U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/07/97 - 08/08/97 ** EVENT NUMBERS ** 32713 32729 32733 32734 32735 32736 32737 32738 32739 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32713 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/02/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:09 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:25[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/08/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |WAYNE KROPP RDO | | DOCKET: 0707001 |JOHN HICKEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAURER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT | | | | "ON 8/1/97 AT 1625 HOURS, THE C-333-A FACILITY AUTOCLAVE POSITION 4 NORTH | | STEAM CONTROLLER WAS DISCOVERED TO BE INOPERABLE DURING CYLINDER HEELING | | OPERATIONS (MODE 5), TSR LCO 2.2.3.3 REQUIRES THE AUTOCLAVE STEAM PRESSURE | | CONTROL SYSTEM TO BE OPERABLE WHEN THE AUTOCLAVE IS IN MODE 5. THE | | AUTOCLAVE WAS DECLARED INOPERABLE AND REMOVED FROM SERVICE AT 1631 HOURS. | | TROUBLESHOOTING AND A SYSTEM ENGINEERING EVALUATION OF THE FAILURE HAVE | | BEEN INITIATED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE AT 0007 ON 08/08/97 BY MIKE UNDERWOOD TAKEN BY JOLLIFFE * * * | | | | A LICENSEE ENGINEERING EVALUATION DETERMINED THAT THE STEAM CONTROLLER IS | | NOT WITHIN THE SAFETY SYSTEM BOUNDARY AND WAS NOT REQUIRED TO BE OPERABLE | | BY THE TECHNICAL SAFETY REQUIREMENT. ADDITIONALLY, THE AUTOCLAVES SAFETY | | SYSTEMS TESTS WERE PERFORMED IN THE "AS-FOUND CONDITION" AND DEMONSTRATED | | THAT THE FAILED STEAM CONTROLLER HAD NO EFFECT ON THE SAFETY SYSTEM TO | | FUNCTION AS DESIGNED. | | | | THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO MONTE PHILLIPS AND THE NMSS EO | | JOHN GREEVES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32729 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 08/06/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 12:03 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/06/97 | +------------------------------------------------+EVENT TIME: 11:24[EDT]| |NRC NOTIFIED BY: PETER ABBOTT |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 +------------------------------------------------------------------------------+ | THE PLANT ENTERED A TECH SPEC REQUIRED SHUTDOWN LCO AFTER DECLARING | | BOTH TRAINS OF THE STANDBY GAS TREATMENT SYSTEM INOPERABLE FOLLOWING | | SURVEILLANCE TESTING. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THE PLANT HAS ENTERED A 24-HOUR LCO TO COLD CONDITION DUE TO 'A' AND 'B' | | STANDBY GAS TREATMENT SYSTEMS HAVING BEEN DECLARED INOPERABLE DUE TO THE | | INABILITY TO ACHIEVE DESIGN FLOW RATE WITH EITHER SYSTEM. DESIGN FLOW IS | | 6,000 STANDARD CUBIC FEET PER MINUTE (SCFM). MAXIMUM ACHIEVABLE CURRENTLY | | IS 4,000 SCFM [LCO 97-0590]. THIS CONDITION MAY BE AS A RESULT OF WATER | | ACCUMULATION IN THE DISCHARGE PIPING." | | | | THE LICENSEE IS ATTEMPTING TO CLEAR THE DRAIN LINE AND RESTORE AT LEAST ONE | | TRAIN OF THE STANDBY GAS TREATMENT SYSTEM TO SERVICE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0120 ON 08/07/97 BY PETER ABBOTT ENTERED BY JOLLIFFE * * * | | | | AT 0030 ON 08/07/97, THE LICENSEE DECLARED BOTH TRAINS OF THE STANDBY GAS | | TREATMENT SYSTEM OPERABLE AND EXITED TECH SPEC LCO SHUTDOWN A/S #3.7.B.3. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO RICH CONTE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32733 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/06/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 20:06 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/06/97 | +------------------------------------------------+EVENT TIME: 19:45[EDT]| |NRC NOTIFIED BY: DENIS CORNAX |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 | 97 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO QUESTIONABLE PRESSURIZER | | SAFETY VALVE SETTINGS | | | | AT 1945, THE LICENSEE COMMENCED A TECHNICAL SPECIFICATION 3.0.1 REQUIRED | | SHUTDOWN DUE TO THE FACT THAT ONE OR MORE PRESSURIZER SAFETY VALVE SETTINGS | | MAY BE OUTSIDE THE ñ1% ALLOWABLE LIMIT. THE PRESSURIZER SAFETY VALVES ARE | | SET IN ACCORDANCE WITH SECTION XI CODE REQUIREMENTS USING MEASURED AMBIENT | | TEMPERATURE. READINGS TAKEN TODAY CONFIRM THAT THE VALVE BODY/BONNET | | TEMPERATURES ARE SIGNIFICANTLY DIFFERENT THAN THE AMBIENT TEMPERATURES USED | | TO SET THE VALVES. THEREFORE, ONE OR MORE VALVES MAY HAVE SETPOINTS LOWER | | THAN 2,485 PSIG ñ1% ALLOWABLE PER THE TECHNICAL SPECIFICATIONS. (UNIT 2 | | NORMALLY OPERATES WITH THE BLOCK VALVES CLOSED. THEY HAVE AN AUTOMATIC | | OPEN SIGNAL.) | | | | THE LICENSEE PLANS TO PLACE UNIT 2 IN A COLD SHUTDOWN MODE AND DEPRESSURIZE | | UNIT 2 IN ORDER TO PERMIT THE VALVES TO BE RESET ACCORDING TO THE RECENT | | TEMPERATURE READINGS. THIS ISSUE AFFECTS UNIT 2 ONLY BECAUSE UNIT 3 IS | | CURRENTLY IN COLD SHUTDOWN MODE IN A REFUELING OUTAGE. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0340 ON 08/07/97 BY MIKE RUH ENTERED BY JOLLIFFE * * * | | | | AT 0200 ON 08/07/97, UNIT 2 ENTERED MODE 4 (HOT SHUTDOWN). THE LICENSEE | | WILL BE RESETTING THE THREE PRESSURIZER SAFETY VALVES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO RICH CONTE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32734 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/07/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 06:43 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/07/97 | +------------------------------------------------+EVENT TIME: 03:34[EDT]| |NRC NOTIFIED BY: DEVON PRICE |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 87 POWER OPERATION | 87 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SACS PUMP AUTO STARTED DUE TO CLOSURE OF A SACS-TO-TACS ISOLATION VALVE - | | | | AT 0334, THE 'C' SAFETY AUXILIARIES COOLING SYSTEM (SACS) PUMP AUTO STARTED | | IN RESPONSE TO A LOW FLOW SIGNAL TO THE TURBINE AUXILIARIES COOLING SYSTEM | | (TACS). THE LOW FLOW SIGNAL TO THE TACS WAS CAUSED BY A SPURIOUS CLOSURE | | OF THE 'B' SACS-TO-TACS ISOLATION VALVE FOR UNKNOWN REASONS. THE LOW FLOW | | SIGNAL TO THE TACS ALSO CAUSED THE INITIATION OF AN AUTOMATIC TACS TRANSFER | | TO THE 'A' SACS LOOP. | | | | THIS REPORT IS BEING MADE BECAUSE A SACS PUMP AUTO START DUE TO A LOW FLOW | | SIGNAL TO THE TACS IS LISTED IN THE UFSAR AS AN ESSENTIAL AUXILIARY SUPPORT | | SYSTEM ACTUATION SIGNAL. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THE VALVE CLOSURE. | | | | THE LICENSEE WILL INFORM LOCAL GOVERNMENT OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32735 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/07/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 09:38 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/07/97 | +------------------------------------------------+EVENT TIME: 08:55[EDT]| |NRC NOTIFIED BY: MIKE EMPEY |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 SBGT SYSTEM OVERPRESSURE DUE TO A LOCA WHILE INERTING AT POWER- | | | | FOLLOWING A RECENT MAINTENANCE OUTAGE, THE PLANT WAS STARTED UP AND | | INERTED AT POWER WITHOUT ADEQUATE RESOLUTION OF THE CONCERN FOR | | STANDBY GAS TREATMENT (SBGT) SYSTEM OVERPRESSURIZATION DUE TO A | | POSTULATED LOCA COINCIDENT WITH INERTING AT POWER. | | | | THE LICENSEE HAS IMPLEMENTED ADMINISTRATIVE CONTROLS TO PREVENT OPENING | | THE INERTING/DEINERTING PATHS UNTIL THE CONCERNS HAVE BEEN RESOLVED. | | | | THE LICENSEE IS DETERMINING LONG TERM CORRECTIVE ACTIONS. | | | | THE LICENSEE IS RESOLVING THIS CONCERN AS A FOLLOWUP TO AN OPERATING | | EXPERIENCE REVIEW CONCERN AT LA SALLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32736 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 08/07/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 10:53 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/07/97 | +------------------------------------------------+EVENT TIME: 09:47[EDT]| |NRC NOTIFIED BY: ROY BROWN |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |AL CHAFFEE, NRR EO | |NOCM COMM ASST BRIEF |STINEDURF FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UE DECLARED DUE TO CONTROL ROOM EVACUATION DUE TO HALON DISCHARGE - | | | | AT 0947, THE HALON SYSTEM IN THE CONTROL ROOM INADVERTENTLY DISCHARGED | | WHEN A FLASH CAMERA PICTURE OF THE OPEN HALON CONTROL PANEL WAS TAKEN. | | THE LICENSEE EVACUATED THE CONTROL ROOM AS A PRECAUTION. | | | | AT 1034, THE LICENSEE REMANNED THE CONTROL ROOM. | | | | AT 1045, THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO THE PRECAUTIONARY | | EVACUATION OF THE CONTROL ROOM. THERE WERE NO INJURIES OR ADVERSE AFFECTS | | TO PLANT PERSONNEL. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR OF THE DECLARATION OF THE UNUSUAL EVENT AND PLANS TO ISSUE A | | PRESS RELEASE. | | | | * * * UPDATE AT 1304 BY PIONTKOWSKI ENTERED BY GOULD * * * | | THE UNUSUAL EVENT WAS TERMINATED AT 1235. THE LICENSEE NOTIFIED STATE | | AND LOCAL OFFICIALS AND THE NRC RESIDENT INSPECTOR OF THE TERMINATION OF | | THE UNUSUAL EVENT. THE NRC OPERATIONS OFFICER NOTIFIED R1DO (RICH CONTE), | | NRR EO (BOB DENNIG) AND FEMA (STINEDRUF). | | | | * * * AT 1500, A COMMISSIONERS ASSISTANTS BRIEFING WAS HELD * * * | | PERTICIPANTS INCLUDED IRD (ROSSI, GIITTER, HASSELBERG), NRR EO (CHAFFEE), | | NMSS EO (COMBS), PAO (DRICKS), SP (LOHAUS), IP (FAULKNER), CA (CALLAHAN), | | EDO (SKEEN), SECY (BATES), PD (WEISS), PM (FAIRTILE), CHAIRMAN JACKSON | | (HUBER), COMMISSION MCGAFFIGAN (JACKSON), COMMISSIONER DIAZ (HSIA) AND | | COMMISSIONER DICUS (CHAN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32737 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 08/07/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 19:26 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/07/97 | +------------------------------------------------+EVENT TIME: 14:25[EDT]| |NRC NOTIFIED BY: KEARNEY |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THAT THE PLANT HAS HAD TWO TRANSIENTS DURING PAST | | REACTOR SCRAM EVENTS WHERE THE PLANT EXCEEDED THE 100øF/HR COOLDOWN/HEATUP | | RATE LIMIT, WHICH IS A TECH SPEC VIOLATION. | | | | BASED ON THE PHENOMENA OCCURRING IN EVENT #31549 ON 01/07/97, A REVIEW OF | | ALL PREVIOUS REACTOR SCRAM EVENTS WAS MADE AND ONLY THE FOLLOWING TWO WERE | | FOUND TO EXCEED THE COOLDOWN/HEATUP RATE LIMIT. | | | | EVENT #24205 ON 09/10/92 - THE REACTOR VESSEL BOTTOM HEAD DRAIN EXPERIENCED | | A COOLDOWN RATE OF APPROXIMATELY 245øF IN ONE HOUR (APPROXIMATELY 520 TO | | 275øF). (THE INPUT SIGNAL IS FROM A TEMPERATURE ELEMENT IN THE REACTOR | | WATER CLEANUP LINE.) ABOUT ONE HOUR LATER, THE BOTTOM HEAD DRAIN STARTED | | TO HEAT UP AT A RATE OF APPROXIMATELY 235øF IN ONE HOUR (265 TO 500øF). | | | | AT THE SAME TIME, THE REACTOR VESSEL BOTTOM HEAD COOLED DOWN AT A RATE OF | | APPROXIMATELY 110øF IN ONE HOUR (APPROXIMATELY 405 TO 295øF). (THE INPUT | | SIGNAL IS FROM A TEMPERATURE ELEMENT MAGNETICALLY ATTACHED TO THE OUTER | | SKIN OF THE REACTOR VESSEL BOTTOM HEAD.) THE BOTTOM HEAD HEATED UP AT | | APPROXIMATELY THE SAME TIME AS THE BOTTOM HEAD DRAIN, BUT AT AN ACCEPTABLE | | RATE (<100øF/HR). THE BOTTOM HEAD AND BOTTOM HEAD DRAIN DID NOT GO BELOW | | 245øF DURING THIS EVENT. THE "A" AND "B" RECIRCULATION LOOPS WERE | | MAINTAINED WITHIN ACCEPTABLE COOLDOWN/HEATUP RATE LIMITS. | | | | EVENT #25316 ON 03/26/93 - THE REACTOR VESSEL BOTTOM HEAD DRAIN EXPERIENCED | | A COOLDOWN RATE OF APPROXIMATELY 220øF IN ONE HOUR (530 TO 310øF). THIS | | WAS FOLLOWED BY A HEATUP RATE OF APPROXIMATELY 140øF IN 20 MINUTES | | (310 TO 450øF). THE BOTTOM HEAD DRAIN DID NOT GO BELOW 300øF DURING THE | | INITIAL TRANSIENT. THE BOTTOM HEAD AND "A" AND "B" RECIRC LOOPS REMAINED | | WITHIN ACCEPTABLE COOLDOWN/HEATUP RATE LIMITS. | | | | NEITHER EVENT VIOLATED THE PERRY TECH SPEC REACTOR VESSEL PRESSURE VERSUS | | METAL TEMPERATURE CURVE. | | | | WHEN THESE EVENTS OCCURRED, COOLDOWN/HEATUP RATE LIMITS OF THE REACTOR | | VESSEL BOTTOM HEAD REGION WERE NOT REQUIRED TO BE MONITORED PER | | SURVEILLANCE PROCEDURE #SVI-B21-1176. THEREFORE, THESE CONDITIONS WERE | | NOT IDENTIFIED AT THAT TIME. SINCE THE 01/7/97 EVENT (#31549), THE | | LICENSEE HAS CHANGED THE SURVEILLANCE PROCEDURES TO INCLUDE THE MONITORING | | OF THESE POINTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32738 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 08/07/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 21:44 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/07/97 | +------------------------------------------------+EVENT TIME: 19:15[EDT]| |NRC NOTIFIED BY: ROLAND |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 2 DECLARED HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM INOPERABLE. | | | | THIS WAS DETERMINED WHILE PERFORMING A WEEKLY TEST OF THE HPCI AUXILIARY | | OIL SYSTEM WHEN AN UNUSUAL VALVE RESPONSE WAS NOTED. APPROXIMATELY | | 9 SECONDS INTO THE TEST, THE TURBINE STOP VALVE CLOSED UNEXPECTEDLY. THE | | SYSTEM RESET ITSELF WITHIN 5 SECONDS AND RESPONDED CORRECTLY THEREAFTER. | | THIS CONDITION HAS BEEN EXPERIENCED IN THE PAST WITH UNIT 2 HPCI SYSTEM | | AND WAS THOUGHT TO BE CORRECTED BY PREVIOUS MAINTENANCE ACTIVITIES AND | | SUCCESSFUL TESTS. THE RESPONSE WAS PREVIOUSLY EVALUATED AS NOT IMPACTING | | SYSTEM OPERABILITY SINCE THE STOP AND CONTROL VALVE REACHED THE FULL OPEN | | POSITION IN LESS THAN THE REQUIRED 30 SECONDS. | | | | ADDITIONAL INFORMATION, NOT CONSIDERED IN PREVIOUS EVALUATIONS, DETERMINED | | THAT THE HPCI SYSTEM MAY NOT BE ABLE TO ACHIEVE FULL FLOW INJECTION WITHIN | | 30 SECONDS OF AN ACTUAL INITIATION SIGNAL. LOGIC INTERLOCKS ASSOCIATED | | WITH THE HPCI INJECTION VALVE AND THE TURBINE STOP VALVE REVEALED THAT | | THERE IS THE POTENTIAL FOR THE INJECTION VALVE TO RECEIVE A CLOSE SIGNAL | | AFTER IT HAS STROKED OPEN ON A SYSTEM INITIATION. ONCE THE INJECTION VALVE | | STROKED CLOSED, THE LOGIC WOULD REOPEN IT. HOWEVER, THIS ADDITIONAL STROKE | | WOULD DELAY THE RESPONSE TIME OF THE HPCI SYSTEM SO THAT IT WOULD NOT | | ACHIEVE FULL INJECTION FLOW UNTIL APPROXIMATELY 36 SECONDS AFTER | | INITIATION. | | | | WITH THE HPCI SYSTEM INOPERABLE, UNIT 2 ENTERED AN LCO ACTION STATEMENT TO | | INSURE OPERABILITY OF THE REMAINING ECCS SYSTEMS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32739 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 08/07/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 22:32 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/07/97 | +------------------------------------------------+EVENT TIME: 20:18[EDT]| |NRC NOTIFIED BY: TURNER |LAST UPDATE DATE: 08/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 HAD AN AUTO REACTOR TRIP FROM 100% POWER DUE TO A TURBINE TRIP. | | | | THE CAUSE OF THE TURBINE TRIP RESULTING IN THE REACTOR TRIP WAS DUE TO A | | TWO OUT OF THREE HI-HI STEAM GENERATOR LEVEL SIGNAL ON THE "A" STEAM | | GENERATOR. THIS WAS ASSOCIATED WITH THE MAIN FEEDWATER REGULATING VALVE | | FAILING OPEN. THE CAUSE IS BEING INVESTIGATED, BUT MAINTENANCE ACTIVITIES | | WERE IN PROGRESS ON THE "A" STEAM GENERATOR LEVEL CONTROL LOOP AT THE TIME. | | ALL RODS FULLY INSERTED, NO ECCS INJECTION OCCURRED AND NO PRIMARY OR | | SECONDARY SAFETY VALVES LIFTED. | | | | BOTH EMERGENCY DIESEL GENERATORS (EDGs) STARTED BUT DID NOT CLOSE THEIR | | OUTPUT BREAKERS AND LOAD, SINCE THE 4KV BUSES TRANSFERRED TO OFFSITE POWER | | WITHOUT THE LOSS OF ANY 4KV BUS. ALL THREE AUXILIARY FEEDWATER PUMPS | | STARTED AS REQUIRED AND SUPPLIED FEEDWATER TO THE STEAM GENERATORS. THE | | LICENSEE IS INVESTIGATING THE CAUSE FOR THE EDGs AUTO START. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+