U.S. Nuclear Regulatory Commission Operations Center Event Reports For 02/10/95 - 02/13/95 ** EVENT NUMBERS ** 28364 28365 28366 28367 28368 28369 28370 28371 28372 28373 28374 28375 +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 28364 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: WESTINGHOUSE HANFORD |NOTIFICATION DATE: 02/10/95 | | CITY: RICHLAND REGION: 4 |NOTIFICATION TIME: 02:21 [ET]| | COUNTY: BENTON STATE: WA |EVENT DATE: 02/09/95 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 11:00[PST]| | DOCKET: |LAST UPDATE DATE: 02/10/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAWRENCE YANDELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: NATIONAL RESPONCE CENTER | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER REPORTED THAT A FUEL TRUCK AT WESTINGHOUSE | | HANFORD HAD A LOOSE FITTING ON A TEMPERATURE HOUSING AND IT CAUSED THE | | RELEASE OF APPROXIMATELY 4LBS OF ETHYLENE GLYCOL(50% WATER SOLUTION) TO THE | | GROUND AT THE FACILITY. THE SOIL WAS EXCAVATED AND ALL OF THE MATERIAL WAS | | RECOVERED. DOE AND EPA HAVE BEEN NOTIFIED BY THE NATIONAL RESPONSE CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28365 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/10/95 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 08:13 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/10/95 | +------------------------------------------------+EVENT TIME: 07:15[EST]| |NRC NOTIFIED BY: KLINE |LAST UPDATE DATE: 02/10/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED AN ATTEMPT TO INTRODUCE CONTRABAND INTO THE PA. | | IMMEDIATE COMPENSATORY MEASURES WERE TAKEN ON DISCOVERY. SEE HOO LOG BOOK | | FOR DETAILS. THE RI WAS INFORMED ALONG WITH LOCAL AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28366 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 02/10/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 12:29 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 02/10/95 | +------------------------------------------------+EVENT TIME: 10:56[CST]| |NRC NOTIFIED BY: DAN UMSHLER |LAST UPDATE DATE: 02/10/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |AL CHAFFEE EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |CANUPP FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 5 STARTUP | 0 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED BASED ON A TECH SPEC REQUIRED SHUTDOWN | | | | THE PLANT DECLARED AN UNUSUAL EVENT BASED ON THE INITIATION OF A SHUTDOWN | | REQUIRED BY TECH SPECS. THE SHUTDOWN IS REQUIRED BY TECH SPECS 3.5.E & | | 3.6.D DUE TO THE FAILURE OF SAFETY RELIEF VALVES (SRVs) E,G & H. THE | | FAILURES WERE DETECTED DURING THE PERFORMANCE OF SURVEILLANCE PROCEDURE | | 6.3.2.1 (AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) MANUAL VALVE ACTUATION). | | ALL THREE VALVES (E,G & H) ARE PART OF THE ADS SYSTEM. COOPER HAS EIGHT | | SRVs, SIX OF WHICH ARE PART OF THE ADS SYSTEM. THE REMAINING SRVs WERE | | TESTED SATISFACTORILY. | | | | THE REACTOR WAS IN STARTUP FROM AN OUTAGE WITH REACTOR POWER AT 5% AND | | REACTOR PRESSURE AT 300 PSIG WHEN THE FAILURES WERE DISCOVERED. THE THREE | | SRVs THAT FAILED WERE PURCHASED FULLY TESTED & CERTIFIED THROUGH THE | | GENERAL ELECTRIC COMPANY FROM THE SHOREHAM NUCLEAR STATION. THE VALVES | | WERE INSTALLED DURING THE JUST COMPLETED OUTAGE. THE REMAINING SRVs WERE | | TESTED, RE-CERTIFIED & REINSTALLED DURING THE JUST COMPLETED OUTAGE. | | THE PLANT IS PROCEEDING TO COLD SHUTDOWN TO DETERMINE THE CAUSE OF THE | | FAILURES. THE UE WILL MOST LIKELY BE TERMINATED WHEN THE PLANT REACHES | | COLD SHUTDOWN. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE | | APPROPRIATE STATE AND LOCAL OFFICIALS. | | | | * * * UPDATE AT 0001 ON 02/11/95 BY REED ENTERED BY HOO JOLLIFFE * * * | | | | AT 2228 (CST) ON 02/10/95, THE PLANT ENTERED CONDITION 4 (COLD SHUTDOWN) | | AND LICENSEE TERMINATED THE UNUSUAL EVENT. LICENSEE NOTIFIED STATE AND | | LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR. HOO NOTIFIED R4DO YANDELL, | | NRR EO BRIAN GRIMES, AND FEMA STINEDURF. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28367 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 02/10/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 15:46 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 02/09/95 | +------------------------------------------------+EVENT TIME: 23:50[EST]| |NRC NOTIFIED BY: RUSS KEARNEY |LAST UPDATE DATE: 02/10/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT DEFAYETTE 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION BASED ON A CHLORINE RELEASE TO LAKE ERIE | | | | THE LICENSEE NOTIFIED THE OHIO DEPARTMENT OF ENVIRONMENTAL PROTECTION OF A | | CHLORINE RELEASE TO THE ENVIRONMENT WITH A DURATION OF GREATER THAN TWO | | HOURS. THE PLANT COMMENCED CHLORINATION OF THE SERVICE WATER INTAKE | | STRUCTURE AT 1700 ON 2/9/95. THE INTENT WAS TO CHLORINATE FOR ONE HOUR IN | | THE AUTOMATIC MODE. INSTEAD, THE CHLORINATION SYSTEM WAS LINED UP IN THE | | MANUAL MODE. INSTEAD OF AUTOMATICALLY TERMINATING AT 1800, CHLORINATION | | CONTINUED UNTIL 2350. THE CHLORINATION WAS TERMINATED WHEN A LOW LEVEL | | ALARM WAS NOTICED IN THE SUPPLY TANK. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. A PRESS RELEASE IS | | PLANNED FOR LATER TODAY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28368 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 02/10/95 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 16:52 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 02/10/95 | +------------------------------------------------+EVENT TIME: 16:52[EST]| |NRC NOTIFIED BY: MIKE FOWLKES |LAST UPDATE DATE: 02/11/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL 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 +------------------------------------------------------------------------------+ | INFORMATION CALL ABOUT POSSIBLE FAILURES IN SOLID STATE PROTECTION SYSTEM | | | | "ON 2/7/95 VCSNS ENGINEERING STAFF DETERMINED THAT A HIGH ENERGY LINE BREAK | | IN THE TURBINE BUILDING COULD RESULT IN FAILURE OF CIRCUITS WHICH PROVIDE | | INPUTS TO THE SOLID STATE PROTECTION SYSTEM (SSPS). FAILURE OF THESE | | CIRCUITS COULD RESULT IN THE DEGRADATION OF THE SSPS DUE TO LOSS OF LOGIC | | CIRCUITRY POWER SUPPLIES WHICH PROVIDE AUTOMATIC ACTUATION OF ESF EQUIPMENT | | FROM THE SYSTEM. THIS CONDITION HAS BEEN EVALUATED WITH RESPECT TO THE | | GUIDANCE PROVIDED IN GENERIC LETTER 91-18 FOR RESOLUTION OF A DEGRADED OR | | NONCONFORMING CONDITION. | | | | AN EVALUATION OF THE PLANTS DESIGN BASIS ACCIDENTS WITH RESPECT TO THIS | | DEGRADATION WAS CONDUCTED WITH THE CONCLUSION THAT THE MAIN STEAM LINE | | BREAK SAFETY ANALYSIS IS THE MOST LIMITING FOR THIS CONDITION AND THE | | SAFETY ANALYSIS ACCEPTANCE CRITERIA IS MET WITHOUT RELIANCE ON MANUAL | | OPERATOR ACTIONS FOR AT LEAST 10 MINUTES. AFTER THE 10 MINUTE DELAY MANUAL | | OPERATOR ACTIONS ARE CREDITED FOR ISOLATION OF THE FAULT, INITIATION OF | | EMERGENCY FEEDWATER FOR LONG TERM COOLING, AND ESTABLISHING CHARGING | | ALIGNMENT FOR THE RESTORATION OF SHUTDOWN MARGIN. | | | | THE SUCCESS OF THE MANUAL OPERATOR ACTIONS HAS BEEN VERIFIED THROUGH | | SIMULATOR SCENARIOS UTILIZING ESTABLISHED EMERGENCY OPERATING PROCEDURES. | | FURTHER, IT HAS BEEN DETERMINED THAT THE SSPS WILL BE CONSIDERED OPERABLE | | UNDER THE PRESENT DEGRADED CONDITIONS WITH CREDIT FOR MANUAL OPERATOR | | ACTIONS IAW SECTION 6.7 OF GL 91-18. THIS DETERMINATION IS MADE WITH THE | | UNDERSTANDING THAT PROMPT CORRECTIVE ACTIONS WILL BE TAKEN TO RESTORE THE | | SYSTEM AUTOMATIC FUNCTION FROM ITS PRESENT DEGRADED CONDITION. THE REPAIR | | DISPOSITION FOR THE NONCONFORMING CONDITION IS EXPECTED TO BE COMPLETED ON | | 2/11/95. A VOLUNTARY LER WILL BE PROVIDED AS A FOLLOWUP TO THIS REPORT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1549 ON 2/11/95 BY DAN GOLDSTON TAKEN BY WEAVER * * * | | | | REPAIRS ON THE SSPS HAVE BEEN COMPLETED. THIS COMPLETES ALL ACTION | | NECESSARY TO ADDRESS THIS DEGRADED CONDITION. THE AUTOMATIC FEATURES HAVE | | BEEN FULLY RESTORED & MANUAL OPERATOR ACTION IS NO LONGER REQUIRED. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HOO NOTIFIED THE RDO | | (CANTRELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 28369 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR INTERNATIONAL CORP. |NOTIFICATION DATE: 02/10/95 | | CITY: ST. PAUL REGION: 3 |NOTIFICATION TIME: 18:34 [ET]| | COUNTY: STATE: MN |EVENT DATE: 02/10/95 | |LICENSE#: 22-19174-01MD AGREEMENT: N |EVENT TIME: 00:00[CST]| | DOCKET: |LAST UPDATE DATE: 02/10/95 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ROBERT DEFAYETTE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DAVID PELLICCIARINI | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SYNCOR INTERNATIONAL CORPORATION | | | | A FUME HOOD USED TO CONTAIN XE-133 & I-131 LOST POWER FOR ABOUT FORTY | | MINUTES. NO RELEASE IN EXCESS OF REGULATORY LIMITS OCCURRED. POWER WAS | | RESTORED AND HOOD WAS RETURNED TO SERVICE. THIS REPORT WAS DELAYED BECAUSE | | THE FACILITY DID NOT REPORT THIS EVENT TO COMPANY HEADQUARTERS UNTIL TODAY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28370 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 02/11/95 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 04:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/10/95 | +------------------------------------------------+EVENT TIME: 23:40[PST]| |NRC NOTIFIED BY: PIERCE |LAST UPDATE DATE: 02/11/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 +------------------------------------------------------------------------------+ | - NON-CREDIBLE BOMB THREAT MADE FROM TELEPHONE OUTSIDE THE PLANT - | | | | AT 2319 (PST) ON 02/10/95, THE UNIT 1 SHIFT FOREMAN RECEIVED A BOMB THREAT | | OVER THE TELEPHONE FROM OUTSIDE THE PLANT. LICENSEE SEARCHED BOTH UNITS | | FOR AN EXPLOSIVE DEVICE; NONE WAS FOUND. LICENSEE CONCLUDED THAT THE | | THREAT WAS NOT CREDIBLE. | | | | LICENSEE NOTIFIED SAN LUIS OBISBO COUNTY OFFICIALS AND WILL INFORM THE NRC | | RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28371 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 02/11/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 11:37 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 02/10/95 | +------------------------------------------------+EVENT TIME: 12:30[EST]| |NRC NOTIFIED BY: STEFFENAUER |LAST UPDATE DATE: 02/11/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - IMPROPER CORE THERMAL POWER INSTRUMENT CALIBRATION CURVES BEING USED - | | | | DURING AN ENGINEERING EVALUATION, LICENSEE DISCOVERED THAT IMPROPER | | INSTRUMENT CALIBRATION CURVES WERE BEING USED FOR THE CALIBRATION OF CORE | | THERMAL POWER ON UNIT 2. THE IMPACT ON CORE THERMAL POWER CALCULATIONS IS | | MINIMAL PRODUCING AN ERROR OF APPROXIMATELY 0.024% IN A NONCONSERVATIVE | | DIRECTION. THUS, IF CORE THERMAL POWER CALCULATIONS INDICATED THAT UNIT 2 | | WAS OPERATING AT 100% POWER, IT WAS ACTUALLY OPERATING AT 100.024% POWER. | | THIS ERROR IS WELL WITHIN INSTRUMENT TOLERANCES OF +/- 0.25%. NO LICENSE | | SAFETY LIMITS WERE APPROACHED. BASED ON THIS ERROR IT IS POSSIBLE BUT HAS | | NOT BEEN VERIFIED THAT UNIT 2 MAY HAVE SLIGHTLY EXCEEDED ITS STEADY STATE | | POWER LIMIT OVER A SHIFT AVERAGE AND IS BEING REPORTED TO THE NRC PER NRC | | DOCUMENT #SSINS-0200, "DISCUSSION OF LICENSED POWER LEVEL" #AITS.F14580HZ, | | DATED 08/22/80. | | | | LICENSEE IMMEDIATE CORRECTIVE ACTIONS WERE TO REDUCE CORE THERMAL POWER BY | | 1 MEGAWATT THERMAL. LICENSEE VERIFIED THE FEEDWATER FLOW ERROR TO BE NO | | GREATER THAN 0.024% AT 100% INDICATED POWER. LICENSEE VERIFIED THAT NO | | SAFETY LIMITS WERE APPROACHED. LICENSEE IS INVESTIGATING THIS SITUATION. | | LICENSEE WILL SUBMIT AN LER ON THIS EVENT. | | | | UNIT 1 IS NOT AFFECTED BY THIS SITUATION. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28372 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 02/11/95 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 11:38 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 02/11/95 | +------------------------------------------------+EVENT TIME: 10:54[EST]| |NRC NOTIFIED BY: DUFFY |LAST UPDATE DATE: 02/11/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ACTUATION OF CONTAINMENT SPRAY PUMP & ENCLOSURE BUILDING FILTRATION FAN | | | | THE LICENSEE HAS JUST COMPLETED MAJOR MODIFICATIONS TO THE ENGINEERED | | SAFEGUARD FEATURES OF THE PLANT. TECH SPEC SURVEILLANCES WERE IN PROGRESS | | THAT WOULD ALSO SATISFY THE POST MAINTENANCE AND POST MODIFICATION TEST | | REQUIREMENTS. THE PLANT WAS TESTING THE BRAVO EMERGENCY DIESEL GENERATOR'S | | (EDG) ABILITY TO START & LOAD AFTER A LOSS OF NORMAL POWER. THE TEST ALSO | | INCLUDED A VERIFICATION OF THE LOCA SEQUENCER. THE TEST FAILED BECAUSE | | SEVERAL LOADS DID NOT START AS EXPECTED. | | | | THE LICENSEE DEENERGIZED ACTUATION CABINET SIX AS PART OF RESTORING FROM | | THE ABOVE TEST. DEENERGIZING ACTUATION CABINET SIX CAUSED A CONTAINMENT | | SPRAY PUMP AND THE ENCLOSURE BUILDING FILTRATION FAN TO START. THESE WERE | | IMMEDIATELY SECURED. THIS WAS AN UNEXPECTED RESPONSE AND IS THE REASON FOR | | THIS REPORT. THE LICENSEE IS CONTINUING TO INVESTIGATE THE PROBLEM. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28373 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 02/11/95 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 21:17 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 02/11/95 | +------------------------------------------------+EVENT TIME: 17:18[EST]| |NRC NOTIFIED BY: JOE MEYER |LAST UPDATE DATE: 02/11/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROBERT DEFAYETTE RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 10 STARTUP | 10 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ABNORMAL REACTOR PRESSURE VESSEL (RPV) WATER LEVEL INDICATIONS NOTED DURING | | TURBINE TESTING | | | | MONITORING EQUIPMENT WAS CONNECTED TO THE PLANT'S TESTABILITY CABINETS (1 | | PIECE OF MONITORING EQUIPMENT FOR EACH OF 2 DIVISIONS) FOR TRANSIENT | | MONITORING DURING TURBINE TESTING. THE PLANT STAFF NOTICED THAT THE WIDE | | RANGE RPV LEVEL INSTRUMENT IN THE CONTROL ROOM INDICATED A 10" LEVEL | | DECREASE. ALL OTHER RPV LEVEL AND PRESSURE INDICATIONS REMAINED NORMAL. | | | | THE MONITORING EQUIPMENT WAS DISCONNECTED & CONTROL ROOM INSTRUMENTATION | | RETURNED TO NORMAL VALUES. IT WAS DETERMINED THAT THE MONITORING | | EQUIPMENTS EFFECT ON PLANT INSTRUMENTATION OCCURRED @ 1718 WHEN IT WAS | | TURNED OFF. | | | | A REVIEW OF THE AFFECTED INSTRUMENTS SHOWED THAT THE LEVEL 8 TRIPS FOR HPCI | | & RCIC WERE NON-CONSERVATIVE, THE PLANTS TECH SPECS ALLOW 24 HOURS TO PLACE | | THE INOPERABLE CHANNELS IN A TRIPPED CONDITION. THE MONITORING EQUIPMENT | | WAS DISCONNECTED AND THE WIDE RANGE RPV LEVEL INDICATIONS WERE RESTORED TO | | NORMAL WITHIN 40 MINUTES. OTHER AFFECTED INDICATIONS WERE AFFECTED IN THE | | CONSERVATIVE DIRECTION. | | | | THE LICENSEE IS CONTINUING TO INVESTIGATE TO DETERMINE WHY THE MONITORING | | EQUIPMENT AFFECTED THE INSTRUMENTS. THE LICENSEE INDICATED THAT ALTHOUGH | | TURBINE TESTING HAS BEEN IN PROGRESS FOR SOME TIME, THIS IS THE FIRST TIME | | THAT LEVEL INDICATIONS WERE NOTED TO BE IN ERROR. THIS INFORMATION IS | | BASED ON A REVIEW OF THE CHART RECORDERS FOR LEVEL IN THE CONTROL ROOM. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28374 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 02/12/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 08:38 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 02/12/95 | +------------------------------------------------+EVENT TIME: 08:06[EST]| |NRC NOTIFIED BY: FULLER |LAST UPDATE DATE: 02/12/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 | 84 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - PLANT SHUTTING DOWN DUE TO 2 OF 5 REACTOR RECIRC PUMPS INOPERABLE - | | | | WITH 1 OF 5 Rx RECIRC PUMPS ('A') INOPERABLE DUE TO BEARING REPLACEMENT | | ON ITS M-G SET, THE 'D' Rx RECIRC PUMP TRIPPED FOR UNKNOWN REASONS. | | LICENSEE IS INVESTIGATING THE CAUSE. | | | | TECH SPEC LCO A/S 3.3.F REQUIRES LICENSEE TO PLACE THE PLANT IN AT LEAST | | HOT SHUTDOWN CONDITION WITHIN 12 HOURS WITH LESS THAN 4 RECIRC LOOPS | | OPERABLE. AT 0806, LICENSEE BEGAN REDUCING POWER AND THE PLANT WAS AT 84% | | POWER AT 0838. LICENSEE IS ATTEMPTING TO RESTORE AT LEAST ONE OF THE PUMPS | | TO OPERABLE STATUS PRIOR TO SHUTTING THE PLANT DOWN. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1205 ON 12/12/95 BY FULLER TAKEN BY WEAVER * * * | | | | THE LICENSEE COMPLETED REPAIRS ON THE 'A' RECIRC PUMP MOTOR GENERATOR. THE | | 'A' RECIRC PUMP HAS BEEN RETURNED TO AN OPERABLE STATUS. THE TECH SPEC | | ACTION STATEMENT AS BEEN EXITED. THE PLANT IS CURRENTLY AT 84% POWER. THE | | PLANT INTENDS TO HOLD AT THIS POWER WHILE THEY REVIEW THIS EVENT. THE 'D' | | RECIRC PUMP IS STILL INOPERABLE. THE CAUSE OF THE TRIP OF 'D' RECIRC PUMP | | IS STILL UNDER INVESTIGATION. THE LICENSEE WILL INFORM THE NRC RESIDENT | | INSPECTOR. HOO NOTIFIED THE RDO (KEIMIG). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 28375 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 02/13/95 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 02:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 02/12/95 | +------------------------------------------------+EVENT TIME: 01:36[EST]| |NRC NOTIFIED BY: KAFANTARIS |LAST UPDATE DATE: 02/13/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD KEIMIG 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 4 STARTUP | 2 STARTUP | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL MAIN STEAM SYSTEM ISOLATION TO STOP RCS TEMPERATURE DECREASE - | | | | ON 02/12/95, UNIT 2 WAS AT 4% POWER WITH 1 OF 4 ATMOSPHERIC RELIEF VALVES | | (22MS-10) CLOSED AND DEENERGIZED FOR MAINTENANCE ACTIVITIES. PRESSURE IN | | #22 STEAM GENERATOR INCREASED FROM A NORMAL OF 1005 PSIG TO 1020 PSIG. | | CONTROL ROOM OPERATORS REDUCED POWER TO 2% TO REDUCE PRESSURE SO AS NOT TO | | CHALLENGE A SECONDARY SIDE SAFETY VALVE. DURING THE POWER REDUCTION, THE | | Rx COOLANT SYSTEM TEMPERATURE DECREASED FROM A NORMAL OF 547 DEGREES F TO | | APPROXIMATELY 540.5 DEGREES F AS AUX FEEDWATER WAS BEING INJECTED INTO THE | | Rx COOLANT SYSTEM. AT 0136, CONTROL ROOM OPERATORS STOPPED THE AUX | | FEEDWATER INJECTION AND MANUALLY CLOSED THE MAIN STEAM LINE WARMUP VALVE | | (MS-18) AND THE MAIN STEAM LINE DRAIN VALVE (MS-7) (ESF ACTUATION) TO | | STOP DUMPING STEAM TO THE MAIN CONDENSER TO STOP THE TEMPERATURE DECREASE. | | UNIT 2 WAS STABILIZED AT 2% POWER AT NORMAL PRESSURE AND TEMPERATURE. | | | | LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT. | | | | AT 0030 ON 02/13/95, LICENSEE DETERMINED THIS EVENT TO BE REPORTABLE TO THE | | NRC AS A MANUAL ESF ACTUATION. | | | | LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+