U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/06/97 - 08/07/97 ** EVENT NUMBERS ** 32588 32610 32635 32723 32726 32729 32730 32731 32732 32733 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32588 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 07/03/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 19:21 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 07/03/97 | +------------------------------------------------+EVENT TIME: 15:57[CDT]| |NRC NOTIFIED BY: RICK PARLATO |LAST UPDATE DATE: 08/06/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MELVYN LEACH RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED ADDITIONAL SECTIONS OF PIPING SUBJECT TO THERMALLY | | INDUCED OVERPRESSURIZATION DURING FOLLOWUP REVIEW TO NRC GENERIC LETTER | | 96-06. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "FOLLOWUP REVIEWS, DUE TO [LICENSEE EVENT REPORT] 266/97-018-00, IDENTIFIED | | SEVERAL ISOLATED PIPE SECTIONS INSIDE CONTAINMENT THAT MAY OVER PRESSURIZE | | DUE TO HEATING IN A POST-ACCIDENT ENVIRONMENT. THESE SECTIONS ARE [AS | | FOLLOWS]: | | | | 1. DEMINERALIZED WATER FROM CHECK VALVES 1(2)-529 | | 2. DEMINERALIZED WATER FROM ISOLATION VALVES 1(2)-11 | | 3. STEAM GENERATOR PRIMARY SIDE HOT AND COLD LEG VENTS | | 4. REACTOR VESSEL LEVEL INDICATION SYSTEM - 5 SECTIONS/UNIT | | 5. [SAFETY INJECTION] ACCUMULATOR LOCAL SAMPLE LINES (UNIT 1 AND 2) | | 6. [REACTOR COOLANT PUMP] #1 SEAL BYPASS LINE (UNIT 1 AND 2) | | 7. EXCESS LETDOWN LINE (UNIT 1 AND 2) | | 8. REFUELING CAVITY DRAIN LINE (UNIT 1 AND 2)." | | | | THE LICENSEE IDENTIFIED THAT CORRECTIVE ACTIONS ARE TO BE DETERMINED. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 1701 AUGUST 6, 1997, UPDATE FROM RICK WOOD RECEIVED BY TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BECAUSE FURTHER REVIEW | | OF THE CONDITIONS DESCRIBED IN THE NOTIFICATION LED TO THE CONCLUSION THAT | | THE CONSEQUENCES OF ANY OF THE POSTULATED PIPE OR VALVE FAILURES WOULD NOT | | HAVE PREVENTED THE FULFILLMENT OF SAFETY FUNCTIONS NECESSARY TO MITIGATE | | THE CONSEQUENCES OF AN ACCIDENT. IN ALL CASES, ADDITIONAL FAILURES | | BEYOND THOSE DESCRIBED BY THE OVER PRESSURE CONDITIONS WOULD HAVE TO OCCUR | | BEFORE THE ACCIDENT MITIGATING FUNCTIONS WERE SIGNIFICANTLY CHALLENGED. | | THEREFORE, THE CONDITIONS ALONE COULD NOT HAVE PREVENTED THE FULFILLMENT | | OF THE SAFETY FUNCTIONS DURING AN ACCIDENT. THE CONDITIONS REPORTED IN | | THIS EVENT NOTIFICATION ARE BEING EVALUATED AND REMEDIED AS PART OF THE | | LICENSEE'S CORRECTIVE ACTION PROCESS. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R3DO (PHIL HARRELL). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32610 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 07/11/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:24 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 07/10/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/06/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JEFF WRIGHT RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: MATT MAURER | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PADUCAH IS MAKING A 24-HOUR NON-CFR REPORT OF AN AUTOMATIC ACTUATION OF A | | "Q" SAFETY SYSTEM. | | | | THE LIQUID HANDLING CRANE HOIST BRAKE (WHICH IS "Q" CLASS SAFETY EQUIPMENT) | | AUTOMATICALLY ACTUATED WHEN THE HOIST MOTOR FOR THE LIQUID HANDLING CRANE | | (WHICH IS "Q" CLASS SAFETY EQUIPMENT) STOPPED FOR UNKNOWN REASONS. | | | | AT 1630 CDT ON 07/10/97, THE HOIST MOTOR ON THE C-360 BUILDING WEST CRANE | | FAILED WHILE MOVING HEELED CYLINDER #UK-2009 FOLLOWING A CYLINDER VALVE | | CHANGE. AS PER THE CRANE DESIGN, THE HOIST BRAKES CLOSED AND SUSPENDED THE | | LOAD APPROXIMATELY SIX FEET OFF THE GROUND. AFTER THE CRANE WAS IDLE FOR | | APPROXIMATELY ONE HOUR, THE ABILITY TO RAISE AND LOWER THE HOIST WAS | | RESTORED. THE CYLINDER WAS LOWERED INTO A CYLINDER STORAGE CRADLE. THE | | CRANE WAS REMOVED FROM SERVICE PENDING AN ENGINEERING INVESTIGATION. | | | | THE LICENSEE CATEGORIZED THIS EVENT NOTIFICATION ACCORDING TO PROCEDURE | | UE2-RA-RE1030, CRITERIA J2. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY PADUCAH. | | | | * * * 1522 AUGUST 6, 1997, UPDATE FROM HALICKS RECEIVED BY TROCINE * * * | | | | PADUCAH IS RETRACTING THIS EVENT NOTIFICATION BASED UPON A REVIEW OF | | THE SAFETY SYSTEM ACTUATION REPORTING CRITERIA. WHILE THE OPERATOR WAS | | POSITIONING THE CYLINDER OVER A CYLINDER CRADLE, HE RELEASED THE UP/DOWN | | TOGGLE SWITCH TO STOP THE CRANE HOIST MOVEMENT AND MOVED THE CRANE EAST A | | FEW INCHES. WHEN HE MOVED THE TOGGLE SWITCH FOR THE DOWN MOVEMENT, THE | | LOAD DID NOT MOVE. IT WOULD NOT MOVE IN EITHER THE DOWN OR UP DIRECTION. | | THE CRANE HOIST BRAKES (THE SAFETY SYSTEM COMPONENT) WERE ALREADY CLOSED | | (HOLDING THE LOAD) WHEN AN ELECTRICAL FAULT OCCURRED. THE SAFETY FUNCTION | | HAD ALREADY BEEN PROVIDED AND PADUCAH BELIEVES THAT NO AUTOMATIC ACTUATION | | OF THE BRAKES OCCURRED. | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS OFFICER | | NOTIFIED THE R3DO (MONTE PHILLIPS) AND NMSS EO (LARRY CAMPER). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32635 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 07/16/97 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 01:08 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 07/15/97 | +------------------------------------------------+EVENT TIME: 22:57[EDT]| |NRC NOTIFIED BY: FREDERICK SMITH |LAST UPDATE DATE: 08/06/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ESF ACTUATION - HPCS SUCTION SWAP ANNUNCIATOR | | | | THE LICENSEE PLACED THE CONTAINMENT AND DRYWELL VENTILATION SYSTEM IN | | SERVICE AS PART OF THE PROCEDURE FOR PUMPING DOWN THE REACTOR WATER CLEANUP | | BACKWASH RECEIVING TANK TO RADWASTE. THE VENTILATION SYSTEM DEVELOPED A | | DIFFERENTIAL PRESSURE BETWEEN THE DRYWELL AND CONTAINMENT, WITH THE DRYWELL | | HAVING THE HIGHER PRESSURE. THIS D/P CAUSED A RISE IN SUPPRESSION POOL | | LEVEL SUFFICIENT TO ACTUATE THE HIGH PRESSURE CORE SPRAY (HPCS) SUCTION | | SWAP ANNUNCIATOR. HOWEVER, SINCE HPCS SUCTION HAD BEEN ALIGNED TO THE | | SUPPRESSION POOL PRIOR TO THIS EVENT, NO VALVES REPOSITIONED BECAUSE OF THE | | HIGH SUPPRESSION POOL LEVEL. | | | | THE LICENSEE IS IN THE PROCESS OF LOWERING SUPPRESSION POOL LEVEL TO CLEAR | | THE ALARM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1003 ON 08/06/97 FROM FARBER KEARNEY TAKEN BY JOLLIFFE * * | | | | THE LICENSEE DETERMINED THAT THE ABOVE ACTUATION RESULTED FROM AND WAS | | PART OF A PREPLANNED SEQUENCE DURING TESTING OR REACTOR OPERATION AND, | | THEREFORE, DESIRES TO RETRACT THIS EVENT NOTIFICATION. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R3DO MONTE PHILLIPS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32723 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 08/05/97 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 13:06 [ET]| |RX TYPE: [1] CE |EVENT DATE: 08/05/97 | +------------------------------------------------+EVENT TIME: 10:42[CDT]| |NRC NOTIFIED BY: LARRY LEES |LAST UPDATE DATE: 08/06/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | CONTAMINATED INJURED INDIVIDUAL TRANSPORTED TO AN OFFSITE MEDICAL FACILITY | | | | DURING THE DECONTAMINATION OF A REACTOR COOLANT PUMP SEAL WHICH WAS | | INTENDED FOR FUTURE USE, THE SEAL SHIFTED AND SMASHED THE MIDDLE FINGER OF | | AN INDIVIDUAL'S RIGHT HAND. A SURVEY CONDUCTED BY A RADIATION PROTECTION | | TECHNICIAN IDENTIFIED 4,000 DISINTEGRATIONS PER MINUTE ABOVE BACKGROUND ON | | THE AFFECTED FINGER, AND THERE WAS NO OTHER CONTAMINATION IDENTIFIED ON THE | | INDIVIDUAL'S BODY. | | | | AT 1042 CDT, AN AUXILIARY BUILDING OPERATOR NOTIFIED THE CONTROL ROOM THAT | | THERE WAS AN INJURED CONTAMINATED INDIVIDUAL IN THE HEALTH PHYSICS COUNT | | ROOM. EMERGENCY MEDICAL TECHNICIANS WERE SUMMONED, AND 911 WAS CALLED. AT | | 1053 CDT, THE NRC RESIDENT INSPECTOR AND THE UNIVERSITY OF NEBRASKA MEDICAL | | CENTER WERE NOTIFIED THAT THE INJURED INDIVIDUAL WOULD BE TRANSPORTED TO | | THE UNIVERSITY OF NEBRASKA MEDICAL CENTER. BLAIR RESCUE (AN AMBULANCE | | SERVICE) TRANSPORTED THE INDIVIDUAL OFFSITE AT 1058 CDT, AND THE UNIVERSITY | | OF NEBRASKA MEDICAL CENTER WAS GIVEN THE INDIVIDUAL'S VITAL SIGNS AT 1059 | | CDT. AT THAT TIME, THE INDIVIDUAL WAS STABLE, ALERT, AND CONSCIOUS. | | | | * * * 1419 EDT AUGUST 6, 1997, UPDATE FROM MATZKE RECEIVED BY TROCINE * * * | | | | THE LICENSEE PROVIDED THE FOLLOWING CORRECTION TO THE INITIAL EVENT | | NOTIFICATION: THE CONTAMINATION WAS LOCATED ON THE TIP OF THE AFFECTED | | FINGER, AND IT WAS IDENTIFIED TO BE 4,000 DISINTEGRATIONS PER MINUTE | | (OR 400 COUNTS PER MINUTE) IN LIEU OF 4,000 COUNTS PER SECOND. THE | | INDIVIDUAL'S FINGER WAS DECONTAMINATED AT THE MEDICAL CENTER. THE LICENSEE | | PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS OFFICER | | NOTIFIED THE R4DO (PHIL HARRELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32726 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 08/05/97 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 15:02 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/05/97 | +------------------------------------------------+EVENT TIME: 13:14[EDT]| |NRC NOTIFIED BY: JOHN THOMAS |LAST UPDATE DATE: 08/06/97 | |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 | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 COMMENCED A TECH SPEC REQUIRED SHUTDOWN DUE TO TWO OF FOUR REFUELING | | WATER STORAGE TANK (RWST) LEVEL TRANSMITTERS BEING OUT-OF-SERVICE. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 1036, ONE OF FOUR RWST LEVEL TRANSMITTERS (#LT-QS-100C) WAS REMOVED | | FROM SERVICE FOR SCHEDULED MAINTENANCE. AT 1314, A SECOND RWST LEVEL | | CHANNEL (#LT-QS-100B) WENT OFFSCALE HIGH. THE CAUSE OF THE SECOND CHANNEL | | FAILURE IS BEING INVESTIGATED. THE CURRENT STATUS OF THE RWST LEVEL | | TRANSMITTERS (TWO OF FOUR OUT OF SERVICE) IS NOT PERMITTED BY TECH SPEC | | 3.3.2.1, AND TECH SPEC 3.0.3 WAS APPLIED AS OF 1314. AT 1412, A POWER | | REDUCTION WAS INITIATED TO COMPLY WITH TECH SPEC 3.0.3. POWER IS CURRENTLY | | STABLE AT 99% AND RESTORATION OF AT LEAST ONE OF THE TWO OUT-OF-SERVICE | | LEVEL TRANSMITTERS IS EXPECTED WITHIN THE SHUTDOWN ACTION TIME LIMIT OF | | TECH SPEC 3.0.3 [6 HOURS]." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0318 ON 08/06/97 FROM KINEST ENTERED BY JOLLIFFE * * * | | | | AT 1541 ON 08/05/97, THE LICENSEE RESTORED THE #LT-QS-100C RWST LEVEL | | TRANSMITTER TO OPERABLE STATUS AND EXITED TECH SPEC LCO A/S 3.0.3. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO RICH CONTE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32730 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: LUCENT TECHNOLOGIES, INC. |NOTIFICATION DATE: 08/06/97 | | CITY: MESQUITE REGION: 4 |NOTIFICATION TIME: 14:09 [ET]| | COUNTY: STATE: TX |EVENT DATE: 07/31/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 00:00[CDT]| | DOCKET: |LAST UPDATE DATE: 08/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RICHARD CONTE/R4 RDO | | | | +------------------------------------------------+CHRIS CHRISTENSEN/R2 RDO | |NRC NOTIFIED BY: THOMAS A. HUGHES |VERN HODGE/NRR RVIB | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT REGARDING HARNESS/POSITIVE PLATE LUG DISCONNECT ON | | THE LIST-1SH ROUND CELL BATTERY | | | | LUCENT TECHNOLOGIES, INC., SUBMITTED AN EVALUATION REPORT OF ITS | | INVESTIGATION ON THE HARNESS/POSITIVE PLATE LUG DISCONNECT ON THE LIST-1SH | | ROUND CELL BATTERY. THE REPORT CONCLUDED THAT A SUBSTANTIAL SAFETY HAZARD | | AS DEFINED IN 10 CFR PART 21 DOES NOT EXIST. | | | | ON MARCH 3, 1997, A REPORT OF DISCOVERY WAS ISSUED REGARDING A HIGH GRAVITY | | ROUND CELL WHICH FAILED A DISCHARGE TEST BY GOING INTO REVERSAL IMMEDIATELY | | FOLLOWING THE START OF THE DISCHARGE. THE TEST WAS PERFORMED AT THE C&D | | TECHNICAL CENTER IN CONSHOHOCKEN, PENNSYLVANIA, ON FEBRUARY 12, 1997, AS | | PART OF A CYCLING TEST PROGRAM TO EXAMINE SPECIFIC CYCLING CHARACTERISTICS | | OF NEW AND AGED CELLS. THIS CELL HAD BEEN MANUFACTURED IN MAY OF 1991, AND | | IT HAD BEEN IN A SPARE BATTERY AT McGUIRE SINCE 1991. THE SPARE BATTERY | | HAD BEEN SUBJECTED TO THE SAME TESTS AS THE IN-SERVICE BATTERY USING | | RELATIVELY HIGH DISCHARGE CURRENTS. DURING THIS TESTING (PRIOR TO SHIPPING | | TO CONSHOHOCKEN), THE CELL DID NOT SHOW ANY REDUCED PERFORMANCE COMPARED TO | | OTHER CELLS. THE DISCONNECT OF THE HARNESS AND POSITIVE PLATE LUGS IN THIS | | CELL WAS THE FIRST REPORTED INCIDENT IN THE 25-YEAR MANUFACTURING HISTORY | | OF APPROXIMATELY 800,000 CELLS. | | | | A FINAL REPORT OF INVESTIGATION DATED JULY 31, 1997, DOCUMENTED LUCENT | | TECHNOLOGIES, INC.'S, CONCLUSION THAT THE OBSERVED DISCONNECT OF THE | | HARNESS FROM THE TOP POSITIVE PLATE LUGS IN THE CELL RESULTED FROM A | | COMBINATION OF WELDS WITH REDUCED PENETRATION DEPTH, EXTENSIVE MECHANICAL | | STRESS DURING SHIPPING, AND EXCESSIVE HANDLING OF THE CELL PRIOR TO THE | | TEST IN CONSHOHOCKEN. IT WAS DETERMINED THAT DISCONNECT BETWEEN HARNESS | | AND POSITIVE PLATE LUGS CANNOT BE CAUSED BY WELDS HAVING THE OBSERVED | | REDUCED PENETRATION DEPTH. EXCESSIVE STRESSES BROUGHT ON BY SEVERE | | HANDLING HAS TO BE PRESENT AS WELL. CORRECTIVE ACTIONS AND PREVENTIVE | | MEASURES TO ASSURE THE DESIRED LASER POWER OUTPUT TO PRODUCE WELDS WITH | | FULL PENETRATION DEPTH HAVE BEEN FULLY INSTITUTED BY C&D. | | | | (REFER TO THE HOO LOG FOR A CONTACT ADDRESS AND CONTACT TELEPHONE NUMBERS.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32731 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 08/06/97 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 15:00 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 08/06/97 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: JOHN BALLETTA |LAST UPDATE DATE: 08/06/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | |VERN HODGE, NRR RVIB | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 NOTIFICATION REGARDING W-2 SWITCHES WITH TEXIN STARWHEELS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WESTINGHOUSE TECHNICAL BULLETIN NO. NSD-TB-74-10, DATED 9/9/74, AS REVISED | | ON 9/30/74, REPORTED THAT THE STARWHEELS, MADE OF A MATERIAL CALLED TEXIN, | | IN CERTAIN TYPES OF W-2 SWITCHES HAVE EXHIBITED FAILURES. ALL PLANTS WITH | | SUCH SWITCHES INSTALLED, INCLUDING [INDIAN POINT UNIT 2], WERE INSTRUCTED | | TO REPLACE ALL TEXIN STARWHEELS IN THE AFFECTED W-2 SWITCHES. HOWEVER, THE | | TECHNICAL BULLETIN NOTED THAT 'ALL SWITCHES HAVING MORE THAN THREE STAGES' | | CAN BE 'POSITIVELY IDENTIFIED AS NOT AFFECTED BY THIS BULLETIN.'" | | | | "DURING THE RECENT REFUELING OUTAGE AT [INDIAN POINT UNIT 2], IT WAS | | DISCOVERED THAT SEVERAL SAFETY-RELATED W-2 SWITCHES, HAVING MORE THAN THREE | | STAGES, DID INDEED HAVE THE TEXIN STARWHEELS. THIS WAS VERIFIED BY THE | | CHEMICAL TESTS AND INFRARED SPECTROSCOPIC STUDIES AT CATHOLIC UNIVERSITY." | | | | "THE AFFECTED STARWHEELS [HAD] BEEN REPLACED PRIOR TO UNIT 2 RESTART. IN | | ADDITION, THE DISCOVERY OF THE TEXIN STARWHEELS IN THESE W-2 SWITCHES HAS | | BEEN COMMUNICATED TO INDUSTRY VIA THE INPO NUCLEAR NETWORK." | | | | THE LICENSEE STATED THAT THIS ISSUE AFFECTED THE RECIRCULATION SWITCHES FOR | | SAFETY INJECTION (RECIRCULATION MODE). | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32732 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 08/06/97 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 16:04 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/06/97 | +------------------------------------------------+EVENT TIME: 13:46[EDT]| |NRC NOTIFIED BY: GREG SOSSON |LAST UPDATE DATE: 08/06/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |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 +------------------------------------------------------------------------------+ | UNEXPECTED REACTOR WATER CLEANUP (RWCU) SYSTEM ISOLATION | | | | AT 1346 ON AUGUST 6, 1997, THE UNIT 2 RWCU SYSTEM ISOLATED DUE TO HIGH | | DIFFERENTIAL FLOW, AND THE INBOARD AND OUTBOARD RWCU SUCTION VALVES | | (HV-044-2F001, HV-44-2F004) AUTOMATICALLY CLOSED. PRIOR TO THE ISOLATION, | | THE '2B' FILTER DEMINERALIZER HAD BEEN PRESSURIZED; AND IT WAS BEING | | ISOLATED PER OPERATING PROCEDURE S45.1.B AT THE TIME OF THE ISOLATION. | | | | THE CAUSE OF THE HIGH DIFFERENTIAL FLOW HAD NOT BEEN DETERMINED AT THE TIME | | OF THIS EVENT NOTIFICATION. PLANT PERSONNEL ARE CURRENTLY IN THE PROCESS | | OF TROUBLESHOOTING THE CAUSE. THE RWCU SYSTEM REMAINS ISOLATED PENDING THE | | OUTCOME OF THE TROUBLESHOOTING. | | | | THIS SITUATION PLACES UNIT 2 IN A 31-DAY TECHNICAL SPECIFICATION LIMITING | | CONDITION FOR OPERATION DUE TO THE INABILITY TO PERFORM RWCU IN-LINE | | CONDUCTIVITY MONITORING. AS A RESULT, STATION CHEMISTRY PERSONNEL ARE | | MONITORING REACTOR WATER CHEMISTRY (CONDUCTIVITY) EVERY FOUR HOURS UNTIL | | THE RWCU SYSTEM IS PLACED BACK IN SERVICE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |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. | +------------------------------------------------------------------------------+