U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/17/95 - 11/20/95 ** EVENT NUMBERS ** 29571 29611 29612 29613 29614 29615 29616 29617 29618 29619 29620 29621 29622 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29571 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 11/07/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 17:47 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/07/95 | +------------------------------------------------+EVENT TIME: 15:45[CST]| |NRC NOTIFIED BY: DENNIS MORRIS |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - >1% OF INSPECTED TUBES ON 4 OF 4 STEAM GENERATORS ARE DEFECTIVE - | | | | WHILE INSPECTING THE FULL LENGTH OF 100% OF THE TUBES OF ALL 4 STEAM | | GENERATORS ON UNIT 1, THE LICENSEE DETERMINED THAT MORE THAN 1% OF THE | | INSPECTED TUBES WERE FOUND TO BE DEFECTIVE IN THAT THEY CONTAINED | | IMPERFECTIONS WHICH EXCEEDED THE PLUGGING OR REPAIR LIMIT. | | | | THE ACCEPTANCE CRITERIA SPECIFIED IN UNIT 1 TECHNICAL SPECIFICATIONS | | 4.4.5.4.a.6 AND 4.4.5.4.a.11 REQUIRE A TUBE TO BE PLUGGED OR REPAIRED IF AN | | IMPERFECTION IS GREATER THAN OR EQUAL TO 40% THROUGH WALL OR EXCEEDS 1 VOLT | | BOBBIN COIL VOLTAGE. THE LICENSEE HAS SUBMITTED A 3.0-VOLT INTERIM | | PLUGGING CRITERIA LICENSE AMENDMENT REQUEST FOR NRC APPROVAL. THIS | | AMENDMENT REQUEST HAS NOT BEEN APPROVED BY THE NRC AT THIS TIME. | | | | IN ACCORDANCE WITH BYRON TECHNICAL SPECIFICATION 4.4.5.2, FOR EACH STEAM | | GENERATOR, THESE INSPECTION RESULTS CORRESPOND TO A C-3 CLASSIFICATION | | REQUIRING NOTIFICATION TO THE NRC. | | | | THE LICENSEE WILL COMPLETE THE INSPECTION OF ALL STEAM GENERATORS, PROVIDE | | AN UPDATE OF SPECIFIC PERCENTAGES TO THE NRC WHEN THE INSPECTION IS | | COMPLETE, AND PLUG OR REPAIR THE DEFECTIVE TUBES. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 17:14 NOVEMBER 17, 1995, UPDATE FROM WINTER RECEIVED BY TROCINE * * * | | | | THE LICENSEE'S INSPECTIONS HAVE BEEN COMPLETED, AND THE FINAL RESULTS ARE | | AVAILABLE. IN ADDITION, THE LICENSEE HAS RECEIVED APPROVAL OF THE 3.0-VOLT | | INTERIM PLUGGING CRITERIA FROM THE NRC. | | | | THE CURRENTLY APPROVED ACCEPTANCE CRITERIA SPECIFIED IN BYRON UNIT 1 | | TECHNICAL SPECIFICATIONS 4.4.5.4.a.6 AND 4.4.5.4.a.11 REQUIRES A TUBE TO BE | | PLUGGED OR REPAIRED IF AN IMPERFECTION IS GREATER THAN OR EQUAL TO 40% | | THROUGH WALL OR A TUBE SUPPORT PLATE IMPERFECTION EXCEEDS THE INTERIM | | PLUGGING CRITERIA BOBBIN VOLTAGE REPAIR LIMIT (i.e., 3 VOLTS ON THE HOT LEG | | AND 1 VOLT ON THE COLD LEG). CONFIRMED INDICATIONS OF CIRCUMFERENTIAL | | CRACKING AT THE TOP OF THE TUBE SHEET ARE CLASSIFIED AS DEFECTIVE AND ARE | | REPAIRED ACCORDINGLY. | | | | STEAM GENERATOR 1A HAD 280 DEFECTIVE TUBES OF 4,120 TOTAL TUBES (6.8%). | | STEAM GENERATOR 1B HAD 1,002 DEFECTIVE TUBES OF 4,064 TOTAL TUBES (24.7%). | | STEAM GENERATOR 1C HAD 742 DEFECTIVE TUBES OF 4,016 TOTAL TUBES (18.5%). | | STEAM GENERATOR 1D HAD 693 DEFECTIVE TUBES OF 4,360 TOTAL TUBES (15.9%). | | (REFER TO THE HOO LOG FOR MORE DETAILED STEAM GENERATOR CATEGORY C-3 B1P02 | | EDDY CURRENT INSPECTION RESULTS.) THE DEFECTIVE TUBES ARE CURRENTLY BEING | | REPAIRED OR PLUGGED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R3DO (BURGESS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29611 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 11/17/95 | |UNIT: [1] [ ] [ ] STATE: MD |NOTIFICATION TIME: 00:02 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/16/95 | +------------------------------------------------+EVENT TIME: 22:52[EST]| |NRC NOTIFIED BY: FRY |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHANSEN 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 STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP DUE TO FAILURE OF MAIN FEEDWATER PUMP | | | | CONTROL ROOM OPERATORS MANUALLY TRIPPED THE UNIT AFTER RECEIVING INDICATION | | OF THE LOSS OF THE #12 STEAM GENERATOR FEED PUMP AND DECREASING STEAM | | GENERATOR WATER LEVELS. THE TRIP WAS UNCOMPLICATED, AND ALL CONTROL RODS | | INSERTED PROPERLY. THE LICENSEE REPORTED THAT THE AUXILIARY FEEDWATER | | SYSTEM AUTOMATICALLY STARTED DUE TO LOW STEAM GENERATOR LEVELS. ALL | | SYSTEMS FUNCTIONED AS DESIGNED. | | | | THE LICENSEE STATED THAT THE FEEDWATER PUMP TRIP APPEARS TO HAVE BEEN | | CAUSED BY A PROBLEM WITH THE CONTROL OIL SYSTEM. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29612 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 11/17/95 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 10:12 [ET]| |RX TYPE: [3] CE |EVENT DATE: 11/17/95 | +------------------------------------------------+EVENT TIME: 08:30[CST]| |NRC NOTIFIED BY: COLLINS |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |SANBORN RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF CRIMINAL ACT INVOLVING INDIVIDUAL GRANTED ACCESS TO THE SITE. | | IMMEDIATE COMPENSATORY ACTIONS TAKEN UPON DISCOVERY. SEE HOO LOG FOR | | DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29613 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/17/95 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 10:42 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/17/95 | +------------------------------------------------+EVENT TIME: 10:00[EST]| |NRC NOTIFIED BY: QUINN |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHANSEN 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DETECTED INDICATION IN WELD ON REACTOR WATER CLEANUP RETURN LINE. | | | | DURING NORMAL INSERVICE INSPECTIONS, THE LICENSEE DETECTED AN INDICATION IN | | A WELD ON THE REACTOR WATER CLEANUP SYSTEM RETURN LINE TO THE REACTOR | | VESSEL (ON THE OUTBOARD WELD OF THE CONTAINMENT PENETRATION). THE FLAW | | APPEARS TO HAVE BEEN CAUSED BY INTERGRANULAR STRESS CORROSION CRACKING | | (IGSCC). THE LICENSEE'S EVALUATION HAS DETERMINED THAT THIS WELD DOES NOT | | MEET THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE REQUIREMENTS | | PLACING THE UNIT OUTSIDE OF ITS DESIGN BASIS. THE INDICATION DOES NOT | | EXTEND THROUGH THE WALL OF THE PIPE. | | | | THE LICENSEE PLANS TO REPAIR THE WELD PRIOR TO STARTUP. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29614 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRAIDWOOD REGION: 3 |NOTIFICATION DATE: 11/17/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 14:39 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/17/95 | +------------------------------------------------+EVENT TIME: 11:49[CST]| |NRC NOTIFIED BY: DENNIS HIGINBOTHAM |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 | M/R N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL OPENING OF THE REACTOR TRIP BREAKERS DUE TO A BLOWN STATIONARY | | GRIPPER FUSE DURING DIGITAL ROD POSITION INDICATION OPERABILITY TESTING | | WITH THE UNIT IN MODE 5 | | | | DURING THE PERFORMANCE OF DIGITAL ROD POSITION INDICATION OPERABILITY | | TESTING, ROD CONTROL BANK 'B' WAS BEING WITHDRAWN. ALL RODS IN THIS BANK | | INDICATED 12 STEPS FROM THE FULLY INSERTED POSITION WITH THE EXCEPTION OF | | ROD K-14 WHICH INDICATED 0 STEPS. AS A CONSERVATIVE MEASURE, THE LICENSEE | | MANUALLY OPENED THE REACTOR TRIP BREAKERS TO ALLOW RE-INSERTION OF CONTROL | | BANK 'B'. ALL RODS FULLY INSERTED. (THERE WERE NO ADMINISTRATIVE OR | | TECHNICAL SPECIFICATION REQUIREMENTS THAT DIRECTED THE OPENING OF THE | | REACTOR TRIP BREAKERS.) | | | | THE LICENSEE DETERMINED THAT THE STATIONARY GRIPPER FUSE FOR ROD K-14 WAS | | BLOWN. THE LICENSEE IS STILL INVESTIGATING THIS PROBLEM AND ANTICIPATES | | THAT THE FUSE WILL BE REPLACED AND THAT FURTHER TESTING WILL PROGRESS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29615 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DAVIS BESSE REGION: 3 |NOTIFICATION DATE: 11/17/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 14:44 [ET]| |RX TYPE: [1] B&W-R-LP |EVENT DATE: 11/17/95 | +------------------------------------------------+EVENT TIME: 11:22[EST]| |NRC NOTIFIED BY: DAVID ESHELMAN |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 +------------------------------------------------------------------------------+ | FUEL MOVEMENT WITH BOTH TRAINS OF THE SPENT FUEL POOL EMERGENCY VENTILATION | | SYSTEM INOPERABLE DUE TO THE BREACH OF THE NEGATIVE PRESSURE BOUNDARY | | | | ON NOVEMBER 17, 1995, A SYSTEM ENGINEER DISCOVERED THAT THE SPENT FUEL POOL | | AREA NEGATIVE PRESSURE BOUNDARY HAD BEEN BREACHED SINCE OCTOBER 6, 1995, | | DUE TO A MAINTENANCE ACTIVITY. APPARENTLY, A FAN ASSEMBLY WAS REMOVED FROM | | SOME NON-SAFETY-RELATED RADWASTE VENTILATION SYSTEM DUCT WORK ALLOWING A | | 1,133 SQUARE INCH FLOW PATH (A 38-INCH DIAMETER HOLE) FROM THE NEGATIVE | | PRESSURE AREA. THIS CONDITION TECHNICALLY RENDERED BOTH TRAINS OF THE | | SPENT FUEL POOL EMERGENCY VENTILATION SYSTEM INOPERABLE, PLACING THE UNIT | | IN TECHNICAL SPECIFICATION LIMITING CONDITION FOR OPERATION 3.9.12, | | "STORAGE POOL VENTILATION." WITH ONE TRAIN OF THE EMERGENCY VENTILATION | | SYSTEM SERVICE ON THE STORAGE POOL AREA INOPERABLE, ACTION STATEMENT 'A' OF | | THIS TECHNICAL SPECIFICATION REQUIRES THAT THE REMAINING TRAIN BE RUNNING | | IF FUEL IS BEING MOVED IN THE SPENT FUEL POOL OR IF HEAVY LOADS ARE BEING | | MOVED OVER THE SPENT FUEL POOL. ACTION STATEMENT 'B' REQUIRES THAT NO FUEL | | MOVEMENT OR MOVEMENT OF HEAVY LOADS TAKE PLACE IN OR OVER THE SPENT FUEL | | POOL IF BOTH TRAINS OF THE EMERGENCY VENTILATION SYSTEM SERVICE IN THE | | STORAGE POOL ARE INOPERABLE. | | | | THE LICENSEE ALSO DETERMINED THAT FUEL MOVEMENT IN THE SPENT FUEL POOL | | OCCURRED AT LEAST ONCE (POSSIBLE AS MANY AS THREE OR FOUR TIMES) WHILE IN | | THIS CONDITION WHICH VIOLATED ACTION STATEMENT 'B' OF TECHNICAL | | SPECIFICATION 3.9.12. THIS CONSTITUTED A CONDITION THAT ALONE COULD HAVE | | PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF THE SPENT FUEL POOL | | AREA EMERGENCY VENTILATION SYSTEM TO MITIGATE THE CONSEQUENCES OF A FUEL | | HANDLING ACCIDENT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29616 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 11/17/95 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 21:41 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 11/17/95 | +------------------------------------------------+EVENT TIME: 19:50[CST]| |NRC NOTIFIED BY: KEITH POLSON |LAST UPDATE DATE: 11/17/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 Y 76 POWER OPERATION | 76 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STRESSES IN CERTAIN MEMBERS, CONNECTIONS, AND ATTACHMENTS OF THE SCRAM | | DISCHARGE PIPING DID NOT MEET UFSAR ALLOWABLE LIMITS. | | | | WHILE PERFORMING WALKDOWNS OF THE UNIT 3 SCRAM DISCHARGE VOLUME PIPING, THE | | LICENSEE DISCOVERED THAT THE STRESSES IN CERTAIN MEMBERS, CONNECTIONS, AND | | ATTACHMENTS DID NOT MEET UFSAR ALLOWABLES. AN OPERABILITY DETERMINATION | | (ENC-QE-40.1) WAS PERFORMED, AND THE DESIGN ENGINEERING GROUP HAS | | DETERMINED THAT SUFFICIENT MARGIN EXISTS IN THE STEEL TO MEET OPERABILITY | | REQUIREMENTS. THEREFORE, THE UNIT IS NOT IN ANY TECHNICAL SPECIFICATION | | LIMITING CONDITIONS FOR OPERATION. | | | | THE LICENSEE IS CONTINUING ITS INVESTIGATIONS AND CORRECTIVE ACTIONS | | DETERMINATIONS. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29617 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/18/95 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 08:36 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/18/95 | +------------------------------------------------+EVENT TIME: 01:20[CST]| |NRC NOTIFIED BY: HARRINGTON |LAST UPDATE DATE: 11/18/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FOR-CAUSE TEST OF A CONTRACT EMPLOYEE RESULTS POSITIVE FOR ALCOHOL. | | | | A CONTRACT DIVING TEAM SUPERVISOR TESTED POSITIVE FOR ALCOHOL WITH A LEVEL | | OF 0.080. THE LICENSEE REMOVED HIS SITE ACCESS AND SENT HIM HOME. THE | | LICENSEE WILL BE REVIEWING THE INDIVIDUAL'S WORK TO DETERMINE IF THERE ARE | | ANY DISCREPANCIES. THE LICENSEE WILL ALSO SEARCH THE INDIVIDUAL'S VAN TO | | DETERMINE IF ANY ALCOHOL IS PRESENT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29618 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 11/18/95 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 09:33 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 11/18/95 | +------------------------------------------------+EVENT TIME: 08:08[CST]| |NRC NOTIFIED BY: HUMPHRIES |LAST UPDATE DATE: 11/18/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DECLARED THE SPDS UNAVAILABLE BECAUSE OF A COMPUTER OUTAGE. | | | | THE LICENSEE HAD A PLANNED OUTAGE OF THE PLANT COMPUTER SYSTEM WHICH MADE | | THE SPDS UNAVAILABLE FOR UP TO 8 HOURS. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29619 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 11/18/95 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 22:58 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/18/95 | +------------------------------------------------+EVENT TIME: 20:49[EST]| |NRC NOTIFIED BY: NORM THOMAS |LAST UPDATE DATE: 11/18/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER RDO | |NINF INFORMATION ONLY | | | | | | |ROGER HANNAH/REGION PAO | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 89 POWER OPERATION | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COURTESY NOTIFICATION DUE TO PUBLIC INTEREST IN A SECONDARY PLANT TRANSIENT | | | | AT 20:49, SEVERAL MAIN TURBINE INTERCEPT VALVES WENT CLOSED CAUSING THE | | SAFETY VALVES ON THE MOISTURE SEPARATOR REHEATERS TO LIFT. AS A RESULT OF | | THIS SECONDARY SYSTEM TRANSIENT, THE OPERATING CREW REDUCED REACTOR POWER | | TO 2%. THERE WERE NO ENGINEERED SAFETY FEATURES ACTUATIONS AS A RESULT OF | | THIS TRANSIENT, AND NO STEAM GENERATOR POWER OPERATED RELIEF VALVES LIFTED. | | ALL OF THE MOISTURE SEPARATOR REHEATER SAFETY VALVES RESEATED WHEN THE | | TURBINE WAS MANUALLY TRIPPED AT 21:06. THERE HAS BEEN NO HISTORY OF STEAM | | GENERATOR TUBE LEAKAGE. THE LICENSEE IS STILL INVESTIGATING THE CAUSE OF | | THE INTERCEPT VALVE CLOSURES. | | | | THE UNIT IS CURRENTLY STABLE AT 2% REACTOR POWER. AUXILIARY FEEDWATER IS | | BEING SUPPLIED TO THE STEAM GENERATORS, AND SECONDARY STEAM IS BEING | | BYPASSED TO THE CONDENSER. THE LICENSEE IS UTILIZING PRESSURIZER HEATERS | | AND SPRAYS, NORMAL CHARGING AND MAKEUP, AND THE REACTOR COOLANT PUMPS FOR | | PRIMARY PRESSURE, INVENTORY, AND TRANSPORT CONTROL. THE LICENSEE IS | | UTILIZING NORMAL OPERATING INSTRUCTIONS AT THIS TIME. | | | | THE NOISE FROM THE LIFTING OF THE MOISTURE SEPARATOR REHEATER SAFETY VALVES | | ATTRACTED ATTENTION FROM SURROUNDING RESIDENTS AND FROM LOCAL RADIO AND | | TELEVISION STATIONS. THE LICENSEE DOES NOT PLAN TO ISSUE AN OFFICIAL PRESS | | RELEASE AT THIS TIME. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, WHO RESPONDED TO THE | | SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29620 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 11/19/95 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 18:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/19/95 | +------------------------------------------------+EVENT TIME: 09:30[CST]| |NRC NOTIFIED BY: LANE O'BEREMBT |LAST UPDATE DATE: 11/19/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNAVAILABILITY OF THE SAFETY PARAMETER DISPLAY SYSTEM DUE TO A FIRE IN THE | | BYPASS TRANSFORMER FOR THE UNINTERRUPTIBLE POWER SUPPLY FOR THE PROCESS | | COMPUTER | | | | AT 09:30 CST, THE STATION EXPERIENCED A FIRE ON THE BYPASS TRANSFORMER FOR | | THE UNINTERRUPTIBLE POWER SUPPLY FOR THE UNIT 1 PROCESS COMPUTER. THE | | BREAKER THAT FEEDS THE BYPASS TRANSFORMER TRIPPED OPEN AS DESIGNED, AND THE | | FIRE WAS EXTINGUISHED WITHIN APPROXIMATELY 10 MINUTES. THE LICENSEE | | DEENERGIZED THE UNINTERRUPTIBLE POWER SUPPLY INVERTER, CAUSING A LOSS OF | | POWER TO THE PROCESS COMPUTER, AND CONSEQUENTLY, THE LOSS OF THE SAFETY | | PARAMETER DISPLAY SYSTEM FOR UNIT 1 FOR GREATER THAN 8 HOURS. ALL OTHER | | CONTROL ROOM INDICATIONS ARE OPERABLE, AND THERE ARE NO TECHNICAL | | SPECIFICATION ACTION STATEMENTS ASSOCIATED WITH THE LOSS OF THE SAFETY | | PARAMETER DISPLAY SYSTEM. TROUBLESHOOTING TO DETERMINE THE CAUSE OF THE | | TRANSFORMER FIRE IS IN PROGRESS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE ILLINOIS | | DEPARTMENT OF NUCLEAR SAFETY. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29621 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COMANCHE PEAK REGION: 4 |NOTIFICATION DATE: 11/19/95 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 21:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/19/95 | +------------------------------------------------+EVENT TIME: 17:35[CST]| |NRC NOTIFIED BY: MIKE SMITH |LAST UPDATE DATE: 11/19/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN 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 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TURBINE TRIP/REACTOR TRIP ON HIGH-HIGH STEAM GENERATOR LEVEL DUE TO A | | FAILED FEEDWATER PUMP RECIRCULATION VALVE | | | | AT 17:24 CST, THE CONTROL ROOM RECEIVED A BALANCE OF PLANT ANALOG POWER | | SUPPLY TRAIN 'C' FAILURE ALARM. THE AFFECTED COMPONENT WAS THE | | RECIRCULATION VALVE FOR THE 'A' STEAM GENERATOR FEEDWATER PUMP. THIS | | 18-INCH VALVE FAILED OPEN AND DIVERTED A PORTION OF THE FEEDWATER BACK TO | | THE CONDENSER HOTWELL. AS A RESULT, THE LICENSEE MANUALLY REDUCED TURBINE | | LOAD TO TRY TO MAINTAIN FEEDWATER PUMP SUCTION PRESSURE. DURING THE LOAD | | REDUCTION, THE LICENSEE HAD EFFORTS IN PLACE TO MANUALLY ISOLATE THE FAILED | | VALVE, AND THE 'B' STEAM GENERATOR FEEDWATER PUMP TRIPPED ON LOW SUCTION | | PRESSURE. THIS INITIATED AN AUTOMATIC START OF BOTH MOTOR-DRIVEN AUXILIARY | | FEEDWATER PUMPS. WHEN THE FAILED RECIRCULATION VALVE WAS MANUALLY | | ISOLATED, STEAM GENERATOR LEVELS PROMPTLY INCREASED, AND HIGH-HIGH LEVEL | | WAS REACHED IN STEAM GENERATOR #2. THIS IN TURN INITIATED AN AUTOMATIC | | TURBINE TRIP AND SUBSEQUENT REACTOR TRIP FROM 72% REACTOR POWER AT 17:35 | | CST. ALL RODS FULLY INSERTED, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. PRIMARY PRESSURE, LEVEL, AND | | TRANSPORT ARE BEING CONTROLLED VIA THE USE OF PRESSURIZER HEATERS AND | | SPRAYS, NORMAL CHARGING AND LETDOWN, AND THE REACTOR COOLANT PUMPS. | | AUXILIARY FEEDWATER IS BEING USED TO SUPPLY WATER TO THE STEAM GENERATORS, | | AND SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER. | | | | THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THE POWER SUPPLY | | FAILURE WHICH RESULTED IN THE VALVE FAILURE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29622 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 11/20/95 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 03:49 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 11/20/95 | +------------------------------------------------+EVENT TIME: 04:00[EST]| |NRC NOTIFIED BY: HAISLET |LAST UPDATE DATE: 11/20/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |NINF INFORMATION ONLY | | |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 +------------------------------------------------------------------------------+ | THE LICENSEE IS TAKING THE RCIC SYSTEM OUT OF SERVICE FOR PLANNED | | MAINTENANCE. | | | | THE PLANT ENTERED A 14 DAY LCO ACTION STATEMENT DUE TO RCIC BEING OUT OF | | SERVICE FOR MAINTENANCE. THE LCO REQUIRES THAT HPCI BE AVAILABLE WHILE RCIC | | IS OUT. HPCI HAS BEEN VERIFIED OPERABLE. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+