U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/15/96 - 11/18/96 ** EVENT NUMBERS ** 29924 31179 31298 31338 31339 31340 31341 31342 31343 31344 31345 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29924 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALISADES REGION: 3 |NOTIFICATION DATE: 02/02/96 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 10:38 [ET]| |RX TYPE: [1] CE |EVENT DATE: 02/02/96 | +------------------------------------------------+EVENT TIME: 09:51[EST]| |NRC NOTIFIED BY: ROBERT VINCENT |LAST UPDATE DATE: 11/17/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RONALD GARDNER RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR THE LOSS OF BOTH TRAINS OF PRIMARY COOLANT SYSTEM | | POWER-OPERATED RELIEF VALVES DURING A POSTULATED APPENDIX 'R' EXPOSURE FIRE | | | | DURING A PLANNED ONGOING RE-EVALUATION OF APPENDIX 'R' COMPLIANCE | | STRATEGIES, THE LICENSEE DISCOVERED THAT A LACK OF COORDINATION EXISTS | | BETWEEN THE FUSES IN THE MAIN DC POWER FEED TO ELECTRICAL PANELS D21-1 AND | | D11-1 AND SELECTED BREAKERS SUPPLYING BRANCH CIRCUITS OFF OF THESE PANELS. | | AN APPENDIX 'R' EXPOSURE FIRE IN SELECTED AREAS IS POSTULATED TO RESULT IN | | MULTIPLE CABLE SHORTS. THESE SHORTS COULD RESULT IN THE CLEARING OF THE | | MAIN POWER FEED FUSES BEFORE THE BRANCH CIRCUITS SUPPLYING THE FAULTED | | CABLES. LOSS OF D21-1 AND D11-1 WOULD RESULT IN LOSS OF BOTH TRAINS OF THE | | PRIMARY COOLANT SYSTEM POWER-OPERATED RELIEF VALVES WHICH WOULD BE NEEDED | | TO ACHIEVE COLD SHUTDOWN. | | | | ALL PANELS AND ASSOCIATED EQUIPMENT REMAIN OPERABLE. THIS IS ONLY AN ISSUE | | UNDER APPENDIX 'R' WITH AN EXPOSURE FIRE. SINGLE RANDOM CABLE FAULTS | | CANNOT CAUSE LOSS OF BOTH TRAINS OF POWER-OPERATED RELIEF VALVES. | | COMPENSATORY FIRE TOURS HAVE BEEN ESTABLISHED. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1324 ON 11/17/96 BY ROBERTS, TAKEN BY WEAVER * * * | | TESTING OF THE INDIVIDUAL BRANCH CIRCUIT BREAKERS IS BEING PERFORMED TO | | ASSURE COORDINATION WITH SYSTEM FUSES. FOUR OF THE 72 BREAKERS HAVE BEEN | | TESTED AND THEY HAVE ALL FAILED TO TRIP. ALL 72 BREAKERS HAVE BEEN | | SCHEDULED FOR REPLACEMENT. IT IS ESTIMATED THAT TESTING OF THE EXISTING | | CIRCUIT BREAKERS WILL ALSO RESULT IN ADDITIONAL FAILURES AND THAT ANALYSIS | | OF THESE POTENTIAL FAILURES WOULD HAVE PUT THE PLANT IN A CONDITION OUTSIDE | | THE DESIGN BASIS. SINCE THIS DISCOVERY WAS MADE WITH THE PLANT SHUTDOWN, | | IT WAS REPORTED AS A FOUR HOUR REPORT (DEGRADED WHILE SHUTDOWN). | | | | THIS PLANT CONDITION HAS BEEN ANALYZED UNDER APPENDIX R AND THOSE | | PROVISIONS FOR BRINGING THE PLANT FROM POWER TO HOT SHUTDOWN APPEAR TO NOT | | TO HAVE BEEN AFFECTED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31179 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 10/18/96 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:09 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 10/18/96 | +------------------------------------------------+EVENT TIME: 17:00[EDT]| |NRC NOTIFIED BY: FAULKNER |LAST UPDATE DATE: 11/15/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HERB WILLIAMS RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DEGRADATION OF THE STANDBY LIQUID CONTROL (SLC) SYSTEM | | | | SLC SYSTEM PERFORMANCE MAY HAVE BEEN IN A DEGRADED CONDITION DUE TO THE | | COMMON SLC STORAGE TANK BEING OPERATED AT A HIGHER THAN NORMAL OPERATING | | TEMPERATURE (ò 122øF) DURING CHEMICAL ADDITION AND SAMPLING OPERATIONS. THE | | CONCERN IS THE REQUIRED NET POSITIVE SUCTION HEAD FOR BOTH SLC PUMPS. IF | | THE TEMPERATURE OF THE SLC TANK IS ò 122øF, THE NET POSITIVE SUCTION HEAD | | WILL NOT BE SUFFICIENT TO SUPPORT A DISCHARGE FLOW RATE FROM EACH SLC PUMP | | OF ò 41.5 GPM (THE MINIMUM TECHNICAL SPECIFICATION FLOW RATE FOR EACH SLC | | PUMP). IN THE PAST, WHEN MIXING THE CHEMICAL USED IN THE SLC TANK, THE | | TEMPERATURE OF THE LIQUID INSIDE THE SLC TANK HAS BEEN AS HIGH AS 140øF. | | THE OPERATING PROCEDURE FOR THE SLC SYSTEM HAS ALWAYS HAD A MINIMUM | | TEMPERATURE AT WHICH THE SLC SYSTEM SHOULD BE MAINTAINED, BUT THE PROCEDURE | | HAS NEVER SPECIFIED A MAXIMUM TEMPERATURE LIMIT. CORRECTIVE ACTION IS TO | | ADD A MAXIMUM OPERATING TEMPERATURE LIMIT FOR THE SLC TANK. | | | | THE LICENSEE NOTIFIED LOWER ALLOWAYS CREEK TOWNSHIP OF THIS EVENT. THE NRC | | RESIDENT WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1150 EST ON 11/15/96 FROM MAHONY TAKEN BY KARSCH * * * | | THE LICENSEE IS RETRACTING THIS EVENT BASED ON AN ENGINEERING EVALUATION | | WHICH DETERMINED THAT THE SLC PUMP'S NET POSITIVE SUCTION HEAD (NPSH) | | REQUIREMENTS WOULD BE SATISFIED FOR ALL POSTULATED OPERATING CONDITIONS, | | INCLUDING THE ELEVATED TEMPERATURES ENCOUNTERED DURING CHEMICAL ADDITION. | | THE MAXIMUM RATED TEMPERATURE FOR THE SLC STORAGE TANK HEATERS IS 150øF, | | WHICH DOES NOT REDUCE THE DENSITY OF THE LIQUID TO A POINT WHICH TRIGGERS | | NPSH CONCERNS. SINCE THE SAFETY FUNCTION OF THE SLC SYSTEM COULD BE | | FULFILLED, THIS EVENT REPORT IS BEING RETRACTED. THE LICENSEE WILL INFORM | | THE NRC RESIDENT INSPECTOR. R1DO (BARKLEY) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 31298 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PROFESSIONAL SERVICE INDUSTRIES INC |NOTIFICATION DATE: 11/08/96 | | CITY: BRISTOL REGION: 2 |NOTIFICATION TIME: 11:16 [ET]| | COUNTY: STATE: VA |EVENT DATE: 05/01/96 | |LICENSE#: 45-25088-01 AGREEMENT: N |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 11/15/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |EDWARD MCALPINE RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: ACKERMANN | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE1 20.2202(b)(1) PERS OVEREXPOSURE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBLE EXPOSURE TO A PROFESSIONAL SERVICE INDUSTRIES, INC. TECHNICIAN'S | | EXTREMITY (POSSIBLY IN EXCESS OF 50 REM) DURING DIRECT HANDLING OF A | | PORTABLE MOISTURE DENSITY GAUGE SOURCE ROD OVER A 6-MONTH TIME PERIOD | | | | WHILE WORKING OUT OF THE LICENSEE'S BRISTOL, VIRGINIA, OFFICE AT LOCATIONS | | IN BOTH VIRGINIA AND TENNESSEE, A TECHNICIAN WAS DIRECTLY HANDLING THE | | SOURCE ROD OF A PORTABLE MOISTURE DENSITY GAUGE OVER A TIME PERIOD FROM MAY | | 1996 TO THE END OF OCTOBER 1996. DIRECT HANDLING OF THE SOURCE ROD | | OCCURRED WHEN THE INDIVIDUAL OPENED THE SHUTTER ON THE BOTTOM OF THE DEVICE | | AND POSITIONED OF THE ROD INTO THE HOLE FOR TESTING. THE MOISTURE DENSITY | | GAUGE WAS A CAMPBELL PACIFIC NUCLEAR DEVICE (MODEL NUMBER MC-1), AND IT | | CONTAINED A 10-MILLICURIE CESIUM-137 SEALED SOURCE. | | | | AT THIS TIME, THE INDIVIDUAL DOES NOT EXHIBIT ANY SIGNIFICANT PHYSICAL | | EFFECTS FROM THE DIRECT HANDLING OF THE SOURCE ROD, AND THE LICENSEE DOES | | NOT HAVE AN ACCURATE ESTIMATE OF THE EXPOSURE RECEIVED BY THE INDIVIDUAL. | | THE INDIVIDUAL WAS WEARING A WHOLE BODY DOSIMETER BUT BELIEVES THAT IT | | WOULD HAVE BEEN SHIELDED BY THE DEVICE. THE INDIVIDUAL WAS NOT WEARING AN | | EXTREMITY MONITORING DEVICE BECAUSE CONTACT WITH THE SOURCE ROD WAS NOT | | EXPECTED. THE LICENSEE BELIEVES THAT THE INDIVIDUAL PRIMARILY USED ONE | | HAND BUT MAY HAVE SWITCHED HANDS OCCASIONALLY. THE LICENSEE ALSO BELIEVES | | THAT THE INDIVIDUAL'S BODY WAS SHIELDED BY THE DEVICE AND ITS INTERNAL | | SHIELDING BASED UPON THE INDIVIDUAL'S DESCRIPTION. AN EXAMINATION AT A | | MEDICAL FACILITY NOTED A COUPLE OF EXTREMELY SUPERFICIAL BLISTERS ON THE | | INDIVIDUAL'S LEFT HAND. | | | | AN NRC REGION 2 INSPECTOR WAS ON SITE YESTERDAY AND WAS AWARE OF THIS | | EVENT. (REFER TO THE HOO LOG FOR LICENSEE CONTACT TELEPHONE NUMBERS.) | | | | * * * 1600 NOVEMBER 13, 1996, UPDATE BY TROCINE * * * | | | | A COMMISSIONERS' ASSISTANTS BRIEFING WAS CONDUCTED AT 1600 ON NOVEMBER 13, | | 1996, IN ORDER TO DISCUSS THE STATUS OF AN AUGMENTED INSPECTION TEAM THAT | | IS CURRENTLY ONSITE. THE BRIEFING NOTIFICATIONS WERE MADE (*INDICATES | | OFFICE DID NOT PARTICIPATE): AEOD (*), IRD (*), JACKSON (BOYLE AND MOORE), | | ROGERS (*), DICUS (LUBANAU), DIAZ (RADDATZ), McGAFFIGAN (SCHLUETER), EDO | | (SHAFFER), NMSS EO (COOL), R2DO (*), PAO (BEECHER), CAO (KEELING), SECY | | (BATES), STATE (BANGART), BRIEFER (HOSEY), AND OTHERS (COLLINS, COMBS, | | DECKER, MALLETT, AND PAPERIELLO). | | | | * * * 1630 NOVEMBER 15, 1996, UPDATE BY WEAVER * * * | | | | A COMMISSIONERS' ASSISTANTS BRIEFING WAS CONDUCTED AT 1630 ON NOVEMBER 15, | | 1996, THE PARTICIPANTS WERE BRIEFED ON THE INPSECTION TEAM'S PROGRESS. | | AEOD(*), IRD (*), JACKSON (BOYLE), ROGERS (COPLAN), DICUS (CHAN), DIAZ | | (RADDATZ), MCGAFFIGAN (SCHLUETER), NMSS (COOL), PAO (BEECHER), SP | | (BANGART), BRIEFER (HOSEY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31338 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 11/15/96 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 09:04 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/15/96 | +------------------------------------------------+EVENT TIME: 08:42[EST]| |NRC NOTIFIED BY: POPE |LAST UPDATE DATE: 11/15/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |URYC RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CHAFFEE EO | | |WRIGHT FEMA | | |BARRETT IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | PARTIAL LOSS OF CONTROL ROOM VISUAL AND AUDIBLE ANNUNCIATORS | | | | DURING PERFORMANCE OF MAINTENANCE ACTIVITIES, A SHORT CIRCUIT CAUSED A | | GROUND, WHICH RESULTED IN THE LOSS OF NUMEROUS CONTROL ROOM ANNUNCIATORS. | | THIS CONDITION DOES NOT AFFECT CONTROL PANEL INSTRUMENTATION AND | | INDICATION. THE LICENSEE HAS IMPLEMENTED COMPENSATORY ACTIONS, AND EXPECTS | | THE ANNUNCIATORS TO BE RESTORED WITHIN A FEW HOURS. THIS EVENT IS SIMILAR | | TO ONE THAT OCCURRED ON 10/25/96. THE NRC RESIDENT INSPECTOR HAS BEEN | | INFORMED BY THE LICENSEE. | | | | [HOO NOTE: SEE RELATED EN 31210] | | | | * * * UPDATE AT 1038 EST FROM POPE TAKEN BY KARSCH * * * | | AT 0955 EST THE LICENSEE REPLACED THE BURNED OUT FUSE IN THE ANNUNCIATOR | | POWER SUPPLY. THIS ACTION RESTORED ALL BUT ONE ANNUNCIATOR LIGHT BOX. THE | | DEENERGIZED LIGHT BOX, CONTAINING 31 ALARMS, IS THE ONE THEY WERE WORKING | | ON AT THE TIME OF THE SHORT CIRCUIT. IT WILL REMAIN DEENERGIZED UNTIL THE | | SHORT CIRCUIT IS REPAIRED. THE LICENSEE IS REMAINING IN THE UNUSUAL EVENT | | UNTIL ALL ANNUNCIATORS ARE RESTORED TO OPERABILITY. THE LICENSEE INFORMED | | THE NRC RESIDENT INSPECTOR. R2DO (URYC) NOTIFIED. | | | | * * * UPDATE 1116 11/15/96 FROM POPE TAKEN BY STRANSKY * * * | | | | UNUSUAL EVENT TERMINATED AT 1115, AFTER ALL ANNUNCIATORS WERE RESTORED. | | NOTIFIED R2DO (URYC), EO (CHAFFEE), FEMA (SWITZER). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31339 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/15/96 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 17:19 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/15/96 | +------------------------------------------------+EVENT TIME: 17:00[EST]| |NRC NOTIFIED BY: RICK BONNER |LAST UPDATE DATE: 11/15/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4160 VAC SWITCHGEAR INOPERABLE WHEN BREAKERS ARE "RACKED DOWN" | | | | THE 4160 VOLT SWITCHGEAR IS INOPERABLE WHEN THE BREAKERS ARE RACKED DOWN | | BECAUSE OF THE ABILITY OF THE BREAKERS TO DAMAGE RELAYS ON THE CABINET DOOR | | DURING A SEISMIC EVENT. THE AFFECTED BREAKERS HAVE BEEN EITHER REMOVED OR | | PARTIALLY ELEVATED. MILLSTONE UNITS 1 & 3 HAVE REPORTED SIMILAR EVENTS AS | | HAVE OTHER LICENSEES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL | | OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31340 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/15/96 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:26 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/15/96 | +------------------------------------------------+EVENT TIME: 18:05[EST]| |NRC NOTIFIED BY: JAMES BAUER |LAST UPDATE DATE: 11/15/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A POSTULATED EVENT COULD PREVENT SAFE SHUTDOWN DURING A TORNADO | | | | A TORNADO EVENT IS PRESUMED TO CAUSE A LOSS OF ALL AC POWER. THEREFORE THE | | SAFE SHUTDOWN CONDITION IS REACHED USING THE CITY WATER SYSTEM IN | | CONJUNCTION WITH THE ISOLATION CONDENSER. IF THE TORNADO RUPTURED THE | | CONDENSATE STORAGE TANK, IT WOULD FLOOD THE PUMP HOUSE, MAKING IT | | INACCESSIBLE. ACCESS TO THE PUMP HOUSE IS NECESSARY TO MAKE UP THE | | CONNECTIONS TO SUPPLY CITY WATER TO THE ISOLATION CONDENSER. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND STATE AND LOCAL | | GOVERNMENT OFFICIALS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31341 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/15/96 | |UNIT: [1] [ ] [ ] STATE: AR |NOTIFICATION TIME: 19:01 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 11/15/96 | +------------------------------------------------+EVENT TIME: 17:05[CST]| |NRC NOTIFIED BY: RICHARD ELLISON |LAST UPDATE DATE: 11/15/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 SAFETY PARAMETER DISPLAY SYSTEM (SPDS) FAILED AT 1705 CST. THE CAUSE | | OF THE FAILURE IS UNKNOWN, BUT I&C IS INVESTIGATING. THE PLANT WILL STAY | | AT 100% POWER WHILE SPDS IS REPAIRED. THE LICENSEE INFORMED THE NRC | | RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2130 ON 11/15/96 BY ELLISON TAKEN BY WEAVER * * * | | THE SPDS SYSTEM WAS REPAIRED AND RETURNED TO SERVICE AS 2005 CST. THE HOO | | NOTIFIED THE R4DO (YANDELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31342 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 11/16/96 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 02:13 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 11/16/96 | +------------------------------------------------+EVENT TIME: 00:31[EST]| |NRC NOTIFIED BY: EPPERSON |LAST UPDATE DATE: 11/16/96 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRUNO URYC 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 Y 36 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT WAS MANUALLY TRIPPED FROM 36% IN ANTICIPATION OF AN AUTOMATIC LOW | | STEAM GENERATOR LEVEL TRIP. | | | | THIS OCCURRED WHILE PERFORMING A CONTROLLED S/D FOR SCHEDULED MAINTENANCE. | | THE REACTOR WAS MANUALLY TRIPPED WHEN ALL THREE STRINGS OF INTERMEDIATE | | PRESSURE FEEDWATER HEATERS AUTOMATICALLY ISOLATED DUE TO HIGH-HIGH HEATER | | SHELL LEVELS. THESE FEEDWATER HEATERS ARE IN PARALLEL AND DO NOT HAVE A | | BYPASS PATH. WHEN THE HEATERS ISOLATED, THE MAIN FEEDWATER PUMPS LOST | | SUCTION SUPPLY AND AT THIS TIME THE REACTOR WAS MANUALLY TRIPPED, PRIOR TO | | RECEIVING AN AUTO TRIP ON LOW STEAM GENERATOR LEVEL. THE CAUSE OF THE | | HEATER LEVEL CONTROL DIFFICULTIES WILL BE INVESTIGATED. FOLLOWING THE | | REACTOR TRIP, RCS TEMPERATURE DROPPED BELOW 540øF(MIN OBSERVED TEMP WAS | | 530øF) WHICH NECESSITATED EMERGENCY BORATION AS DIRECTED BY THE EMERGENCY | | PROCEDURES UNTIL S/D MARGIN WAS VERIFIED TO BE ADEQUATE. RCS TEMPERATURE | | WAS RESTORED TO VALUES ABOVE 540øF BY MANUAL CONTROL OF THE AUX FEEDWATER | | SYSTEM, ALSO DIRECTED BY THE EMERGENCY PROCEDURES. ALL RODS FULLY | | INSERTED, NO SAFETY OR RELIEF VALVES LIFTED AND NO INJECTION OCCURRED. THE | | HEAT SINK IS THE S/G AND MAIN CONDENSER. | | | | THE RESIDENT WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31343 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/16/96 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:15 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 11/16/96 | +------------------------------------------------+EVENT TIME: 13:33[EST]| |NRC NOTIFIED BY: SCOTT CHUBON |LAST UPDATE DATE: 11/16/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - DRYWELL FLOOR AND EQUIPMENT DRAIN SUMP ISOLATED | | | | WHILE THE REACTOR WAS SHUTDOWN WITH THE FUEL REMOVED AND THE CRD SYSTEM | | SHUTDOWN FOR MAINTENANCE, AN INVALID RPS SCRAM AND ISOLATION SIGNAL WAS | | RECEIVED. THE SIGNAL WAS CAUSED BY AN I&C TECHNICIAN INADVERTENTLY OPENING | | A PRESSURE TRANSMITTER ISOLATION VALVE WHILE ATTEMPTING TO ADJUST THE | | VALVE'S PACKING. THIS CAUSED TWO REACTOR VESSEL LEVEL TRANSMITTERS TO | | SENSE A FALSE LOW LEVEL AND GENERATED THE ACTUATION SIGNAL. | | | | ALL VALVES HAVE BEEN RETURNED TO THEIR PRE-ACTUATION POSITIONS. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31344 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 11/17/96 | |UNIT: [ ] [2] [ ] STATE: AR |NOTIFICATION TIME: 01:03 [ET]| |RX TYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 11/16/96 | +------------------------------------------------+EVENT TIME: 20:04[CST]| |NRC NOTIFIED BY: RICHARD ELLISON |LAST UPDATE DATE: 11/17/96 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LARRY YANDELL RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 1 STARTUP | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFIED THE STATE OF ARKANSAS THAT WERE SHUTTING DOWN TO REPAIR A SMALL | | STEAM GENERATOR TUBE LEAK. | | | | THE FOLLOWING TEXT IS FROM A FACSIMILE SENT TO THE NRC OPERATION CENTER. | | | | "SMALL STEAM GENERATOR TUBE LEAK ON THE "B" STEAM GENERATOR INDICATED ON AN | | INSTALLED NITROGEN-16 RADIATION MONITOR APPROACHED A MANAGEMENT GUIDELINE | | OF 50gpd (GALLONS PER DAY) AT 1954 ON 11-16-96. ANO MANAGEMENT DIRECTED A | | REACTOR SHUTDOWN AND POWER REDUCTION COMMENCED AT 2004. REACTOR SHUTDOWN | | WAS COMPLETED AT 2201 11/16/96. A PLANT COOLDOWN WILL COMMENCE AT EARLIEST | | OPPORTUNITY." | | | | STEAM GENERATOR "B" TUBE LEAK HAD BEEN INCREASING SLOWLY THE LAST COUPLE OF | | DAYS BEFORE ARKANSAS NUCLEAR MANAGEMENT DIRECTED A REACTOR SHUTDOWN TO | | REPAIR THE STEAM GENERATOR TUBE LEAK. LICENSEE SAID THAT THEY WILL BE SHUT | | DOWN FOR 2 TO 3 WEEKS TO REPAIR THE STEAM GENERATOR TUBE LEAK. THE STATE OF | | ARKANSAS WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31345 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 11/17/96 | |UNIT: [ ] [2] [ ] STATE: MD |NOTIFICATION TIME: 11:58 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 11/17/96 | +------------------------------------------------+EVENT TIME: 10:59[EST]| |NRC NOTIFIED BY: BOB PACE |LAST UPDATE DATE: 11/17/96 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD BARKLEY RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR TRIP ON LOW STEAM GENERATOR LEVEL | | | | THE REACTOR TRIPPED ON LOW LEVEL IN THE #21 STEAM GENERATOR. A FAILURE IN | | THE MAIN FEEDWATER CONTROL SYSTEM CAUSED BOTH FEEDWATER PUMPS TO TRIP AND | | RESULTED IN THE LOW STEAM GENERATOR LEVEL. ALL CONTROL ELEMENT ASSEMBLIES | | FULLY INSERTED. STEAM IS BEING DUMPED TO THE MAIN CONDENSER AS NECESSARY | | TO REMOVE DECAY HEAT. BOTH THE STEAM DRIVEN AND THE MOTOR DRIVEN AUX FEED | | PUMPS STARTED AS EXPECTED. STEAM GENERATOR LEVELS ARE BEING RESTORED. | | | | THE #22 MAIN FEED PUMP TURBINE RESET ITSELF AFTER INITIALLY BEING TRIPPED. | | THE TURBINE COULD NOT BE TRIPPED FROM THE CONTROL ROOM AND REQUIRED | | OPERATORS TO MANUALLY SHUT OFF THE STEAM SUPPLY. THE TURBINE DID NOT REACH | | A HIGH ENOUGH SPEED TO ALLOW THE MAIN FEED PUMP TO INJECT WATER INTO THE | | STEAM GENERATOR. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+