHONE NUMBER. | | | | * * * 2018 NOVEMBER 11, 1996, UPDATE FROM THE CONNECTICUT RADIATION PROGRAM | | (KEVIN SCOTT) RECEIVED BY TROCINE * * * | | | | THE CONNECTICUT RADIATION PROGRAM DUTY OFFICER (KEVIN SCOTT) REPORTED THAT | | A TROXLER MOISTURE DENSITY GAUGE (MODEL #22276, SOURCE #75-3942) HAD BEEN | | FOUND IN BRANFORD, CONNECTICUT. LOCAL LAW ENFORCEMENT PERSONNEL DETERMINED | | THAT THE GAUGE WAS ORIGINALLY REPORTED TO BE STOLEN FROM LANE CONSTRUCTION | | IN MERIDAN, CONNECTICUT, DURING MARCH OF THIS YEAR. | | | | THE GAUGE WAS FOUND BEHIND AN EXCAVATION COMPANY GARAGE BY THE OWNER'S SON, | | AND THE BOY BROUGHT THE GAUGE HOME. THE EXCAVATION COMPANY'S OWNER | | RECOGNIZED THE GAUGE AND IMMEDIATELY CALLED THE LOCAL FIRE DEPARTMENT. THE | | CONNECTICUT RADIATION PROGRAM DUTY OFFICER RECEIVED NOTIFICATION OF THIS | | ISSUE AT 1856 VIA HIS INTERNAL EMERGENCY RESPONSE ORGANIZATION. HE | | RESPONDED TO THE SCENE AT 2001 AND PERFORMED SURVEYS OF THE GAUGE. THE | | DEVICE WAS FOUND TO BE INTACT AND LOCKED IN ITS SHIELDED POSITION. IT ALSO | | EXHIBITED NORMAL RADIATION READINGS FOR A TROXLER GAUGE IN THIS | | CONFIGURATION. IN ADDITION, THE CONNECTICUT RADIATION PROGRAM DUTY OFFICER | | PLANS TO INTERVIEW THE INDIVIDUAL WHO FOUND THE GAUGE TO DETERMINE IF HE IN | | ANY WAY UNSHIELDED THE SOURCE. | | | | THE CONNECTICUT RADIATION PROGRAM DUTY OFFICER STATED THAT LANE | | CONSTRUCTION HAD NOT YET BEEN INFORMED BUT THAT THE COMPANY WOULD PROBABLY | | BE NOTIFIED TOMORROW MORNING. THE NRC OPERATIONS CENTER NOTIFIED THE R1DO | | (CONTE). (REFER TO THE HOO LOG FOR CONTACT TELEPHONE NUMBERS FOR THE | | CONNECTICUT RADIATION PROGRAM DUTY OFFICER.) | | | | * * * 1424 NOVEMBER 12, 1996, FROM LANE CONSTRUCTION CORPORATION (JAY | | CRUICKSHANK) RECEIVED BY TROCINE * * * | | | | A STOLEN GAUGE WAS RETURNED TO LANE CONSTRUCTION TODAY. THE DEVICE WAS | | FOUND LAST NIGHT, AND THE BRANFORD POLICE DEPARTMENT NOTIFIED THE STATE | | DEPARTMENT OF ENVIRONMENTAL PROTECTION. THE GAUGE WAS CHECKED AND WAS NOT | | LEAKING. EVERYTHING APPEARS TO BE INTACT. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R1DO (BARKLEY). (REFER TO THE HOO | | LOG FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 31297 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: N.C. DIV. OF RAD PROTECTION |NOTIFICATION DATE: 11/08/96 | | CITY: RALEIGH REGION: 2 |NOTIFICATION TIME: 10:47 [ET]| | COUNTY: STATE: NC |EVENT DATE: 11/01/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 09:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/12/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: GERALD SPEIGHT | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NORTH CAROLINA DIVISION OF RADIATION PROTECTION WAS NOTIFIED BY TROXLER | | ELECTRONICS LABS, THAT A TROXLER MOISTURE DENSITY GAUGE (MODEL #4232, | | SERIAL #261) WAS MISPLACED. THIS OCCURRED WHEN A TROXLER EMPLOYEE SENT | | THIS EQUIPMENT BY FEDEX FROM ATLANTA, GEORGIA, TO TROXLER FACILITIES IN | | RALEIGH, NORTH CAROLINA. FEDEX IS CURRENTLY LOOKING FOR THE DEVICE. THEY | | HAVE SEARCHED THEIR ATLANTA TERMINAL AND THEIR HUB IN MEMPHIS, BUT THEY | | HAVE NOT FOUND THE DEVICE. THE DEVICE CONTAINED 100 MICROCURIES OF | | CALIFORNIUM. THE STATE DID NOT NOTIFY THE NRC IMMEDIATELY BECAUSE THEY | | THOUGHT THE GAUGE WOULD HAVE BEEN FOUND BEFORE NOW. | | | | * * * 1456 NOVEMBER 12, 1996, UPDATE FROM SPEIGHT RECEIVED BY TROCINE * * * | | | | THE NORTH CAROLINA DIVISION OF RADIATION PROTECTION WAS NOTIFIED THAT THE | | MISSING TROXLER GAUGE HAD BEEN LOCATED AND WAS BEING SHIPPED TO THE TROXLER | | FACILITIES LOCATED IN RALEIGH, NORTH CAROLINA. THE NORTH CAROLINA | | DEPARTMENT OF RADIATION PROTECTION PLANS TO NOTIFY THE NORTH CAROLINA STATE | | EMERGENCY PLANNING OFFICE, THE ENVIRONMENTAL PROTECTION AGENCY, AND THE | | GEORGIA DEPARTMENT OF RADIATION PROTECTION. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (BARR). (REFER TO THE HOO LOG | | FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31316 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 01:30 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/11/96 | +------------------------------------------------+EVENT TIME: 23:05[CST]| |NRC NOTIFIED BY: SCOTT SANDBOTHE |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 20 POWER OPERATION | 1 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED AN UNPLANNED FEEDWATER ISOLATION SIGNAL DUE TO A | | HIGH-HIGH LEVEL ON THE "A" STEAM GENERATOR (SG). | | | | UNIT 1 WAS RETURNING TO POWER AFTER COMPLETING REFUELING OUTAGE 9. POWER | | WAS INCREASING AT APPROXIMATELY 20% AFTER SYNCHRONIZING THE GENERATOR TO | | THE GRID AND COMPLETING THE VALVE SWAP FROM FEEDWATER BYPASS TO MAIN | | FEEDWATER REG VALVES. AT THAT POINT, OPERATORS OBSERVED LEVELS IN THE "A" | | AND "D" SGs TRENDING DOWN, WHILE LEVELS IN THE "B" AND "C" WERE TRENDING | | UP. ATTEMPTS TO STABILIZE LEVELS BY SHIFTING THE MFRV CONTROLLERS BETWEEN | | AUTO AND MANUAL WERE UNSUCCESSFUL; i.e., THE "A" SG WAS OVERFED, RESULTING | | IN A FEEDWATER ISOLATION AND TURBINE TRIP AT 78% LEVEL (NARROW RANGE). BOTH | | MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS STARTED AS EXPECTED. OPERATORS | | REDUCED POWER TO 1% AND ARE CONTROLLING AFW IN MANUAL TO MAINTAIN SG LEVEL | | AT 50% (NARROW RANGE). THE LICENSEE IS IN THE PROCESS OF RESTORING THE "B" | | MAIN FEEDWATER PUMP. UNIT 1 BRIEFLY ENTERED TS A/S 3.1.1.4 (MINIMUM | | TEMPERATURE FOR CRITICALITY) WHICH REQUIRED THE RCS TEMPERATURE BE RESTORED | | TO 551øF WITHIN 15 MINUTES. THE LOWEST TEMPERATURE OBSERVED WAS 546øF. | | THIS WAS DUE TO THE TURBINE TRIP FOLLOWED BY THE RAPID DOWN POWER AND USE | | OF AFW. THE A/S WAS EXITED AFTER APPROXIMATELY 7 MINUTES. A PROBLEM | | INVOLVING DUAL INDICATION OF THE "C" MAIN FEEDWATER ISOLATION VALVE WAS | | IDENTIFIED AND IS BEING CORRECTED. THE LICENSEE HAS ASSEMBLED AN EVENT | | REVIEW TEAM TO DETERMINE THE ROOT CAUSE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31317 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 05:40 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 04:02[CST]| |NRC NOTIFIED BY: SCOTT SANDBOTHE |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DALE POWERS 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 1 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 COMPLETED A TECH SPEC REQUIRED SHUTDOWN FOLLOWING THE HIGH VIBRATION | | TRIP OF REACTOR COOLANT PUMP (RCP) "B". | | | | AT 0242 CST RCP "B" TRIPPED ON HIGH VIBRATION. THIS PLACED UNIT 1 IN TS | | 3.4.1.1 WHICH REQUIRES ALL REACTOR COOLANT LOOPS OPERABLE IN MODE 1 AND 2 | | OTHERWISE BE IN MODE 3 WITHIN THE FOLLOWING 6 HOURS. AT 0402 CST THE | | LICENSEE COMMENCED A SHUTDOWN ENTERING MODE 3 AT 0430 CST. CURRENT PLANT | | CONDITIONS ARE RCS AT NORMAL OPERATING TEMPERATURE AND PRESSURE WITH | | SHUTDOWN BANK CONTROL RODS WITHDRAWN. DECAY HEAT IS BEING REMOVED VIA THE | | MAIN CONDENSER. ALL OFFSITE POWER SOURCES ARE AVAILABLE WITH NO | | SAFETY-RELATED EQUIPMENT OUT-OF-SERVICE. THE LICENSEE WILL MAINTAIN THE | | UNIT IN MODE 3 WHILE TROUBLESHOOTING RCP "B". | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31318 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MONTICELLO REGION: 3 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: MN |NOTIFICATION TIME: 10:44 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 09:30[CST]| |NRC NOTIFIED BY: DANE HASBROUCK |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR SCRAM FOLLOWING DUAL RECIRCULATION PUMP TRIP. | | | | DURING PERFORMANCE OF AN RHR INTERLOCK TEST, A TEST JUMPER WAS INSTALLED ON | | THE WRONG RELAY RESULTING IN A DUAL RECIRCULATION PUMP TRIP. PER ABNORMAL | | OPERATING PROCEDURE C.4, OPERATORS MANUALLY SCRAMMED THE REACTOR. ALL | | CONTROL RODS FULLY INSERTED. REACTOR WATER LEVEL DECREASED FROM THE NORMAL | | OPERATING LEVEL OF 35" TO 5" CAUSING A PARTIAL GROUP II ISOLATION. | | INVOLVING SEVERAL CHEMISTRY SAMPLE VALVES. THE UNIT IS CURRENTLY IN HOT | | SHUTDOWN REJECTING DECAY HEAT TO THE MAIN CONDENSER. THERE ARE NO SAFETY | | SYSTEMS OUT-OF-SERVICE AT THIS TIME. ALL SYSTEMS RESPONDED AS EXPECTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31319 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 11/12/96 | |UNIT: [ ] [2] [ ] STATE: VA |NOTIFICATION TIME: 10:54 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 08:54[EST]| |NRC NOTIFIED BY: CROSSMAN |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ 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 STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A REACTOR TRIP FROM 100% POWER DUE TO A TURBINE TRIP. | | | | THIS OCCURRED AFTER A GENERATOR DIFFERENTIAL LOCKOUT RELAY ACTUATED | | RESULTING IN A U2 TURBINE TRIP. THE TURBINE TRIP CAUSED THE REACTOR TRIP. | | THE CAUSE OF THE GENERATOR DIFFERENTIAL LOCKOUT RELAY ACTUATION IS UNKNOWN | | AND BEING INVESTIGATED. NO INJECTION OCCURRED AND NO STEAM GENERATOR OR | | PRESSURIZER SAFETY RELIEF VALVES LIFTED. ALL RODS FULLY INSERTED, BUT ONE | | ROD ("D4") INDICATED 15 STEPS AFTER THE TRIP, SO BORATION WAS INITIATED. | | THE PLANT HAD AUX FEED WATER AUTO ACTUATION, AS EXPECTED, FOR APPROXIMATELY | | 35 MINUTES BEFORE BEING PLACED BACK TO AUTO POSITION. THE UNIT ALSO | | EXPERIENCED SOME MINOR EQUIPMENT PROBLEMS WHEN AN INTERMEDIATE RANGE | | NUCLEAR INSTRUMENT WAS OVER COMPENSATED AND A MOISTURE SEPARATOR REHEAT | | VALVE DID NOT CLOSE AUTOMATICALLY. THE HEAT SINK IS THE CONDENSER VIA THE | | STEAM GENERATORS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED. THE LICENSEE MAY ISSUE A PRESS | | RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31320 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 11/12/96 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 11:27 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 03:45[CST]| |NRC NOTIFIED BY: TIM KOLB |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LPCI WAS DECLARED INOPERABLE DUE TO THE FAILURE OF A CHECK VALVE TO RESEAT. | | | | DURING POST-MAINTENANCE TESTING FOLLOWING BREAKER REPLACEMENT, THE "2D" RHR | | PUMP DISCHARGE CHECK VALVE FAILED TO RESEAT AFTER THE PUMP WAS SECURED. | | THIS CAUSED THE LOW PRESSURE COOLANT INJECTION (LPCI) SYSTEM TO LOSE | | KEEP-FILL PRESSURE AND LPCI DECLARED INOPERABLE. THIS PLACED THE UNIT IN | | THE 7 DAY LCO A/S 3.5.A.2 WHICH REQUIRES VERIFICATION OF OTHER ECCS | | SYSTEMS. AT 0426 CST THE KEEP-FILL PRESSURE WAS RESTORED AND THE LPCI | | SYSTEM DECLARED OPERABLE. AT 0915 CST THE LICENSEE DETERMINED THAT THIS | | EVENT WAS REPORTABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31321 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 12:32 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 12:12[EST]| |NRC NOTIFIED BY: MIKE BIGIARELLI |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED AUTOMATIC START OF THE EMERGENCY DIESEL GENERATOR (EDG) DURING | | THE PERFORMANCE OF AN UNRELATED SURVEILLANCE TEST | | | | THE LICENSEE WAS IN THE PROCESS OF BLEEDING DOWN THE AIR START HEADER IN | | ORDER TO TEST THE START FEATURE OF A DC AIR COMPRESSOR ASSOCIATED WITH THE | | EDG AIR START SYSTEM. SOME PROBLEMS WERE ENCOUNTERED DURING THE | | PERFORMANCE OF THIS SURVEILLANCE TEST, AND THE EDG AIR START SOLENOIDS | | SENSED A DIFFERENTIAL PRESSURE. THE AIR START VALVE SUBSEQUENTLY OPENED, | | AND THE EDG AUTOMATICALLY STARTED. AFTER STARTING, THE EDG CAME UP TO | | SPEED BUT DID NOT LOAD. IT HAS SINCE BEEN SECURED. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT. THE UNIT IS NOT | | CURRENTLY IN ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION | | DUE TO THIS EVENT BECAUSE THE UNIT IS DEFUELED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31322 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [2] [ ] STATE: TX |NOTIFICATION TIME: 14:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/06/96 | +------------------------------------------------+EVENT TIME: 16:56[CST]| |NRC NOTIFIED BY: PAUL COX |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 N 0 COLD SHUTDOWN | 0 HOT SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SEVERAL CLASS-1E 480-V BREAKERS WERE FOUND TO BE IN THE 'REMOVED' POSITION | | WHICH WAS DETERMINED TO BE A NON-SEISMICALLY QUALIFIED CONDITION. (SIMILAR | | EVENTS WERE REPORTED BY SUSQUEHANNA, THREE MILE ISLAND, AND OYSTER CREEK. | | REFER TO EVENT NUMBERS 31279, 31323, AND 31325 FOR ADDITIONAL INFORMATION.) | | | | AT 1455 CST ON NOVEMBER 6, 1996, THE LICENSEE WAS NOTIFIED OF AN EVENT AT | | SUSQUEHANNA WHICH POTENTIALLY AFFECTED THE SEISMIC CAPABILITY OF THE | | CLASS-1E 480-V AND 6.9-V SWITCHGEARS. IN RESPONSE TO THIS REPORTABLE | | CONDITION, LICENSEE ENGINEERING PERSONNEL CONDUCTED AN EVALUATION AS TO | | SAFETY-RELATED SWITCHGEAR BEING PLACED IN A POTENTIALLY NON-SEISMICALLY | | QUALIFIED CONDITION. THE CONDITION IN QUESTION WAS THE IMPACT OF A BREAKER | | ON A SAFETY BUS BEING RACKED TO A POSITION IN WHICH IT MAY NOT BE PROPERLY | | RESTRAINED. SPECIFICALLY, BREAKERS NOT IN THE 'CONNECT,' 'TEST,' OR | | 'DISCONNECT' POSITION MAY NOT BE SEISMICALLY RESTRAINED AND MAY PLACE THE | | ENTIRE ASSOCIATED BUS IN A CONDITION OUTSIDE THE DESIGN BASIS. | | | | THE COMANCHE PEAK CONTROL ROOM STAFF WAS NOTIFIED OF THIS ISSUE AT 1656 CST | | ON NOVEMBER 6, 1996, AND A WALKDOWN WAS IMMEDIATELY CONDUCTED TO DETERMINE | | THE ACTUAL POSITION OF ALL SAFETY-RELATED 6.9-KV AND 480-V SWITCHGEAR | | BREAKERS. SEVERAL CLASS-1E 480-V BREAKERS WERE FOUND TO BE IN THE | | 'REMOVED' POSITION, AND ALL WERE SUBSEQUENTLY PLACED IN EITHER THE | | 'CONNECT' OR 'DISCONNECT' POSITIONS (SEISMICALLY QUALIFIED POSITIONS). ALL | | 6.9-KV BREAKERS WERE FOUND TO BE PROPERLY POSITIONED. AT 1255 CST ON | | NOVEMBER 12, 1996, ADDITIONAL EVALUATION BY ENGINEERING AND LICENSING | | PERSONNEL DETERMINED THAT THIS CONDITION MET THE REPORTABILITY CRITERIA. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31323 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: THREE MILE ISLAND REGION: 1 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 14:56 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 14:20[EST]| |NRC NOTIFIED BY: MAX NELSON |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4160-VOLT AC SWITCHGEAR USING WESTINGHOUSE CIRCUIT BREAKERS ARE NOT | | SEISMICALLY QUALIFIED WHEN THE CIRCUIT BREAKERS ARE IN THE 'RACKED-OUT' | | POSITION. (SIMILAR EVENTS WERE REPORTED BY SUSQUEHANNA, COMANCHE PEAK, AND | | OYSTER CREEK. REFER TO EVENT NUMBERS 31279, 31322, AND 31325 FOR | | ADDITIONAL INFORMATION.) | | | | WHEN WESTINGHOUSE MODEL-50-DHP-250, 4160-VOLT, AC, CIRCUIT BREAKERS ARE IN | | THE 'RACKED-OUT' POSITION THE SWITCHGEAR IS NOT SEISMICALLY QUALIFIED. THE | | LICENSEE PRESENTLY HAS 2, CLASS-1E, 4160-VOLT, AC, BUSES THAT ARE AFFECTED. | | THE '1D' SAFETY-RELATED CLASS-1E BUS HAS A RACKED-OUT CIRCUIT BREAKER FOR | | THE THIRD HIGH PRESSURE INJECTION PUMP, AND THE '1E' BUS HAS A RACKED-OUT | | SPARE CIRCUIT BREAKER. THE LICENSEE CURRENTLY PLANS TO PHYSICALLY REMOVE | | THE RACKED-OUT BREAKERS TO RESTORE SEISMIC QUALIFICATION TO THE AFFECTED | | SWITCHGEAR. THIS IS A GENERIC WESTINGHOUSE ISSUE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31324 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 15:46 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 13:09[CST]| |NRC NOTIFIED BY: MARK KAUL |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | IDENTIFICATION OF A 10 CFR PART 50, APPENDIX 'R,' VULNERABILITY INVOLVING | | THE RESIDUAL HEAT REMOVAL (RHR) SYSTEM DURING AN ALTERNATE SHUTDOWN FIRE | | | | NOTE: THIS ISSUE INVOLVES VALVE RHR-MOV-MO39B, RHR SYSTEM OUTBOARD | | ISOLATION SUPPLY VALVE FOR SUPPRESSION POOL COOLING; VALVES RHR-MOV-MO15B | | AND RHR-MOV-MO15D, RHR SUCTION INTERLOCKS TO THE REACTOR VESSEL FOR | | SHUTDOWN COOLING; AND RELAY RHR-REL-K120B, INTERLOCK RELAY WHICH PREVENTS | | THE OPENING OF VALVE RHR-MOV-MO39B WHEN EITHER VALVE RHR-MOV-MO15B OR VALVE | | RHR-MOV-MO15D IS OPEN. | | | | AS PART OF AN ONGOING APPENDIX 'R' VALIDATION EFFORT, IT WAS DISCOVERED | | THAT DURING AN ALTERNATE SHUTDOWN FIRE, VALVE RHR-MOV-MO39B IS VULNERABLE | | TO A SPURIOUS OPENING OF VALVE RHR-MOV-MO15B WHICH AFFECTS THE 'OPEN' | | INTERLOCK THROUGH RELAY RHR-REL-K120B. THIS INTERLOCK IS NOT ISOLATED BY | | THE ALTERNATE SHUTDOWN PANEL ISOLATION SWITCH BECAUSE THE RELAY IS NOT | | LOCATED IN ONE OF THE ALTERNATE SHUTDOWN AREAS. IT IS LOCATED INTERNAL TO | | MCC-Y (REACTOR BUILDING #903 SOUTH). VALVE RHR-MOV-MO15D PROVIDES THE SAME | | INTERLOCK, BUT IT IS CONTROLLED FROM THE ALTERNATE SHUTDOWN PANEL AND DOES | | NOT POSE A PROBLEM WITH SPURIOUS OPERATION. VALVE RHR-MOV-MO39B IS | | REQUIRED TO BE OPENED APPROXIMATELY 3 HOURS FOLLOWING AN ALTERNATE SHUTDOWN | | FIRE IN ORDER TO SUPPORT SUPPRESSION POOL COOLING. | | | | A FIRE WATCH HAS BEEN IN PLACE FOR THE AFFECTED AREAS SINCE JULY 25, 1996, | | AND A 1-HOUR ROVING PATROL IS ALSO CURRENTLY IN PLACE. IN ADDITION, THE | | LICENSEE PLANS TO INITIATE A PROCEDURE REVISION DIRECTING LOCAL CONTROL TO | | OPEN VALVE RHR-MOV-MO39B. | | | | THIS INFORMATION IS SUPPLEMENTAL TO THE PREVIOUS REPORTS OF JULY 25, 1996, | | AND AUGUST 13, 1996. THE LICENSEE PLANS TO DOCUMENT IT FULLY IN THE FINAL | | SUPPLEMENT TO LICENSEE EVENT REPORT LER-96-009. (REFER TO EVENT #30787 FOR | | ADDITIONAL INFORMATION.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31325 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:28 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 15:10[EST]| |NRC NOTIFIED BY: STEVE FULLER |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TWO 4160-VOLT SWITCHGEAR BREAKERS WERE FOUND TO BE IN THE 'RACKED-OUT' | | POSITION WHICH WAS DETERMINED TO BE IN A NON-SEISMICALLY QUALIFIED | | POSITION. (SIMILAR EVENTS WERE REPORTED BY SUSQUEHANNA, COMANCHE PEAK, AND | | THREE MILE ISLAND. REFER TO EVENT NUMBERS 31279, 31322, AND 31323 FOR | | ADDITIONAL INFORMATION.) | | | | IT WAS DETERMINED THAT 4160-VOLT SWITCHGEAR CIRCUIT BREAKERS WERE | | SEISMICALLY ANALYZED WITH ALL CIRCUIT BREAKERS IN THE 'RACKED-IN' POSITION, | | AND OYSTER CREEK HAS TWO CIRCUIT BREAKERS IN THE 'RACKED-OUT' POSITION. | | THIS REPRESENTS AN UNANALYZED CONDITION. THE BREAKERS IN QUESTION ARE | | EMERGENCY TIE BREAKERS THAT ARE ONLY RACKED IN WHEN THE UNIT IS IN A COLD | | SHUTDOWN CONDITION TO ALLOW THE LICENSEE TO CROSS TIE THE VITAL 4160-VOLT | | BUSES. | | | | THE BREAKERS ARE CURRENTLY IN THE 'RACKED-OUT' POSITION; HOWEVER, THE | | LICENSEE PLANS TO PHYSICALLY REMOVE THESE BREAKERS FROM THE SWITCHGEAR | | CABINETS AND SECURE THEM SEISMICALLY IN THE SWITCHGEAR ROOMS. THE UNIT IS | | NOT IN ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR OPERATION AS A | | RESULT OF THIS ISSUE. THE LICENSEE DISCOVERED THAT OTHER FACILITIES HAD | | MADE A SIMILAR DETERMINATION THAT APPLIED TO OYSTER CREEK AT 1510 TODAY AND | | DETERMINED THAT THIS EVENT MET THE CRITERIA FOR A ONE-HOUR REPORT AT | | APPROXIMATELY 1720. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31326 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 19:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: JOHN ROBERTSON |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A POTENTIAL GENERIC ISSUE INVOLVING THE EMERGENCY DIESEL | | GENERATOR (EDG) INLET SERVICE WATER CONTROL VALVES (36000 SERIES CONTROL | | BALL VALVES MANUFACTURED BY MASONEILAN) | | | | APPROXIMATELY 5 MINUTES AFTER THE START OF THE '2B' EDG DURING MONTHLY | | TESTING, THE LOCAL OPERATOR FOUND THE INLET SERVICE WATER CONTROL VALVE TO | | BE CLOSED. THIS VALVE IS DESIGNED TO OPEN AUTOMATICALLY UPON AN EDG START. | | IN THIS INSTANCE, THE MANUAL ACTUATOR PREVENTED THE VALVE FROM PROPERLY | | OPENING, AND THE EDG WAS IMMEDIATELY SECURED. UPON FURTHER REVIEW, IT WAS | | DISCOVERED THAT A SPRING CLIP DESIGNED TO HOLD THE MANUAL ACTUATOR IN A | | FULLY WITHDRAWN POSITION HAD BROKEN. ALL SIX EDGs WERE CHECKED FOR THIS | | CONDITION, AND NO OTHER SPRING CLIPS WERE FOUND TO BE BROKEN. HOWEVER, THE | | INLET SERVICE WATER VALVES FOR THE OTHER FIVE EDGs WERE FOUND TO BE | | IMPROPERLY SET UP TO PREVENT THIS TYPE OF OCCURRENCE. THE MANUAL WHEELS | | FOR THESE VALVES WERE NOT IN THE FULLY WITHDRAWN POSITION. | | | | ALL INLET SERVICE WATER VALVES HAVE SINCE BEEN PROPERLY POSITIONED AND | | VERIFIED FOR ALL EDGs. HOWEVER, SIMILAR VALVES MAY BE IN USE IN OTHER | | PLANT SYSTEMS, AND THE LICENSEE PLANS TO CONDUCT A REVIEW TO ENSURE THAT | | ANY OTHER VALVES OF THIS TYPE ARE PROPERLY SET UP IF THEY EXIST. AS A | | RESULT OF THIS INVESTIGATION, THE LICENSEE ALSO BELIEVES THAT OPERATIONS | | PERSONNEL ARE NOT PROPERLY TRAINED ON THE PROPER SET UP OF THIS TYPE OF | | VALVE. THE LICENSEE PLANS TO CONDUCT TRAINING FOR OPERATIONS PERSONNEL. | | (THE VALVE REFERENCED IS A 36000 SERIES CONTROL BALL VALVE MANUFACTURED BY | | MASONEILAN.) | | | | THE LICENSEE HAS NOTIFIED THE LOWER ALLOWAYS CREEK TOWNSHIP AND PLANS TO | | NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31327 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/12/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 20:15 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/12/96 | +------------------------------------------------+EVENT TIME: 20:02[EST]| |NRC NOTIFIED BY: MIKE BIGIARELLI |LAST UPDATE DATE: 11/12/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY 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 +------------------------------------------------------------------------------+ | DISCOVERY OF INCONSISTENCIES BETWEEN THE DESIGN BASIS AND THE SURVEILLANCE | | TESTING AND OPERATION OF THE EMERGENCY DIESEL GENERATOR (EDG) AIR START | | SYSTEM | | | | DURING AN ENGINEERING REVIEW, THE LICENSEE DETERMINED THAT SURVEILLANCE | | TESTING AND OPERATION HAVE NOT BEEN PERFORMED CONSISTENT WITH THE DESIGN | | BASIS. SPECIFICALLY, THERE IS AN EDG REQUIREMENT IN THE DESIGN BASIS FOR | | THE AIR START SYSTEM TO BE CAPABLE OF SUPPLYING SUFFICIENT AIR FOR 3 COLD | | STARTS OF THE EDG AND THAT THE STARTING PRESSURE SHOULD BE 250 PSIG, AND IT | | WAS IDENTIFIED THAT THE COMPRESSORS THAT CHARGE THE AIR RECEIVERS ACTUALLY | | START AT APPROXIMATELY 225 PSIG. THE AC AIR COMPRESSOR IS DESIGNED TO | | START AT 225 PSIG, THE DC COMPRESSOR IS DESIGNED TO START AT 220 PSIG, AND | | BOTH COMPRESSORS ARE DESIGNED TO SHUT OFF WHEN THE PRESSURE IN THE | | RECEIVERS REACHES APPROXIMATELY 250 PSIG. THE SYSTEM ALSO HAS A LOW | | PRESSURE ALARM THAT IS DESIGNED TO COME IN AT 175 PSIG. THE PRESSURE IN | | THE AIR RECEIVERS IS CHECKED TWICE EVERY 24 HOURS DURING OPERATOR ROUNDS, | | AND THE MINIMUM PRESSURE ON THE CHECK LIST IS 200 PSIG. THEREFORE, | | OPERATIONALLY, THE PRESSURE IN THE RECEIVERS WOULD BE SOMEWHERE BETWEEN 225 | | PSIG AND 250 PSIG. THE PRE-OPERATIONAL TESTING WAS PERFORMED AT 250 PSIG, | | BUT SINCE THAT TIME, THE LICENSEE CANNOT BE SURE THAT A MINIMUM OF 250 PSIG | | HAS BEEN MAINTAINED IN THE AIR RECEIVERS. | | | | THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION LIMITING CONDITIONS FOR | | OPERATION AS A RESULT OF THIS EVENT BECAUSE THE UNIT IS CURRENTLY DEFUELED. | | THE LICENSEE BELIEVES THAT THERE WAS NO AFFECT ON THE PLANT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL AGENCIES. | +------------------------------------------------------------------------------+