U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/19/96 - 04/22/96 ** EVENT NUMBERS ** 30152 30163 30229 30285 30301 30317 30318 30319 30320 30321 30322 30323 30324 30325 30326 30327 30328 30329 30330 30331 30332 30333 30334 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30152 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 03/22/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 04:22 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 03/22/96 | +------------------------------------------------+EVENT TIME: 04:00[EST]| |NRC NOTIFIED BY: BILL BANDHAUER |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CREV SYSTEM DESIGN FLOW RATE CALCULATIONS MAY BE NONCONSERVATIVE - | | | | THE LICENSEE DETERMINED THAT THE CONTROL ROOM EMERGENCY VENTILATION (CREV) | | SYSTEM DESIGN CALCULATIONS ASSUMED NOMINAL AIR FLOW VALUES. THE CREV FANS | | HAVE AN ALLOWABLE ADJUSTMENT TOLERANCE OF ń10% OF THE NOMINAL FLOW RATE. | | THE CURRENTLY MEASURED ACTUAL FLOW RATES ARE WITHIN THE ALLOWABLE DESIGN | | FLOW RATE TOLERANCE. THE DESIGN CALCULATIONS DO NOT PROVIDE ASSURANCE THAT | | ADJUSTMENT WITHIN THIS TOLERANCE WILL PROVIDE ADEQUATE CHARCOAL FILTRATION | | EFFICIENCY AT THE HIGHER TOLERANCE OR ADEQUATE DILUTION OF AIR IN LEAKAGE | | (DOSE) AT THE LOWER TOLERANCE. THE CALCULATION IS CURRENTLY BEING | | REPERFORMED USING THE TOLERANCE VALUES. THE LICENSEE WILL RESOLVE THIS | | ISSUE PRIOR TO THE PLANT ENTERING MODE 4 WHEN THE CREV SYSTEM WILL BE | | REQUIRED. THE CASE FOR FUEL MOVEMENT (FUEL HANDLING ACCIDENT) HAS ALREADY | | BEEN ANALYZED AND IS WELL WITHIN THE DESIGN LIMITS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0906 ON 04/19/96, FROM NEUMAN TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS NOTIFICATION. THE REVISED CALCULATION HAS | | BEEN COMPLETED, AND SHOWED THAT THE UNIT WAS NOT OPERATING OUTSIDE OF ITS | | DESIGN BASIS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. THE NRC OPERATIONS CENTER | | NOTIFIED THE R2DO (CASTO). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30163 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 03/24/96 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 15:30 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 03/24/96 | +------------------------------------------------+EVENT TIME: 13:50[CST]| |NRC NOTIFIED BY: A. T. ROGERS |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MILTON SHYMLOCK 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 +------------------------------------------------------------------------------+ | LOCAL LEAK RATE TESTING FAILURE OF MAIN STEAM LINE ISOLATION VALVES WITH | | THE UNIT IN COLD SHUTDOWN | | | | DURING THE PERFORMANCE OF LOCAL LEAK RATE TESTING OF THE MAIN STEAM LINE | | ISOLATION VALVES WITH THE UNIT IN COLD SHUTDOWN, THE '2A' AND '2C' MAIN | | STEAM LINES EXCEEDED THE TECHNICAL SPECIFICATION LIMIT OF 11.5 STANDARD | | CUBIC FEET PER HOUR (SCFH). THE LEAK RATES FOR THE '2A' AND '2C' MAIN | | STEAM LINES WERE FOUND TO BE 18.69 SCFH AND 32.02 SCFH, RESPECTIVELY. AT | | THIS TIME, THE LICENSEE DOES NOT KNOW WHETHER OR NOT THE FAILURES OCCURRED | | ON THE INBOARD OR OUTBOARD VALVES. THE '2B' AND '2D' MAIN STEAM LINES WERE | | SATISFACTORILY TESTED. | | | | THE LICENSEE PLANS TO REPAIR AND RETEST THESE VALVES. THE LICENSEE ALSO | | PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | ***RETRACTION 04/19/96, @ 1651 EDT FROM WALDREP TAKEN BY MACKINNON*** | | | | THE TOTAL LEAKAGE DID NOT EXCEED THE MAXIMUM ALLOWABLE TECHNICAL | | SPECIFICATION LIMIT. THEREFORE, THE PLANT WAS NOT IN A SERIOUSLY DEGRADED | | CONDITION, AND THIS EVENT REPORT IS BEING RETRACTED. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. THE | | R2DO (CASTO) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30229 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/03/96 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 14:09 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/03/96 | +------------------------------------------------+EVENT TIME: 13:55[EST]| |NRC NOTIFIED BY: DAVID McDANIEL |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT THE RECIRCULATION SPRAY SYSTEM (RSS) MAY BE EXPOSED TO | | HIGHER TEMPERATURES THAN DESIGNED FOLLOWING A DESIGN BASIS ACCIDENT | | | | THE FOLLOWING IS A PORTION OF A FACSIMILE PROVIDED BY THE LICENSEE: | | | | "AN ENGINEERING REVIEW INDICATES THAT THE RSS (DESIGNED FOR 150 DEGREES | | FAHRENHEIT) MAY SEE SIGNIFICANTLY HIGHER TEMPERATURES FOLLOWING A LOCA, | | WHICH MAY RESULT IN SUPPORT STRESSES ABOVE ASME III, APPENDIX F, ALLOWABLE | | STRESSES FOR ONE-TIME FAULTED CONDITION. | | | | A LOSS OF SERVICE WATER TO ONE OR TWO RSS HEAT EXCHANGERS AND AN AUTOMATIC | | START OF THE RSS PUMPS AT APPROXIMATELY 11 MINUTES WOULD RESULT IN A HIGHER | | THAN ANALYZED TEMPERATURE RECIRCULATION FLOW FROM THE SUMP TO THE RSS | | HEADERS DOWNSTREAM OF THE HEAT EXCHANGERS. | | | | IT IS NOT APPARENT THAT OPERATORS WOULD HAVE CLEAR, UNAMBIGUOUS INDICATION, | | OR PROCEDURAL REQUIREMENTS TO ISOLATE THE RSS HEADERS TO PREVENT A FAULTED | | CONDITION." (END OF TEXT) | | | | THE UNIT IS NOT CURRENTLY IN ANY TECHNICAL SPECIFICATION LIMITING | | CONDITIONS FOR OPERATION AS A RESULT OF THIS CONDITION BECAUSE IT WAS | | DISCOVERED WHILE THE UNIT WAS IN A COLD SHUTDOWN CONDITION. TEMPERATURES | | AS HIGH AS 200 TO 250 DEGREES FAHRENHEIT MAY OCCUR. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPROPRIATE STATE | | AND LOCAL AUTHORITIES. THE LICENSEE ALSO PLANS TO ISSUE A PRESS RELEASE. | | | | ***UPDATE ON 04/19/96, @ 1506 EDT FROM D. ASHINGHURST TAKEN BY MACKINNON*** | | | | THE LICENSEE IS UPGRADING THIS EVENT TO A 1-HOUR REPORTABLE 10 CFR | | 50.72(b)(1)(ii)(B), OUTSIDE DESIGN BASIS, EVENT. ENSUING EVALUATIONS OF | | THE RSS AND QUENCH SPRAY SYSTEM IN CONTAINMENT HAVE SHOWN THAT THE PIPING | | WILL BE SUBJECTED TO TEMPERATURES IN EXCESS OF THOSE TO WHICH IT WAS | | ORIGINALLY DESIGNED AS THE RESULT OF A DESIGN BASIS ACCIDENT (LOCA, MLSB). | | PRELIMINARY ANALYTICAL RESULTS SHOW AN INCREASE IN PIPING STRESSES AND | | REVISED PIPE SUPPORT LOADINGS MAY RESULT IN PIPING SUPPORTS BEING OUTSIDE | | OF THE DESIGN BASIS OF THE PLANT. | | | | THE R1DO (JOHN WHITE) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. THE NRC | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30285 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 04/14/96 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 09:57 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/14/96 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: CLAYTON CHA |LAST UPDATE DATE: 04/21/96 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |JOHN HANNON, NRR EO | | |JIM MUSE FEMA | | |RICH BARRETT AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNUSUAL EVENT DECLARED ON UNIT 2 DUE TO BOTH EDGs BEING INOPERABLE - | | | | UNIT 1 IS AT 100% POWER WITH TWO OF TWO EDGs OPERABLE. UNIT 2 IS IN MODE 6 | | IN A REFUELING OUTAGE WITH THE ENTIRE CORE OFFLOADED INTO THE SPENT FUEL | | POOL. ONE OF TWO UNIT 2 EDGs ('CD') IS INOPERABLE FOR MAINTENANCE | | ACTIVITIES. | | | | AT 1000, THE LICENSEE DECLARED THE SECOND OF TWO UNIT 2 EDGs ('AB') | | INOPERABLE FOR MAINTENANCE ACTIVITIES AND DECLARED AN UNUSUAL EVENT ON | | UNIT 2 IN ACCORDANCE WITH THE EMERGENCY PLAN DUE TO TWO OF TWO UNIT 2 EDGs | | BEING INOPERABLE WITH UNIT 2 IN MODE 6 WITH THE CORE DEFUELED. THERE IS NO | | UNIT 2 TECHNICAL SPECIFICATION LCO ACTION STATEMENT APPLICABLE TO TWO OF | | TWO EDGs BEING INOPERABLE WITH UNIT 2 IN MODE 6 WITH THE CORE DEFUELED. THE | | LICENSEE DECLARED THE UNIT 2 'AB' EDG INOPERABLE WHILE THE UNIT 2 'CD' EDG | | WAS INOPERABLE SO AS NOT TO EXTEND THE LENGTH OF THE UNIT 2 REFUELING | | OUTAGE BEYOND THE PRESENT SCHEDULED UNIT 2 RESTART DATE OF MAY 5, 1996. | | | | THE NORMAL ELECTRICAL POWER SUPPLY (OFFSITE POWER) FOR BOTH UNITS FOR | | THE SPENT FUEL POOL COOLING SYSTEM IS AVAILABLE, AND THE UNIT 1 BACKUP | | POWER SUPPLY (TWO EDGs) FOR THE SPENT FUEL COOLING SYSTEM IS AVAILABLE. | | THE UNIT 2 BACKUP POWER SUPPLY (TWO EDGs) FOR THE SPENT FUEL POOL COOLING | | SYSTEM IS INOPERABLE. | | | | THE LICENSEE PLANS TO COMPLETE THE MAINTENANCE ACTIVITIES ON THE 'CD' EDG, | | DECLARE IT OPERABLE, AND TERMINATE THE UNUSUAL EVENT WITHIN 2 DAYS. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | | | | * * * 0925 APRIL 21, 1996, UPDATE FROM BRUCK RECEIVED BY TROCINE * * * | | | | THE LICENSEE TESTED BOTH INOPERABLE EDGs AND DID NOT NOTE ANY PROBLEMS. | | BECAUSE BOTH EDGs ARE NOW AVAILABLE (NOT OPERABLE), THE LICENSEE EXITED THE | | UNUSUAL EVENT AT 0920. THE LICENSEE NEEDS TO REVIEW START TIME TEST DATA | | BEFORE MAKING TECHNICAL SPECIFICATION OPERABILITY DETERMINATIONS FOR THE | | EDGs. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE | | STATE AND COUNTY OFFICIALS. THE NRC OPERATIONS CENTER NOTIFIED THE R3DO | | (CLAYTON), ERB (BARRETT), NRR EO (MATTHEWS), AND FEMA (STORER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30301 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 04/17/96 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 16:27 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/17/96 | +------------------------------------------------+EVENT TIME: 14:30[CDT]| |NRC NOTIFIED BY: MATTHEW ROBERT |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 +------------------------------------------------------------------------------+ | GREATER THAN 1% OF THE TUBES IN THE 1B STEAM GENERATOR ARE DEFECTIVE. | | | | WHILE INSPECTING 100% OF THE TUBES OF THE UNIT 1 STEAM GENERATORS AT THE | | HOT LEG TOP OF TUBE SHEET REGION, COMMONWEALTH EDISON (COM ED) DETERMINED | | THAT MORE THAN 1% OF THE INSPECTED TUBES WERE FOUND TO BE DEFECTIVE IN THAT | | THEY CONTAINED CONFIRMED INDICATIONS OF CIRCUMFERENTIAL AND/OR AXIAL | | CRACKING. THE ACTUAL NUMBER OF TUBES FOUND TO BE DEFECTIVE IS | | APPROXIMATELY 20% OF THE TUBES IN THE 1B STEAM GENERATOR. | | | | THE ACCEPTANCE CRITERIA SPECIFIED IN THE TECHNICAL SPECIFICATIONS REQUIRES | | A TUBE TO BE PLUGGED OR REPAIRED IF AN IMPERFECTION IS ņ40% THROUGH-WALL OR | | EXCEEDS 3 VOLTS BOBBIN VOLTAGE. CONFIRMED INDICATIONS OF CIRCUMFERENTIAL | | AND/OR AXIAL CRACKING AT THE TOP OF THE TUBES ARE ALSO CLASSIFIED AS | | DEFECTIVE AND ARE REPAIRED ACCORDINGLY. THESE INSPECTION RESULTS | | CORRESPOND TO A C-3 CLASSIFICATION FOR THE 1B STEAM GENERATOR, WHICH | | REQUIRES NRC NOTIFICATION. | | | | COM ED WILL COMPLETE THE REMAINING TOP OF TUBE SHEET AND BOBBIN COIL | | INSPECTIONS ON ALL STEAM GENERATORS. ALL DEFECTIVE TUBES WILL BE PLUGGED | | OR REPAIRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE ON 04/19/96, @ 1528 EDT FROM M. WINTER TAKEN BY MACKINNON*** | | | | THE TOP TUBE SHEET INSPECTION OF THE 1A, 1C, AND 1D STEAM GENERATORS HAS | | BEEN COMPLETED. COM ED HAS DETERMINED THAT MORE THAN 1% OF THE INSPECTED | | TUBES IN EACH STEAM GENERATOR WAS FOUND TO BE DEFECTIVE IN THAT THEY | | CONTAINED CONFIRMED INDICATIONS OF CIRCUMFERENTIAL AND/OR AXIAL CRACKING. | | IN ACCORDANCE WITH BYRON TECHNICAL SPECIFICATION 4.4.5.2, THESE INSPECTION | | RESULTS CORRESPOND TO A C-3 CLASSIFICATION FOR THE 1A, 1C, AND 1D STEAM | | GENERATORS. COM ED WILL COMPLETE THE REMAINING INSPECTIONS ON ALL STEAM | | GENERATORS, WILL PROVIDE AN UPDATE TO THE NRC OF SPECIFIC DEFECTIVE TUBE | | PERCENTAGES WHEN THE INSPECTIONS ARE COMPLETE, AND WILL PLUG OR REPAIR | | DEFECTIVE TUBES. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. THE R3DO (BRENT | | CLAYTON) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30317 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 04/19/96 | |UNIT: [1] [2] [ ] STATE: CA |NOTIFICATION TIME: 01:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/18/96 | +------------------------------------------------+EVENT TIME: 18:09[PDT]| |NRC NOTIFIED BY: JOSEPHENE BROWN |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAIR SPITZBERG RDO | |DTHR 73.71(c) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNCOMPENSATED PERIMETER DETECTION ZONES | | | | TWO AREAS WERE NOT PROMPTLY COMPENSATED FOR BY GUARDS. (REFER TO THE HOO | | LOG FOR DETAILS.) INVESTIGATION IS ON-GOING, BUT THE LICENSEE DOES NOT | | THINK THERE WAS ANY INTRUSION ONTO THE SITE. OFFICERS HAVE BEEN POSTED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30318 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 04/19/96 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 05:08 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 05:50[EDT]| |NRC NOTIFIED BY: ROY DUKE |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 7 STARTUP | 7 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT WILL BE SHUT DOWN PER TECHNICAL SPECIFICATION 3.0.3. | | | | THE LICENSEE WILL COMMENCE A UNIT SHUT DOWN AT 0550 EDT BECAUSE HPCI AND | | RCIC ARE BOTH INOPERABLE. HPCI WAS DECLARED INOPERABLE DUE TO NOT | | COMPLETING SURVEILLANCE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATION | | ALLOWED TIME LIMIT. THE STEAM LINE PRESSURE WAS TOO LOW TO START THE | | TESTING. RCIC WAS DECLARED INOPERABLE DUE TO VALVE SEAT LEAKAGE ON THE | | RCIC TURBINE STEAM INLET VALVE (E51-F045). THE LICENSEE IS INVESTIGATING | | THE REASON FOR THE LOW STEAM PRESSURE READINGS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE 04/19/96, @ 1701 EDT FROM S. MAREK TAKEN BY MACKINNON*** | | | | TECHNICAL SPECIFICATION 3.0.3 WAS EXITED AT 1606 EDT WHEN REACTOR VESSEL | | STEAM DOME PRESSURE WAS <150 psig. REACTOR VESSEL STEAM DOME PRESSURE HAS | | TO BE <150 psig WHEN RCIC AND HPCI ARE INOPERABLE. THE REACTOR WAS | | MANUALLY SCRAMMED FROM <1% (800 psig) REACTOR POWER. ALL CONTROL RODS | | FULLY INSERTED. ALL SYSTEMS OPERATING PROPERLY EXCEPT FOR HPCI AND RCIC. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | | THE R3DO (CLAYTON) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30319 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 04/19/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:43 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 10:50[EDT]| |NRC NOTIFIED BY: D. LATZ |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | LACK OF SEPARATION BETWEEN REDUNDANT CHANNELS OF RADIATION MONITORS FOUND | | DURING WALKDOWNS. | | | | THE LICENSEE DISCOVERED A LACK OF PHYSICAL SEPARATION BETWEEN REDUNDANT | | CHANNELS OF THE STEAM TUNNEL VENTILATION RADIATION MONITOR AND REACTOR | | BUILDING VENTILATION RADIATION MONITOR. THERE ARE TWO SEPARATE MONITORS | | AND THERE ARE TWO DETECTORS FOR EACH CHANNEL. THE DETECTOR CABLES BETWEEN | | THE ENDS OF THE CABLE CONDUITS AND THE DETECTORS WERE FOUND TO BE TOUCHING. | | THE UPDATED FINAL SAFETY ANALYSIS REPORT REQUIRES THAT WIRING FROM THE | | SENSORS TO THE CONTROL CABINETS FOR TWO REDUNDANT DIVISIONS OF A SAFETY | | FUNCTION BE PHYSICALLY SEPARATED OR BARRIERED. SINCE SEPARATION WAS NOT | | MAINTAINED, A SINGLE ACTIVE FAILURE OF THESE HIGH VOLTAGE CABLES COULD BE | | POSTULATED IN THAT BOTH CHANNELS WOULD BE RENDERED INOPERABLE. THE | | LICENSEE ENTERED TECHNICAL SPECIFICATION 3.2.E.2 , WHICH ALLOWS 24 HOURS OF | | OPERATION WITH ONLY 1 CHANNEL PER TRIP FUNCTION. | | | | PHYSICAL SEPARATION BETWEEN THE DETECTOR CABLES HAS BEEN ESTABLISHED USING | | SP-EE-076 AS A GUIDE TO ESTABLISH SUFFICIENT AIR SPACE. THE AFFECTED | | MONITORS WERE FUNCTIONALLY CHECKED USING EXISTING SURVEILLANCE PROCEDURES. | | BOTH CHANNELS OF THE STEAM TUNNEL VENTILATION RADIATION MONITORS AND BOTH | | CHANNELS OF THE REACTOR BUILDING VENTILATION RADIATION MONITOR ARE OPERABLE | | IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3.2.E.1. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30320 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 04/19/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 11:50 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 11:00[EDT]| |NRC NOTIFIED BY: R. HATHAWAY |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VIDEO CAMERA EQUIPMENT CABLE FOUND TO CROSS OVER FROM THE "A" TRAIN CABLE | | TRAY TO THE "B" TRAIN CABLE TRAY. | | | | DURING A PLANT TOUR, THE LICENSEE NOTICED THAT A CABLE THAT SUPPLIES VIDEO | | EQUIPMENT USED BY THE RADIATION CONTROLS DEPARTMENT HAD BEEN RUN IN THE | | PLANT CABLE TRAYS. THE VIDEO CABLE CROSSED BETWEEN THE "A" TRAIN AND THE | | "B" TRAIN CABLE TRAYS. THE EQUIPMENT THAT IS SUPPLIED BY THE CABLES IN | | THESE TRAYS IS NOT SPECIFICALLY KNOWN AT THIS TIME; HOWEVER, THE LICENSEE | | DOES KNOW THAT IT SUPPLIES SAFETY-GRADE EQUIPMENT. THE VIDEO CABLE HAS | | BEEN DISCONNECTED AND IS BEING REMOVED. IF IT IS LATER DETERMINED THAT THE | | EQUIPMENT SUPPLIED BY THE CABLE RUN THROUGH THESE TRAYS WAS NOT AFFECTED BY | | THE VIDEO CABLE, THIS REPORT WILL BE RETRACTED. | | | | THE LICENSEE WILL NOTIFY THE STATE OF MAINE OF THIS EVENT. THE NRC | | RESIDENT INSPECTOR WILL ALSO BE INFORMED OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30321 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 04/19/96 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 12:05 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 10:16[EDT]| |NRC NOTIFIED BY: R. PROBASCO |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 20 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MAIN TURBINE TRIPPED ON HIGH MAIN TURBINE VIBRATION CAUSING A REACTOR SCRAM | | | | THE REACTOR WAS BEING SHUT DOWN FOR A PLANNED FIVE-DAY MAINTENANCE OUTAGE. | | DURING THE SHUTDOWN, THE MAIN TURBINE TRIPPED DUE TO A VALID MAIN TURBINE | | HIGH VIBRATION SIGNAL. THE MAIN TURBINE VIBRATION TRIP SETPOINT IS 12 mils | | (HIGHEST VIBRATION SEEN WAS 13 mils). THE TURBINE TRIP CAUSED AN AUTOMATIC | | REACTOR SCRAM. ALL CONTROL RODS FULLY INSERTED INTO THE CORE. THE UNIT | | RECEIVED A GROUP 2 ISOLATION (DRYWELL AND REACTOR BUILDING VENTILATION) AND | | A GROUP 6 ISOLATION (REACTOR WATER CLEANUP). | | | | APPROXIMATELY 2 TO 3 MINUTES AFTER THE REACTOR SCRAM, A GROUP 1 ISOLATION | | (MAIN STEAM ISOLATION VALVES) WAS RECEIVED DUE TO HIGH REACTOR VESSEL WATER | | LEVEL (+50"). THE HIGH REACTOR VESSEL WATER LEVEL WAS CAUSED WHEN THE | | WATER LEVEL SUDDENLY SWELLED FROM +30" TO +50". (THE REACTOR FEEDWATER | | PUMP WAS IN SERVICE AT THIS TIME.) HIGH PRESSURE COOLANT INJECTION (HPCI) | | WAS THEN MANUALLY STARTED IN THE FULL FLOW TEST MODE OF OPERATION TO | | CONTROL REACTOR VESSEL PRESSURE, AND THE REACTOR WATER CLEANUP (RWCU) | | SYSTEM WAS USED TO REDUCE REACTOR VESSEL WATER LEVEL. HPCI WAS PLACED IN | | AND OUT OF SERVICE SEVERAL TIMES BEFORE HPCI TRIPPED ON HIGH REACTOR VESSEL | | WATER LEVEL AT ~1115 EDT. | | | | AFTER HPCI TRIPPED, THE LICENSEE OPENED ONE SAFETY/RELIEF VALVE (SRV) TO | | CONTROL REACTOR VESSEL PRESSURE AND LEVEL. (THE RWCU SYSTEM WAS STILL | | BEING USED TO REDUCE REACTOR VESSEL WATER LEVEL.) WITH REACTOR VESSEL | | PRESSURE IN ITS NORMAL BAND AND REACTOR VESSEL WATER LEVEL AT +40", THE SRV | | WAS CLOSED. WHEN THE SRV WAS CLOSED, THE REACTOR VESSEL WATER SHRANK LOWER | | THAN EXPECTED. AT ~1125 EDT, THE REACTOR VESSEL WATER LEVEL DECREASED TO | | THE RWCU ISOLATION SETPOINT OF +12" AND THEN INCREASED CAUSING A GROUP 6 | | (RWCU) ISOLATION. | | | | THE MAIN STEAM ISOLATION VALVES WERE REOPENED AT 1150 EDT. REACTOR VESSEL | | WATER LEVEL IS BEING MAINTAINED AT +25" VIA A REACTOR FEEDWATER PUMP, AND | | DECAY HEAT IS BEING DUMPED TO THE MAIN CONDENSER BY THE BYPASS VALVES. THE | | LICENSEE INTENDS TO COOL DOWN THE PLANT. THE LICENSEE DISCOVERED THAT THE | | MAIN GENERATOR LOCKOUT RELAY DID NOT LATCH FOLLOWING THE TURBINE TRIP. THE | | LICENSEE IS INVESTIGATING WHY THIS RELAY DID NOT OPERATE PROPERLY. THE | | LICENSEE WILL NOTIFY STATE AND LOCAL OFFICIALS OF THIS EVENT ON 04/20/96. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30322 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: MSD, INC |NOTIFICATION DATE: 04/19/96 | | CITY: DARLINGTON REGION: 2 |NOTIFICATION TIME: 12:03 [ET]| | COUNTY: STATE: SC |EVENT DATE: 04/19/96 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/19/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: MAHAFFEY | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEF 21.21(b)(2) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT - INCORRECT COILS INSTALLED IN TIME DELAY RELAYS | | | | THE FOLLOWING IS TEXT EXCERPTED FROM A FACSIMILE SUBMITTED BY THE VENDOR: | | | | "IT HAS COME TO OUR ATTENTION THAT A QUANTITY OF STRUTHERS-DUNN TYPE | | 236ABX135NE TIME DELAY RELAYS BUILT IN 1983 HAVE INCORRECT COILS IN THEM. | | SPECIFICALLY, THE AFFECTED RELAYS CONTAIN 39 GAUGE COILS; THEY SHOULD HAVE | | 43 GAUGE. AS A RESULT, THE COILS CONSUME SEVERAL TIMES THE REQUIRED POWER | | WHICH IS DISSIPATED AS HEAT, AND UPON PROLONGED ENERGIZATION MAY OVERHEAT | | TO THE POINT OF SELF-DESTRUCTION. WE HAVE ONE SUCH OCCURRENCE TO DATE. | | | | WE BELIEVE THE DEFECT WAS CAUSED BY PERSON OR PERSONS WHO RELIED ON MEMORY | | RATHER THAN DOCUMENTATION WHEN BUILDING THESE DEVICES. THEY WERE INTENDED | | FOR USE ON 125-VOLT DC CIRCUITS; THE COILS INSTALLED ARE THOSE NORMALLY | | USED ON 120-VOLT AC. SINCE THE RELAYS WOULD FUNCTION PROPERLY FOR BRIEF | | PERIODS, THE DEFECT WAS OBVIOUSLY OVERLOOKED. | | | | TO DATE, WE HAVE FOUND NINE RELAYS AS DESCRIBED, ALL AT GEORGIA POWER'S | | PLANT HATCH. ALL ARE DATE CODED 8335 WHICH INDICATES THEY WERE BUILT IN | | THE 35TH WEEK OF 1983. WE ARE OF THE OPINION THIS WAS THE ONLY TIME THIS | | OCCURRED, BUT THERE IS NO WAY TO PROVE IT ... FORTUNATELY, THESE RELAYS' | | COILS ARE CLEARLY MARKED, AND VERIFICATION OF CORRECT COIL GAUGE CAN BE | | ACCOMPLISHED WITH A VISUAL INSPECTION ... AGAIN, WE BELIEVE PLANT HATCH HAS | | THE ONLY ONES, BUT WE CANNOT BE CERTAIN." | | | | THE ASSETS OF STRUTHERS-DUNN WERE PURCHASED IN 1990 BY MSD, INC. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30323 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 04/19/96 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 12:37 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: NEUMAN |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CASTO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INSUFFICIENT ELECTRICAL SEPARATION OF TOXIC GAS MONITOR CHANNELS | | | | THE LICENSEE HAS DETERMINED THAT THE CABLE AND CIRCUIT SEPARATION CRITERIA | | FOR CABLES TO THE TOXIC GAS ANALYZERS WAS NOT MET. THE CABLES FROM THE AC | | POWER DISTRIBUTION PANELS ARE ROUTED THROUGH A COMMON CABLE TRAY. IN | | ADDITION, THERE IS NO ELECTRICAL ISOLATION BETWEEN THE SAFETY-RELATED AND | | NON-SAFETY RELATED PORTIONS OF THE ELECTRICAL POWER AND CONTROL CABLES TO | | THE TOXIC GAS ANALYZERS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |RESEARCH REACTOR | |EVENT NUMBER: 30324 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: U. S. GEOLOGICAL SURVEY |NOTIFICATION DATE: 04/19/96 | | RXTYPE: 1000 KW TRIGA MARK I |NOTIFICATION TIME: 14:01 [ET]| |COMMENTS: |EVENT DATE: 04/18/96 | | |EVENT TIME: 12:00[MDT]| | |LAST UPDATE DATE: 04/19/96 | | CITY: DENVER REGION: 4 +-----------------------------+ | COUNTY: DENVER STATE: CO |PERSON ORGANIZATION| |LICENSE#: R-133 AGREEMENT: Y |BRENT CLAYTON RDO | | DOCKET: 05000274 | | +------------------------------------------------+MARVIN MENDONCA NRR | |NRC NOTIFIED BY: JON RALSTON | | |HQ OPS OFFICER JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCHARGE OF 0.084 ęCI OF INSOLUBLE RADIOACTIVITY TO THE SANITARY SEWER | | SYSTEM | | | | THE RETENTION TANK WAS 3/4 FULL ON 04/08/96. ON 04/09/96, THE RETENTION | | TANK CONTENTS WERE RECIRCULATED, AND A PRE-RELEASE SAMPLE WAS TAKEN. THE | | PRE-RELEASE SAMPLE WAS COUNTED ON 04/10/96, AND NO INSOLUBLE ACTIVITY WAS | | DETECTED. | | | | ON 04/11/96, 250 GALLONS WAS PUMPED FROM THE RETENTION TANK TO THE SANITARY | | SEWER SYSTEM. A POST-RELEASE SAMPLE WAS TAKEN AT 1300 CDT ON 04/11/96, AND | | WAS COUNTED ON 04/12/96 (BETWEEN THE HOURS OF 1000 CDT TO 1500 CDT). THE | | FILTER PAPER THAT THE SAMPLE WAS ON BLEW OUT OF AN OPEN WINDOW AND FELL TWO | | STORIES TO THE GROUND BELOW. THIS IS THE POST-RELEASE SAMPLE THAT WAS | | COUNTED ON 04/12/96. INSOLUBLE ACTIVITY VALUE WAS SUSPECTED; THEREFORE, | | THE LICENSEE TOOK A SECOND POST-DISCHARGE SAMPLE, AND IT WAS COUNTED ON | | 04/17/96 (1100-1300 CDT). THE SAMPLE SHOWED AN INSOLUBLE ACTIVITY OF | | 5.5E-08 ęCI/ml (BETA-GAMMA). THE RETENTION TANK WAS RECIRCULATED ON | | 04/17/96, AND ANOTHER SAMPLE WAS TAKEN AT 1730 CDT. THE SAMPLE WAS COUNTED | | ON 04/18/96. THE PRESENTS OF INSOLUBLE ACTIVITY WAS CONFIRMED ON THIS | | SAMPLE. A TOTAL OF 0.084 ęCI/ml OF INSOLUBLE BETA-GAMMA ACTIVITY WAS | | DISCHARGED ON 04/11/96, AT A CONCENTRATION OF 8.9E-08 ęCI/ml TO THE | | SANITARY SEWER SYSTEM. UNIVERSITY OF ILLINOIS TECHNICAL SPECIFICATIONS DO | | NOT ALLOW ANY INSOLUBLE ACTIVITY TO BE DISCHARGED TO THE ENVIRONMENT. | | | | ALL DISCHARGES TO THE ENVIRONMENT FROM THE RETENTION TANK WILL BE SUSPENDED | | UNTIL THIS PROBLEM IS CORRECTED. | | | | REGION 3 (GARY SHEAR) WAS NOTIFIED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 30325 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: EXXON CO., USA |NOTIFICATION DATE: 04/19/96 | | CITY: BILLINGS REGION: 4 |NOTIFICATION TIME: 15:41 [ET]| | COUNTY: STATE: MT |EVENT DATE: 04/15/96 | |LICENSE#: 25-03375-01 AGREEMENT: N |EVENT TIME: 12:00[MDT]| | DOCKET: |LAST UPDATE DATE: 04/19/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BLAIR SPITZBERG RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: MIKE ERVIN | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IAIM 30.50(a) REG LIMITS EXCEEDED | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A 10-mCI CESIUM-137 SOURCE USED TO MEASURE LEVEL IN A TANK WAS ACCIDENTALLY | | SEVERED FROM ITS GAUGING TAPE. | | | | A 10-mCI CS-137 SOURCE GAUGE WAS THOUGHT TO BE BACK IN ITS STORED POSITION. | | THE GAUGE IS USED TO MEASURE LEVELS IN A 13' DIAMETER TANK. THE BLOCK | | VALVE (ISOLATION VALVE) FOR THE STORED GAUGING DEVICE WAS CLOSED. THE | | GAUGE SOURCE WAS NOT IN ITS STORED POSITION WHEN THE ISOLATION VALVE WAS | | CLOSED, AND THIS CUT THE GAUGING DEVICES TAPE WHICH CAUSED THE 10-mCI | | CS-137 GAUGING DEVICE TO DROP TO THE BOTTOM OF THE TUBE IN WHICH IT TRAVELS | | TO MEASURE THE TANK LEVEL. | | | | THE LICENSEE CALLED THE MANUFACTURER OF THE GAUGE (OHMART) AND INFORMED | | OHMART THAT HELP WAS NEEDED IN RETRIEVING THE SOURCE GAUGE. ACCESS TO THE | | TANK WAS RESTRICTED, AND RADIATION SURVEYS OF THE TANK WERE TAKEN. | | | | ON 04/17/96, AN OHMART REPRESENTATIVE RETRIEVED THE SOURCE GAUGE OUT OF THE | | TANK AND PLACED THE SOURCE BACK IN ITS STORED POSITION. THE OHMART | | REPRESENTATIVE RECEIVED A CALCULATED EXPOSURE TO HIS HAND OF 3 mREM WHILE | | HE WAS PLACING THE SOURCE GAUGE BACK IN ITS STORED POSITION. ALL RADIATION | | SAFETY PRECAUTIONS WERE TAKEN WHILE RETRIEVING THE GAUGE SOURCE. | | | | REGION 4 HAD ALREADY BEEN NOTIFIED OF THIS EVENT AND HAD MR. ERVIN OF EXXON | | CO. CALL THE OPERATION CENTER. THE LICENSEE WILL SEND A WRITTEN REPORT TO | | THE NRC DESCRIBING THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30326 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 04/19/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 15:43 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: HATHAWAY |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |DTHR 73.71(c) SECURITY DEGRADATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | SAFEGUARDS INFORMATION WAS FOUND TO BE NOT PROPERLY CONTROLLED AND STAMPED | | SAFEGUARDS INFORMATION. THE SAFEGUARDS INFORMATION HAS BEEN RETRIEVED, AND | | CORRECTIVE ACTIONS ARE BEING TAKEN TO PREVENT THIS FROM HAPPENING AGAIN. | | (REFER TO THE HOO LOG FOR ADDITIONAL INFORMATION.) | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30327 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 04/19/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 19:20 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 19:18[EDT]| |NRC NOTIFIED BY: NEWT YOUNG |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION 3.0.3 (CORRECT PROBLEM WITHIN 1 HOUR OR IN THE | | FOLLOWING 6 HOURS BE IN A HOT STANDBY CONDITION) ENTERED WHEN BOTH STATION | | BATTERIES WERE DECLARED OUT OF SERVICE. | | | | AN NRC INSPECTION TEAM ON SITE HAS FOUND THAT SEVERAL SMALL LOADS WHICH ARE | | TO BE SUPPLIED BY THE STATION BATTERIES DURING A LOSS OF AC POWER WERE | | MISSING FROM THE STATION BATTERY LOAD PROFILE CALCULATION. THE LICENSEE | | MEASURED THE LOADS OF THE EQUIPMENT IDENTIFIED BY THE NRC INSPECTION TEAM. | | | | AT THE PRESENT TIME, THERE IS A MEETING ON THE STATION BATTERY LOAD | | CALCULATIONS. ALL ECCS SYSTEMS ARE FULLY OPERABLE, AND THE EDGs ARE FULLY | | OPERABLE IF NEEDED. | | | | (REFER TO EVENT #30314 DATED APRIL 18, 1996, FOR BACKGROUND INFORMATION.) | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | ***UPDATE AT 2148 EDT ON 04/19/96, FROM NEWT YOUNG TAKEN BY MACKINNON*** | | | | STATION BATTERY LOAD PROFILE CALCULATIONS SHOW THAT THEY CAN CARRY THE | | EXTRA LOADS THAT HAD NOT BEEN ACCOUNTED FOR IN THE ORIGINAL STATION BATTERY | | LOAD PROFILE. THE LICENSEE DECLARED THE STATION BATTERIES BACK IN SERVICE | | AND FULLY OPERABLE IF NEEDED. TECHNICAL SPECIFICATION 3.0.3 WAS EXITED AND | | PLANT SHUTDOWN WAS TERMINATED AT 2140 EDT WITH REACTOR POWER AT A LEVEL OF | | 45%. REACTOR POWER LEVEL WILL BE INCREASED BACK TO 100%. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT | | UPDATE. THE R1DO (WHITE) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30328 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/19/96 | |UNIT: [ ] [2] [ ] STATE: AL |NOTIFICATION TIME: 19:33 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/19/96 | +------------------------------------------------+EVENT TIME: 18:13[CDT]| |NRC NOTIFIED BY: MARTIN |LAST UPDATE DATE: 04/19/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF ONE STEAM GENERATOR TUBE THAT IS NOT PERMITTED TO BE IN | | SERVICE PER TECHNICAL SPECIFICATION 3.4.6 | | | | FARLEY HAS DISCOVERED THAT ONE STEAM GENERATOR TUBE IN THE "B" STEAM | | GENERATOR IS NOT PERMITTED TO BE IN SERVICE PER TECHNICAL SPECIFICATION | | 3.4.6. THE ACTION REQUIREMENT FOR THE SPECIFICATION IS NOT MET. THUS, | | TECHNICAL SPECIFICATION 3.0.3 WAS ENTERED. THE VARIANCE BETWEEN THE TOP OF | | THE TUBE SHEET AND THE BOTTOM OF THE ROLL TRANSITION HAD NOT BEEN ACCOUNTED | | FOR DURING PREVIOUS INSPECTION. RE-ANALYSIS OF F* (F STAR) TUBES | | DISCOVERED A TUBE WITH INDICATIONS NOT ALLOWED BY F* (F STAR) CRITERIA IN | | SERVICE. UNIT 2 MUST BE IN HOT STANDBY BY 0113 CDT ON 04/20/96. ALL ECCS | | SYSTEMS AND THE EDGs ARE FULLY OPERABLE IF NEEDED. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE OF THIS EVENT. | | | | *** RETRACTION AT 2205 EDT ON 04/19/96, FROM MARTIN TAKEN BY MACKINNON *** | | | | FARLEY NUCLEAR POWER PLANT IS RETRACTING THE NOTIFICATION OF SHUTDOWN | | REQUIRED BY TECHNICAL SPECIFICATION 3.0.3. UPON DISCUSSION WITH | | ENGINEERING AND LICENSING IT HAS BEEN DETERMINED THAT ENTRY INTO TECHNICAL | | SPECIFICATION 3.0.3 WAS PREMATURE. EVALUATION OF EDDY CURRENT DATA SHOWS | | THAT THE "B" STEAM GENERATOR TUBE IN QUESTION IS NOT OUTSIDE ITS TECHNICAL | | SPECIFICATION CRITERION. THE LICENSEE EXITED TECHNICAL SPECIFICATION 3.0.3 | | AT 2054 CDT. REACTOR POWER LEVEL WAS AT 71% WHEN TECHNICAL SPECIFICATION | | 3.0.3 WAS EXITED. THE LICENSEE WILL INCREASE REACTOR POWER BACK TO 100%. | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. THE R2DO | | (CASTO) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30329 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 04/20/96 | |UNIT: [ ] [2] [ ] STATE: TN |NOTIFICATION TIME: 05:10 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/20/96 | +------------------------------------------------+EVENT TIME: 01:12[EDT]| |NRC NOTIFIED BY: ROBERT HAYS |LAST UPDATE DATE: 04/20/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 HOT STANDBY | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF THE INABILITY OF AN INPUT TO THE REACTOR PROTECTION SYSTEM | | (RPS) TO TRIP THE REACTOR IF A TURBINE TRIP OCCURRED. | | | | DURING REMOVAL OF THE UNIT FROM SERVICE FOR A SCHEDULED REFUELING OUTAGE, | | THE REACTOR WAS MANUALLY TRIPPED FROM APPROXIMATELY 20% POWER PER PLANT | | OPERATING PROCEDURES, AND THE EMERGENCY PROCEDURE NETWORK WAS ENTERED. | | DURING THE PERFORMANCE OF THE IMMEDIATE OPERATOR ACTIONS, ONE BISTABLE | | LIGHT INDICATION FOR A TURBINE THROTTLE VALVE DID NOT SHOW FULLY CLOSED. | | THIS VALVE WAS VERIFIED TO BE CLOSED BY WAY OF THE LVDT METER (WHICH SHOWED | | '0'), BY THE FACT THAT THERE WAS NO REACTOR COOLANT SYSTEM COOLDOWN IN | | PROGRESS, AND BY LOCAL VERIFICATION. AT APPROXIMATELY 0500, THE LICENSEE'S | | INVESTIGATION FOUND THAT A THROTTLE VALVE LINKAGE THAT OPERATES THE LIMIT | | SWITCHES, WHICH ARE A BACKUP/REDUNDANT INPUT TO THE RPS, HAD BROKEN. | | ESSENTIALLY, THIS INPUT TO THE RPS WOULD HAVE BEEN UNABLE TO TRIP THE | | REACTOR IF A TURBINE TRIP HAD OCCURRED THROUGH THIS INPUT FROM LIMIT | | SWITCHES OFF OF FOUR THROTTLE VALVES. THIS IS A REDUNDANT CHANNEL, AND | | THIS IS NOT TO SAY THAT A REACTOR TRIP WOULD NOT HAVE OCCURRED FROM A | | TURBINE TRIP (ONLY THIS INPUT). | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. AUXILIARY FEEDWATER IS BEING | | SUPPLIED TO THE STEAM GENERATORS, AND SECONDARY STEAM IS BEING DUMPED TO | | THE CONDENSER. IN ADDITION, NORMAL CHARGING AND MAKEUP, PRESSURIZER | | HEATERS AND SPRAYS, AND THE REACTOR COOLANT PUMPS ARE BEING UTILIZED FOR | | PRIMARY SYSTEM INVENTORY, PRESSURE, AND TRANSPORT CONTROL. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30330 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/20/96 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 09:26 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/20/96 | +------------------------------------------------+EVENT TIME: 09:14[EDT]| |NRC NOTIFIED BY: BARRY COLEMAN |LAST UPDATE DATE: 04/20/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DAVID MATTHEWS, NRR EO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL |BUTCH STINEDURF FEMA | | |RICH BARRETT ERB | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNUSUAL EVENT DUE TO THE TRANSPORT OF A POTENTIALLY CONTAMINATED INJURED | | INDIVIDUAL OFFSITE | | | | A CONTRACTOR FELL APPROXIMATELY TEN FEET OFF SCAFFOLDING IN THE DRYWELL AND | | SUSTAINED SEVERE HEAD INJURIES AND POSSIBLE CHEST INJURIES. THE INDIVIDUAL | | WAS NOT FRISKED AND WAS TRANSPORTED AS CONTAMINATED (WITH SOME OF HIS | | PROTECTIVE CLOTHING ON) TO A MEDICAL FACILITY VIA AN AMBULANCE AT 0914. THE | | LICENSEE DECLARED AN UNUSUAL EVENT AT THAT TIME DUE TO THE TRANSPORT OF A | | POTENTIALLY CONTAMINATED INJURED INDIVIDUAL OFFSITE. THE LICENSEE | | CURRENTLY PLANS TO TERMINATE THE UNUSUAL EVENT WHEN HEALTH PHYSICS | | PERSONNEL CAN CONFIRM THAT THE INDIVIDUAL IS NOT CONTAMINATED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL OFFICIALS. | | | | * * * 1047 APRIL 20, 1996, UPDATE FROM COLEMAN RECEIVED BY TROCINE * * * | | | | THE INJURED INDIVIDUAL WAS SURVEYED AT THE HOSPITAL AND WAS FOUND TO BE | | CONTAMINATED (SLIGHTLY OVER THE LIMIT OF 100 COUNTS PER MINUTE OVER A 1,000 | | SQUARE CENTIMETER AREA). THE INDIVIDUAL WAS DECONTAMINATED AND TRANSPORTED | | FROM THE APPLING COUNTY HOSPITAL IN BAXLEY, GEORGIA, TO SAVANNAH, GEORGIA | | VIA A HELICOPTER. THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 1036 WHEN | | THE INDIVIDUAL WAS NO LONGER CONTAMINATED. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR AND THE APPLICABLE | | STATE AND LOCAL OFFICIALS. THE NRC OPERATIONS CENTER NOTIFIED THE R2DO | | (CASTO), THE NRR EO (MATTHEWS), AND FEMA (AUSTIN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30331 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAINT LUCIE REGION: 2 |NOTIFICATION DATE: 04/20/96 | |UNIT: [ ] [2] [ ] STATE: FL |NOTIFICATION TIME: 16:55 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/20/96 | +------------------------------------------------+EVENT TIME: 15:56[EDT]| |NRC NOTIFIED BY: JACK BREEN |LAST UPDATE DATE: 04/20/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 83 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DURING QUARTERLY PERFORMANCE OF THE MAIN TURBINE TRIP TEST, IT WAS | | DETERMINED THAT PORTIONS OF THE TURBINE OVERSPEED PROTECTION SYSTEM MAY NOT | | BE OPERATING PROPERLY. | | | | AT 1328 EDT, THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.3.4 (TURBINE | | OVERSPEED PROTECTION) WHEN IT WAS DETERMINED THAT PORTIONS OF THE TURBINE | | OVERSPEED PROTECTION SYSTEM MAY NOT BE FUNCTIONING PROPERLY. WHILE | | PERFORMING STEP 6 OF OPERATING PROCEDURE NO. 2-0030150 (SECONDARY PLANT | | OPERATING CHECKS AND TESTS), AUTO STOP OIL PRESSURE RETURNED TO | | APPROXIMATELY 60 psig ON THE LOCAL TEST GAUGE. SINCE 60 psig IS NOT WITHIN | | THE ALLOWED BAND (90 - 110 psig) PER THE PROCEDURAL STEP, STEP 6 COULD NOT | | BE PERFORMED SATISFACTORILY. THEREFORE, THE TESTING OF THE OVERSPEED TRIP | | MECHANISM COULD NOT BE COMPLETED AT THIS POINT. ADDITIONALLY, SINCE AUTO | | STOP OIL PRESSURE DID NOT RETURN TO NORMAL INDICATION LOCALLY, THE | | OVERSPEED TRIP HANDLE COULD NOT BE RETURNED TO THE NORMAL POSITION FROM THE | | TEST POSITION. IT WAS THEN DETERMINED THAT PORTIONS OF THE TURBINE | | OVERSPEED PROTECTION SYSTEM MAY NOT BE FUNCTIONAL IN THIS CONDITION, AND | | THE LICENSEE ENTERED TECHNICAL SPECIFICATION 3.3.4. THIS TECHNICAL | | SPECIFICATION STATES THAT THE MAIN TURBINE MUST BE ISOLATED FROM THE MAIN | | STEAM SUPPLY WITHIN 6 HOURS AFTER ENTERING THE TECHNICAL SPECIFICATION. THE | | LICENSEE COULD NOT REPAIR THE TRIP MECHANISM, SO THE LICENSEE COMMENCED A | | REACTOR SHUTDOWN AT 1556 EDT. THE LICENSEE WILL HAVE THE MAIN TURBINE OFF | | LINE BY 1928 EDT. THE REACTOR WILL REMAIN CRITICAL WHILE THE MAIN TURBINE | | TRIP MECHANISM IS REPAIRED. ALL EMERGENCY CORE COOLING SYSTEMS AND THE | | EMERGENCY DIESEL GENERATORS ARE FULLY OPERABLE IF NEEDED. THE ELECTRICAL | | GRID IS STABLE. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | | | | ***UPDATE 04/20/96 @ 2051 EDT FROM STEVE MERRILL TAKEN BY MACKINNON*** | | | | REACTOR POWER IS STABLE AT 3%, AND THE MAIN TURBINE HAS BEEN TRIPPED. THE | | LICENSEE PLANS TO RELATCH THE MAIN TURBINE TO RE-PERFORM TROUBLESHOOTING ON | | THE TURBINE TRIP MECHANISM. IF THE MAIN TURBINE CHECKS OUT SATISFACTORILY, | | THE LICENSEE WILL RECOMMENCE INCREASING REACTOR POWER ON THE MIDNIGHT | | SHIFT. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED OF THE UPDATE BY THE LICENSEE. THE | | R2DO (CASTO) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30332 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 04/21/96 | |UNIT: [ ] [ ] [3] STATE: AL |NOTIFICATION TIME: 05:50 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 04/21/96 | +------------------------------------------------+EVENT TIME: 03:51[CDT]| |NRC NOTIFIED BY: DONALD C. SMITH |LAST UPDATE DATE: 04/22/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM AND AUTOMATIC INITIATION OF HIGH PRESSURE COOLANT | | INJECTION (HPCI) AND REACTOR CORE ISOLATION COOLING (RCIC) AS A RESULT OF | | LOW WATER LEVEL DUE TO THE LOSS OF ONE OF THREE REACTOR FEEDWATER PUMPS | | | | THE 'C' FEEDWATER PUMP TRIPPED FOR UNKNOWN REASONS CAUSING REACTOR WATER | | LEVEL TO DECREASE, AND A LOW LEVEL REACTOR SCRAM FROM 100% POWER OCCURRED | | WHEN WATER LEVEL REACHED THE SCRAM SETPOINT OF -11 INCHES. IN ADDITION, | | BOTH HPCI AND RCIC AUTOMATICALLY INJECTED INTO THE VESSEL WHEN WATER LEVEL | | REACHED -45 INCHES. WATER LEVEL DECREASED TO A MAXIMUM OF -47 INCHES. THE | | REACTOR SCRAM CAUSED A TURBINE TRIP, AND THE TURBINE TRIP IN TURN CAUSED | | THE RECIRCULATION PUMPS TO TRIP. ALL RODS FULLY INSERTED DUE TO THE | | REACTOR SCRAM, AND ALL SYSTEMS FUNCTIONED AS REQUIRED. EXPECTED GROUP | | ISOLATIONS 2 (DRYWELL FLOOR AND EQUIPMENT DRAIN ISOLATION VALVES), 3 | | (REACTOR WATER CLEANUP), 6 (PRIMARY AND SECONDARY CONTAINMENT VENTILATION | | ISOLATIONS), AND 8 (TRANSVERSING INCORE PROBES) WERE RECEIVED; AND BOTH THE | | STANDBY GAS TREATMENT AND CONTROL ROOM EMERGENCY VENTILATION SYSTEMS | | AUTOMATICALLY INITIATED AS EXPECTED. NONE OF THE SAFETY RELIEF VALVES | | LIFTED DURING THIS TRANSIENT. | | | | THE UNIT IS CURRENTLY STABLE IN HOT STANDBY. BOTH HPCI AND RCIC HAVE BEEN | | SECURED, AND AT THE TIME OF THIS NOTIFICATION, THE LICENSEE WAS UNSURE OF | | THE AMOUNT OF WATER THAT WAS INJECTED BY THESE SYSTEMS. NORMAL FEEDWATER | | IS CURRENTLY BEING SUPPLIED TO THE VESSEL, THE MAIN STEAM ISOLATIONS VALVES | | ARE OPEN, AND THE CONDENSER IS AVAILABLE AS A HEAT SINK. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE FEEDWATER PUMP TRIP AND THE | | REASON FOR WATER LEVEL DECREASING TO -47 INCHES. TYPICALLY, WITH A SINGLE | | FEEDWATER PUMP TRIP, WATER LEVEL WOULD BE RECOVERED WITH THE REMAINING TWO | | FEEDWATER PUMPS. A RESTART DATE HAS NOT YET BEEN DETERMINED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND PLANS TO SUBMIT A | | LICENSEE EVENT REPORT. | | | | * * * 0417 APRIL 22 , 1996, UPDATE FROM SMITH RECEIVED BY TROCINE * * * | | | | DURING THE MORNING STATUS CALL ON APRIL 22, 1996, THE LICENSEE PROVIDED THE | | FOLLOWING ADDITIONAL INFORMATION: | | | | PER THE ABNORMAL OPERATING INSTRUCTIONS, OPERATORS REDUCED REACTOR POWER TO | | APPROXIMATELY 82% TO 85% AFTER THE 'C' REACTOR FEEDWATER PUMP TRIPPED AND | | PRIOR TO THE REACTOR SCRAM. THIS WOULD NORMALLY BE THE APPROPRIATE ACTION | | FOR TWO PUMP OPERATION. HOWEVER, THE REMAINING TWO OPERATING REACTOR | | FEEDWATER PUMPS DID NOT MAINTAIN REACTOR VESSEL WATER LEVEL DUE TO LEAKBY | | ON THE DISCHARGE CHECK VALVE FOR THE 'C' FEEDWATER PUMP FOLLOWING THE PUMP | | TRIP. THE ACTUAL LEVEL DROP WAS RAPID AND QUITE SEVERE. IN ADDITION, BOTH | | HPCI AND RCIC RAN FOR APPROXIMATELY 1-1/2 MINUTES. THE LICENSEE CURRENTLY | | PLANS TO PLACE THE UNIT BACK ON LINE TODAY. | | | | THE NRC OPERATIONS CENTER NOTIFIED THE R2DO (CASTO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30333 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 04/21/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 17:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 04/21/96 | +------------------------------------------------+EVENT TIME: 16:52[EDT]| |NRC NOTIFIED BY: M. EARLES |LAST UPDATE DATE: 04/21/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO 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 Y 12 STARTUP | 2 STARTUP | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUXILIARY FEEDWATER PUMPS AUTOMATICALLY STARTED ON A LOSS OF BOTH MAIN | | FEEDWATER PUMPS (MFW). | | | | OPERATING MFW PUMP "1A" TRIPPED ON LOW VACUUM WHILE THE LICENSEE WAS | | ADJUSTING THE MANUAL VALVE FROM MAIN FEEDWATER PUMP TURBINE CONDENSER TO | | THE MAIN CONDENSER. NON-OPERATING MFW PUMP "1B" WAS NOT RESET AT THE TIME | | MFW PUMP "1A" TRIPPED ON LOW VACUUM. (THIS IS NORMAL AT LOW POWER LEVELS.) | | BOTH THE MOTOR-DRIVEN AND THE TURBINE-DRIVEN AUXILIARY FEEDWATER PUMPS | | AUTOMATICALLY STARTED ON A LOSS OF BOTH MFW PUMPS SIGNAL. THE LICENSEE | | ENTERED THE ABNORMAL OPERATING PROCEDURE FOR A LOSS OF MAIN FEEDWATER | | (AOI-16) AND REDUCED REACTOR POWER TO 2% TO BE WITHIN AUXILIARY FEEDWATER | | CAPABILITY. | | | | THE STEAM GENERATOR #1 AUXILIARY FEEDWATER LEVEL CONTROL VALVE (LCV-3-174) | | FAILED TO TRANSFER TO MANUAL WHEN A UNIT OPERATOR ATTEMPTED MANUAL CONTROL | | OF THE AUXILIARY FEEDWATER FLOW TO STEAM GENERATOR #1. PROPER WATER LEVEL | | WAS MAINTAINED IN THE STEAM GENERATORS DURING THE EVENT. | | | | THE LICENSEE WILL INVESTIGATE WHY THE AUXILIARY FEEDWATER LEVEL CONTROL | | LEVEL VALVE FAILED TO TRANSFER TO MANUAL. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30334 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 04/21/96 | |UNIT: [1] [ ] [3] STATE: SC |NOTIFICATION TIME: 18:48 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 04/21/96 | +------------------------------------------------+EVENT TIME: 17:20[EDT]| |NRC NOTIFIED BY: M. HILL |LAST UPDATE DATE: 04/21/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHUCK CASTO 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 | | | | | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INOPERABILITY OF CONTAINMENT HYDROGEN RECOMBINER CONDENSATE PUMPS (TWO PER | | UNIT) DUE TO MECHANICAL BINDING | | | | THE OCONEE UNIT 1 AND 3 CONTAINMENT HYDROGEN CONTROL SYSTEMS' FLOW PATHS | | WERE DECLARED INOPERABLE PER TECHNICAL SPECIFICATION 3.16.3 DUE TO EACH | | UNITS' HYDROGEN RECOMBINER CONDENSATE SKID PUMPS "A" AND "B" BEING FOUND | | INOPERABLE. THE PUMPS WERE INSTALLED ABOUT TWO MONTHS AGO, AND THIS IS THE | | FIRST TIME THAT THEY HAVE BEEN TESTED SINCE THEY WERE INSTALLED PER A | | MODIFICATION. THE PUMPS WERE INSTALLED TO REMOVE MOISTURE FROM THE | | HYDROGEN RECOMBINER SYSTEM, ARE BETWEEN 1/3 TO 1/2 HORSEPOWER IN SIZE, AND | | ARE LOCATED IN PENETRATION RUNS. OPERABILITY OF THE PUMPS WAS CHECKED | | AFTER THEY WERE INSTALLED. THE LICENSEE WAS ABLE TO FREE UP THE PUMPS | | AFTER LOOSENING THE MOTOR FROM THE PUMP AND AGITATING THE PUMPS. THE | | LICENSEE HAS SIX SPARE PUMPS ON HAND (FOUR OF WHICH ARE OPERABLE.), AND | | EACH CAN BE INSTALLED WITHIN ONE HOUR. ENGINEERING IS INVESTIGATING WHY | | THE PUMPS ARE BINDING UP MECHANICALLY. AFTER THE CAUSE IS FOUND AND | | CORRECTED, THE SPARE PUMPS WILL BE INSTALLED ON UNITS 1 AND 3. UNITS 1 AND | | 3 ENTERED A 7-DAY LIMITING CONDITION OF OPERATION AT 1720. | | | | THE UNIT 2 CONTAINMENT HYDROGEN CONTROL SYSTEM FLOW PATH IS ALSO BEING | | REPORTED SINCE IT WOULD HAVE BEEN INOPERABLE IF UNIT 2 HAD BEEN ABOVE COLD | | SHUTDOWN. AT 1400 ON 04/20/96, HYDROGEN RECOMBINER CONDENSATE SKID PUMP | | "A" INDICATED THAT IT COULD NOT PERFORM ITS INTENDED FUNCTION (MECHANICAL | | BINDING OF THE PUMP). THE "B" CONDENSATE SKID PUMP WAS FOUND TO BE | | INOPERABLE AT 1100 ON 04/21/96. THE UNIT 1 AND 3 CONDENSATE SKID PUMPS | | WERE INSPECTED DUE TO THE FAILURE OF THE UNIT 2 CONDENSATE SKID PUMPS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE OF THIS EVENT. | +------------------------------------------------------------------------------+