U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/10/94 - 06/13/94 ** EVENT NUMBERS ** 27280 27295 27353 27381 27382 27383 27384 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27280 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 05/20/94 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 13:30 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 05/20/94 | +------------------------------------------------+EVENT TIME: 10:15[CDT]| |NRC NOTIFIED BY: REIS |LAST UPDATE DATE: 06/10/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GROBE 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 +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED THAT ONE OF THE SNUBBERS ("RH14-1051S") INSTALLED | | ON THE "1C" RHR LINE DOWN STREAM OF THE FULL FLOW TEST VALVE("1E12-F021") | | HAD A 30 DEGREE ANGULAR DEVIATION FROM ITS ANALYZED CONDITION. | | | | THE FOLLOWING TEXT IS FROM A FAX BY THE LICENSEE: | | | | "SNUBBER RH14-1051S IN SUBSYSTEM 1RH08 WAS FOUND TO BE INSTALLED WITH AN | | ANGULAR DEVIATION OF 30 DEGREES FROM ITS AS-ANALYZED CONDITION. A | | RE-ANALYSIS OF SUBSYSTEM 1RH08 WAS THEN PERFORMED WITH SNUBBER RH14-1051S | | IN ITS AS INSTALLED CONDITION. ALL PIPE STRESSES AND RESTRAINT LOADS WERE | | WITHIN DESIGN BASIS ALLOWABLES EXCEPT FOR SNUBBER RH141016S. BOTH SNUBBERS | | ARE DOWNSTREAM OF THE 1CRHR FULL FLOW TEST VALVE 1E12-F021. | | | | THE REANALYZED LOADS FOR RH14-1016S EXCEEDS THE UFSAR LIMITS FOR THE | | SUPPORT CONCRETE EXPANSION ANCHORS(CEA'S). THE CEA'S ARE REQUIRED TO HAVE A | | FACTOR OF SAFETY AGAINST FAILURE OF 4.0. WITH THE REVISED LOADS, THE FACTOR | | OF SAFETY IS 3.0. THE ANCHORS HAVE NOT BEEN OVER STRESSED BY THE LOADS THEY | | HAVE SEEN TO DATE, SINCE THE DESIGN LOADS ARE PRIMARILY DUE TO EARTHQUAKES | | AND NO EARTHQUAKES HAVE OCCURRED. IF AN EARTHQUAKE HAD OCCURRED, THE | | ANCHORS MAY HAVE BEEN STRESSED BEYOND THE UFSAR LIMITS, BUT BASED ON THE | | REMAINING FACTOR OF SAFETY, THEY WOULD LIKELY NOT HAVE FAILED. RH14-1051S | | IS TO BE INSTALLED IN ITS AS DESIGNED CONDITION." | | | | THE PLANT CURRENTLY HAS ECCS OPERABLE ON DIV 1 AND DIV 3. | | | | THE RI WILL BE NOTIFIED. | | | | **** RETRACTED BY REIS @ 1435 EDT ON 06/10/94 TAKEN BY ANDREWS **** | | LICENSEE IS RETRACTING THIS EVENT BECAUSE THEY HAVE DETERMINED THAT THE | | NOTIFICATION CRITERIA WAS NOT MET. THE ANALYZED LOAD FOR THE "AS FOUND" | | SUPPORT M09-R14-101016S EXCEEDS THE UFSAR LIMITS FOR THE SUPPORT CONCRETE | | EXPANSION ANCHORS (CEA), HOWEVER, ANALYSIS SHOWS THAT FAILURE OF THE PIPING | | AND SUPPORT WOULD NOT HAVE OCCURED DUE TO SUFFICIENT MARGIN. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | R3DO (JORGENSEN) NOTIFIED BY HOO. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/25/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 13:14[CDT]| |NRC NOTIFIED BY: DAVE KUSER |LAST UPDATE DATE: 06/11/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROBERT DENNING EO | |NLCO TECH SPEC LCO A/S |BOB CALDWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOTH EMERGENCY DIESEL GENERATORS BEING | | DECLARED INOPERABLE. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "ON MAY 25, 1994 AT 1:14 PM A NOTIFICATION OF UNUSUAL EVENT WAS DECLARED | | WHEN BOTH DIESEL GENERATORS WERE DECLARED INOPERABLE DUE TO THE | | SURVEILLANCE TEST CONDUCTED EACH REFUELING OUTAGE NOT VERIFYING THE LOAD | | SHEDDING OF ALL LOADS ON THE CRITICAL 480 VOLT BUS. PROPER LOAD SHEDDING | | OF ALL 4160 VOLT LOADS IS VERIFIED DURING THE SEQUENTIAL LOADING TEST. THE | | PRINCIPAL 480 VOLT LOADS NOT VERIFIED TO BE SHED INCLUDE STATION AIR | | COMPRESSORS AND THE CRD PUMPS. THESE COMPONENTS ARE TRANSFERRED TO ANOTHER | | BUS DURING THE SURVEILLANCE TEST. INDIVIDUALLY, THE REMAINING LOADS ON THE | | CRITICAL 480 VOLT BUS ARE SMALL. | | | | IN ACCORDANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS IN SECTION 3.5.F.2, | | A LOAD REDUCTION TO 25 PERCENT POWER WAS INITIATED. AN ENGINEERING | | EVALUATION OF THE CONDITION IS ONGOING. A FOLLOW-UP NOTIFICATION WILL BE | | MADE WHEN SUCH INFORMATION IS AVAILABLE." END OF TEXT. | | | | THE LICENSEE IS REDUCING POWER AT 100 MW(e) PER HOUR. THE LICENSEE | | CONSIDERS THE EDGS AVAILABLE. ALL ECCS AND RCIC ARE OPERABLE. THE WEATHER | | IN THE AREA IS CALM WITH NO FORECAST OF RAIN. THE PROBLEM WAS DISCOVERED | | DURING REVIEW OF UNDERVOLTAGE TESTING. THE LAST REFUELING OUTAGE ENDED IN | | JULY OF 1993. THE LICENSEE IS INVESTIGATING CORRECTIVE ACTIONS AND IS | | PURSUING ENFORCEMENT DISCRETION WITH THE NRC TO STOP THE POWER DESCENSION. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND HAS INFORMED LOCAL AND | | STATE OFFICIALS IN ACCORDANCE WITH THEIR EMERGENCY PLAN. | | | | * * * UPDATE 5/25/94 @ 22:40 FROM CAUL TAKEN BY SEBROSKY * * * | | THE REACTOR IS CURRENTLY AT 24% POWER AND THE LICENSEE PLANS TO SCRAM THE | | THE PLANT AT 22:00 CT PER THEIR NORMAL SHUTDOWN PROCEDURES. THE SHUTDOWN | | IS BEING DONE DUE TO BOTH EDGS BEING DECLARED INOPERABLE. THE LICENSEE | | WILL EXIT THE UNUSUAL EVENT WHEN THE PLANT REACHES COLD SHUTDOWN | | CONDITIONS. COLD SHUTDOWN IS EXPECTED TO BE REACHED SOMETIME TOMORROW | | MORNING. THE LICENSEE HAS BEEN IN CONTACT WITH REGION 4 OFFICIALS | | CONCERNING THE SHUTDOWN AND HAS INFORMED THE RESIDENT INSPECTOR. | | HOO NOTIFIED R4DO(POWERS) AND EO(VARGA). | | | | * * * UPDATE 5/27/94 @ 0106 FROM HITZEL TAKEN BY WEAVER * * * | | THE PLANT REACHED COLD SHUTDOWN AT 2357 CDT ON 5/26/94. THIS SATISFIES THE | | TECHNICAL SPECIFICATION ACTION STATEMENT FOR HAVING BOTH EMERGENCY DIESELS | | INOPERABLE. CONTRARY TO THE LAST UPDATE, THE UNUSUAL EVENT WILL NOT BE | | TERMINATED UNTIL AT LEAST ONE EDG IS MADE OPERABLE AS REQUIRED BY THEIR | | EMERGENCY PROCEDURES. NO TIME ESTIMATE WAS AVAILABLE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL GOVERNMENTS. | | HOO NOTIFIED R4 RDO (POWERS) AND EO (CHAFFEE). | | | | * * * UPDATE 1400EDT 5/27/94 FROM KUSER TO S.SANDIN * * * | | THE CONTINUING INVESTIGATION HAS REVEALED THAT LOAD SHEDDING OF THE SERVICE | | WATER PUMPS, 4160 VOLT LOADS, IS NOT VERIFIED DURING THE SEQUENTIAL LOADING | | TEST. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED | | R4DO(POWERS). | | | | * * * UPDATE AT 1734 EDT ON 6/11/94 FROM HITZEL TAKEN BY KARSCH * * * | | THE FOLLOWING NOTIFICATION WAS MADE PURSUANT TO 10CFR50.72(b)(2)iiiD: | | "AS AN ELEMENT OF THE INVESTIGATION INTO THIS CONDITION, AN EVALUATION OF | | CONTACT TEST REQUIREMENTS NECESSARY TO SATISFY LOGIC SYSTEM FUNCTIONAL | | TESTING REQUIREMENTS SPECIFIED IN TECHNICAL SPECIFICATIONS FOR SAFETY | | RELATED SYSTEMS WAS PERFORMED. THIS EVALUATION REVEALED A NUMBER OF | | CONTACTS NOT VERIFIED BY SURVEILLANCE PROCEDURES. EACH CONTACT NOT TESTED | | WAS EVALUATED TO DETERMINE IF FAILURE TO ASSURE ITS OPERABILITY JEOPARDIZED | | COMPLIANCE WITH THE LOGIC SYSTEM FUNCTIONAL TEST DEFINITION SPECIFIED IN | | SECTION 1.0 OF THE TECH SPECS. | | | | "AT 1430 TODAY (JUNE 11, 1994), THE SYSTEMS IDENTIFIED BELOW WERE DECLARED | | INOPERABLE DUE TO THE SURVEILLANCE TEST DEFICIENCY. | | SERVICE WATER REACTOR EQUIPMENT COOLING | | 4160 VAC BUS 1F 4160 VAC BUS 1G | | DIESEL GENERATOR 1 DIESEL GENERATOR 2 | | PROCEDURE CHANGES AND SPECIAL PROCEDURES ARE BEING DEVELOPED AND CONDUCTED | | TO ASSURE OPERABILITY OF THE LOGIC SYSTEMS. WHILE TECHNICALLY INOPERABLE, | | AND NOT REQUIRED TO BE OPERABLE UNDER THE PRESENT PLANT CONDITIONS, THE | | SYSTEMS ARE FUNCTIONAL AND AVAILABLE. THE ASSOCIATED SYSTEMS WILL NOT BE | | DECLARED OPERABLE UNTIL SATISFACTORY COMPLETION OF THE TESTS AND | | VERIFICATION OF THE RESULTS." | | | | THE LICENSEE HOPES TO COMPLETE TESTING ON ONE DIVISION'S EDG BY LATE | | MONDAY. AT THAT TIME THEY SHOULD BE ABLE TO EXIT THEIR UNUSUAL EVENT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R4DO(SANBORN) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27353 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 06/05/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 20:54 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/05/94 | +------------------------------------------------+EVENT TIME: 17:39[CDT]| |NRC NOTIFIED BY: PAUL INFINGER |LAST UPDATE DATE: 06/10/94 | |HQ OPS OFFICER: THOMAS ANDREWS +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AT 1739 CDT, ON 06/05/94, THE LICENSEE DISCOVERED THAT THEY COULD NOT | | ACCESS THE PRIME COMPUTER POINT HISTORY. LOSS OF ACCESS TO THE POINT | | HISTORY IS CONSIDERED TO BE A LOSS OF ASSESSMENT CAPABILITY. | | | | WORK IS IN PROGRESS TO RESTORE THE PRIME COMPUTER TO OPERABLE STATUS. | | HOWEVER, THE COMPUTER WAS NOT RESTORED WITHIN THE 2 HOURS GIVEN IN | | COMMITMENT DOCUMENTS. THE LICENSEE SUSPECTS THE PROBLEM IS RELATED TO THE | | HARD DISK. THEY DID NOT HAVE AN ESTIMATED TIME REQUIRED TO COMPLETE THE | | REPAIRS. THIS PROBLEM DOES NOT AFFECT THE ANNUNCIATOR SYSTEM USED BY THE | | OPERATORS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED. | | | | * * * UPDATE ON 6/10/94 AT 1417 EDT FROM HARKNESS TAKEN BY KARSCH * * * | | COMPUTER RESTORED TO OPERABILITY. R3DO (JORGENSEN) THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27381 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/10/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 11:10 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/10/94 | +------------------------------------------------+EVENT TIME: 10:40[EDT]| |NRC NOTIFIED BY: STRONG |LAST UPDATE DATE: 06/10/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DETERMINED THAT AN UNANALYZED CONDITION EXIST ASSOCIATED | | WITH THE PRIMARY PRESSURE BOUNDARY. | | | | THIS WAS DISCOVERED WHEN THEY REALIZED THAT THEY HAD SOME NON QA BALL SEALS | | (WHICH WERE INSTALLED IN 1990, QA PAPER WORK CANNOT BE FOUND) ON THE | | CONTROL ELEMENT DRIVE ASSEMBLY. PRIOR TO A RECENT MODIFICATION, WHEN THEY | | INSTALLED A VERSAVENT ASSEMBLY (DURING REFUEL OUTAGE IN 1992), THEY HAD A | | SEATING ARRANGEMENT WITH THE BALL SEALS AND A THREADED VENT PLUG TORQUED ON | | TO THE BALL PROVIDING A SEALING PATH WITH A CAP AT THE TOP AND BOTH | | TOGETHER PROVIDED QA CATEGORY 1 SEALS FOR BOUNDARIES. WHEN THEY INSTALLED | | THE VERSAVENT ASSEMBLY, HOWEVER, THEY REMOVED THE CAP. SINCE THE VERSAVENT | | ASSEMBLY DOES NOT PROVIDE CODE BOUNDARY ISOLATION DUE TO ITS DESIGN | | CONFIGURATION (IT HAS AN "O" RING WHICH PREVENTS IT FROM BEING A CODE | | ISOLATION) THEY MAY HAVE CREATED A CONDITION WITH THE COMBINATION OF BOTH | | THE NON QA BALL SEALS AND A NON QA VERSAVENT ASSEMBLY, THAT COULD | | POTENTIALLY RESULT IN NOT HAVING A QA CATEGORY 1 PRESSURE BOUNDARY FOR THE | | RCS. THEY ARE FURTHER INVESTIGATING THIS CONDITION AND WILL CORRECT PRIOR | | TO RESTART. THE RI AND STATE AND LOCAL AGENCIES WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27382 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 06/10/94 | |UNIT: [1] [2] [ ] STATE: PA |NOTIFICATION TIME: 13:14 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 06/10/94 | +------------------------------------------------+EVENT TIME: 12:20[EDT]| |NRC NOTIFIED BY: DON ROLAND |LAST UPDATE DATE: 06/10/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | |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 15 POWER OPERATION | 15 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | EMERGENCY SIRENS INOPERABLE FROM 0930 TO 1200 EDT DUE TO WORK ON THE | | TELEPHONE LINES. THE TELEPHONE LINES WERE REMOVED FROM SERVICE DUE TO | | STATIC ON THE LINES. THE LICENSEE IS INVESTIGATING WHY THE TELEPHONE LINES | | WERE REMOVED FROM SERVICE WITHOUT ENSURING SIRENS OR AN ALTERNATE MEANS OF | | NOTIFICATION WERE AVAILABLE. | | | | EMERGENCY RESPONSE PERSONNEL NOTIFIED THE PENNSYLVANIA EMERGENCY MANAGEMENT | | AGENCY, THE LUZERNE COUNTY AND COLUMBIA COUNTY EMERGENCY MANAGEMENT | | AGENCIES AND THE NRC RESIDENT INSPECTOR. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27383 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 06/10/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 06/10/94 | +------------------------------------------------+EVENT TIME: 14:34[EDT]| |NRC NOTIFIED BY: MARIOS KAFANTARIS |LAST UPDATE DATE: 06/10/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP CAUSED BY TURBINE-GENERATOR PROTECTION. | | | | A GENERATOR TRIP OCCURRED DUE TO AN OVER EXCITATION CONDITION. TWO FOSSIL | | PLANTS HAD TRIPPED OFF THE GRID JUST PRIOR TO THE OVER EXCITATION, BUT THE | | EXACT CAUSE OF THE TRIP IS UNDER INVESTIGATION. ALL CONTROL RODS INSERTED | | FULLY FOLLOWING THE REACTOR TRIP. A MANUAL MAIN STEAM ISOLATION VALVE | | CLOSURE WAS INITIATED IN ACCORDANCE WITH EMERGENCY OPERATING PROCEDURES TO | | CONTROL REACTOR COOLANT SYSTEM COOLDOWN. THE LOWEST T AVE REACHED WAS 538 | | DEGREES F. AUX FEEDWATER (BOTH TURBINE AND MOTOR DRIVEN PUMPS) WAS | | MANUALLY INITIATED IN ANTICIPATION OF LOW STEAM GENERATOR LEVEL. A | | "FEEDWATER INTERLOCK" SIGNAL CLOSES THE MAIN FEED REG VALVE IF T AVE DROPS | | BELOW 554 DEGREES F FOLLOWING A REACTOR TRIP. THE MOTOR DRIVEN AUX FEED | | PUMPS ARE STILL RUNNING. DECAY HEAT REMOVAL IS VIA AUX FEED AND | | ATMOSPHERIC RELIEF VALVES. THE GRID IS NOW STABLE. SALEM UNIT 2 AND HOPE | | CREEK GENERATING PLANT ARE OPERATING NORMALLY. THE LICENSEE INFORMED LOWER | | ALLOWAYS CREEK TOWNSHIP AND THE NRC RESIDENT INSPECTOR. THE LICENSEE WILL | | ISSUE A PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27384 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 06/11/94 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 09:16 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 06/11/94 | +------------------------------------------------+EVENT TIME: 07:41[EDT]| |NRC NOTIFIED BY: VALLECORSA |LAST UPDATE DATE: 06/11/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MFW SYSTEM ISOLATED WHEN SG MAIN STEAM LINE ISOLATION VALVE WAS OPENED - | | | | AT 0741, WITH THE 'A' STEAM GENERATOR WATER LEVEL AT ITS NORMAL RANGE OF | | 44 TO 46%, CONTROL ROOM OPERATORS ATTEMPTED TO PLACE THE MAIN STEAM LINE | | HEADER IN SERVICE BY OPENING THE 'A' STEAM GENERATOR MAIN STEAM LINE | | ISOLATION VALVE, #2MSS-AOV-101A. | | | | THE 'A' STEAM GENERATOR WATER LEVEL SPIKED (SWELLED) OFF SCALE HIGH CAUSING | | 2 OF THE 3 WATER LEVEL DETECTORS TO INITIATE A MAIN FEEDWATER ISOLATION DUE | | TO A HI HI STEAM GENERATOR LEVEL SIGNAL (75%). THE DIFFERENTIAL PRESSURE | | BETWEEN THE STEAM GENERATOR AND THE MAIN STEAM LINE HEADER WAS 30 PSID. | | | | THREE CONTAINMENT MAIN FEEDWATER ISOLATION VALVES AND 3 MAIN FEEDWATER | | BYPASS FLOW CONTROL VALVES SHUT, AS REQUIRED, DUE TO THE MAIN FEEDWATER | | ISOLATION SIGNAL. | | | | AT 0743, CONTROL ROOM OPERATORS RESET THE ISOLATION SIGNAL AND RESTORED | | ALL VALVES TO THEIR NORMAL POSITIONS. | | | | LICENSEE IS DETERMINING CORRECTIVE ACTIONS. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+