U.S. Nuclear Regulatory Commission Operations Center Event Reports For 04/29/97 - 04/30/97 ** EVENT NUMBERS ** 32058 32232 32236 32237 32238 32239 32240 32241 32242 32243 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32058 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/31/97 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 18:54 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/31/97 | +------------------------------------------------+EVENT TIME: 16:00[EST]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 04/29/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVE VERRELLI RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 95 POWER OPERATION | 95 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED AN ERROR IN ITS ACCIDENT ANALYSIS. (THIS IS | | SIMILAR TO A REPORT FROM HATCH (EVENT #32011) ON 03/25/97.) | | | | AN INCONSISTENCY BETWEEN THE FUEL VENDOR (GENERAL ELECTRIC) ROD WITHDRAWAL | | ERROR (RWE) ANALYSIS ASSUMPTIONS AND TECHNICAL SPECIFICATION OPERABILITY | | REQUIREMENTS FOR THE ROD BLOCK MONITOR (RBM) SYSTEM HAS BEEN IDENTIFIED. | | THE VENDOR ASSUMED THAT THE RBM WAS OPERABLE DURING THE RWE EVENTS FOR | | BRUNSWICK OPERATING CYCLE B1C10 TO ENSURE THAT THE FUEL MECHANICAL | | OVERPOWER (MOP) CRITERIA WERE NOT EXCEEDED. THE LICENSEE IDENTIFIED AT | | LEAST ONE OCCURRENCE DURING THE B1C10 OPERATING CYCLE (1995) WHEN CONTROL | | RODS WERE WITHDRAWN WITH THE RBM SYSTEM INOPERABLE PER TECHNICAL | | SPECIFICATION GUIDANCE. WITH REACTOR POWER ABOVE 90% RATED THERMAL POWER | | AND MINIMUM CRITICAL POWER RATIO (MCPR) ABOVE 1.4, THE TECHNICAL | | SPECIFICATIONS DO NOT REQUIRE THE RBM TO BE OPERABLE. AN RWE ANALYSIS | | INDICATED A SMALL VIOLATION OF THE MOP CRITERIA. THIS IS BEING REPORTED AS | | A FAILURE OF THE RBM TO MITIGATE THE CONSEQUENCE OF AN RWE. THIS IS BASED | | UPON NEITHER RBM BEING AVAILABLE TO PREVENT THE RWE. | | | | THE CURRENT TECHNICAL SPECIFICATION REQUIREMENTS FOR THE RBM ARE ACCEPTABLE | | FOR BRUNSWICK OPERATING CYCLE B1C11. | | | | THE SAFETY SIGNIFICANCE OF THIS EVENT IS SMALL. THE VENDOR INDICATED THAT | | THE SMALL VIOLATION OF THE MOP CRITERIA, WITH THE CONSERVATIVE NATURE OF | | THE MOP CRITERIA WITH RESPECT TO THE 1% PLASTIC STRAIN AND BASED UPON | | GENERIC CALCULATIONS, IT IS HIGHLY UNLIKELY THAT THE 1% PLASTIC STRAIN | | CRITERIA WOULD HAVE BEEN EXCEEDED, EVEN WITH NO CREDIT FOR THE RBM ROD | | BLOCK. | | | | THERE ARE NO IMMEDIATE CORRECTIVE ACTIONS FOR THIS EVENT SINCE THE CURRENT | | TECHNICAL SPECIFICATIONS ARE ADEQUATE FOR BRUNSWICK OPERATING CYCLES B1C11 | | AND B2C12. THE INVESTIGATION OF THIS EVENT THROUGH CORRECTIVE ACTION | | PROGRAM WILL ADDRESS THE NEEDED CORRECTIVE ACTIONS TO PRECLUDE RECURRENCE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 1140 EDT ON 04/29/97, FROM MARK TURKAL TO S. SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION BASED ON THE FOLLOWING: | | | | THE LICENSEE EVALUATED THE GENERAL ELECTRIC ANALYSIS RECEIVED ON 04/11/97, | | FOR THIS FUEL CYCLE AND CONCLUDED THAT THE 1% STRAIN LIMIT WOULD NOT BE | | EXCEEDED. THE CALCULATED STRAIN WAS APPROXIMATELY 0.5%. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (CASTO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32232 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/28/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:38 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/28/97 | +------------------------------------------------+EVENT TIME: 04:00[CDT]| |NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 04/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -SPDS & ERDS INOPERABLE FOR 24 HOURS DUE TO PLANNED MAINTENANCE ACTIVITIES- | | | | AT 0400 CDT ON 04/28/97, THE LICENSEE PLANS TO DECLARE THE SAFETY PARAMETER | | DISPLAY SYSTEM (SPDS) INOPERABLE DUE TO THE LOSS OF POWER FROM THE #1D | | STATION UNINTERRUPTIBLE POWER SUPPLY (UPS). THE LICENSEE PLANS TO REMOVE | | THE #1D UPS FROM SERVICE FOR PLANNED MAINTENANCE ACTIVITIES. POWER TO THE | | PLANT EMERGENCY RESPONSE DATA SYSTEM (ERDS) ALSO WILL BE LOST DURING THIS | | TIME. | | | | THE LICENSEE PLANS TO RESTORE ALL SYSTEMS TO NORMAL WITHIN 24 HOURS. THE | | LICENSEE ALSO PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * 0433 EST 04/29/97, UPDATE FROM FUNKHOUSER ENTERED BY JOLLIFFE * * * | | | | AT 0330 CDT ON 04/29/97, THE LICENSEE COMPLETED THE PLANNED MAINTENANCE | | ACTIVITIES ON THE #1D UPS, RESTORED THE #1D UPS TO SERVICE, AND DECLARED | | THE SPDS AND ERDS OPERABLE. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS CENTER NOTIFIED THE R3DO (MARK RING). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32236 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 04/29/97 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 10:20 [ET]| |RX TYPE: [3] CE |EVENT DATE: 04/28/97 | +------------------------------------------------+EVENT TIME: 21:38[CDT]| |NRC NOTIFIED BY: PAUL CAROPINO |LAST UPDATE DATE: 04/29/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE ISSUED A PRESS RELEASE AFTER DROPPING A NEW FUEL ASSEMBLY | | DURING FUEL MOVEMENT IN THE SPENT FUEL POOL. | | | | "AT APPROXIMATELY 2138 ON APRIL 28, 1997, A NEW FUEL ASSEMBLY WAS DROPPED | | IN THE SPENT FUEL POOL. IT FELL FROM THE SPENT FUEL HANDLING TOOL AND CAME | | TO REST BETWEEN CELLS DD20, EE20, DD21, AND EE21 LEANING AGAINST THE SOUTH | | WALL. ALL FUEL HANDLING ACTIVITIES WERE HALTED AND THE FUEL HANDLING | | BUILDING WAS EVACUATED. THERE WAS NO RELEASE OF RADIOACTIVITY FROM THE | | ASSEMBLY. PLANT PERSONNEL ENTERED OFF-NORMAL PROCEDURE OP-901-405 'FUEL | | HANDLING INCIDENT.' CURRENT CONDITIONS ARE STABLE. THE CAUSE OF THE EVENT | | IS UNKNOWN AND THE SAFETY SIGNIFICANCE OF THE EVENT APPEARS TO BE MINIMAL | | OR NONE." | | | | THE LICENSEE ISSUED A PRESS RELEASE AND INFORMED THE NRC RESIDENT | | INSPECTOR. | | | | * * * UPDATE AT 1340 EDT FROM E. LEMKE TO BAILEY * * * | | | | THE SUBJECT FUEL ASSEMBLY (FE R338) WAS BEING MOVED AS PART OF A REFUELING | | OUTAGE WHEN IT WAS DROPPED FROM THE +46 FOOT LEVEL OF THE FUEL HANDLING | | BUILDING. THE PLANT WAS IN DAY 18 OF A SCHEDULED 40 DAY REFUELING OUTAGE. | | FIVE PEOPLE WERE EVACUATED FOR 1 HOUR OR MORE. RADIATION, CONTAMINATION | | AND AIRBORNE SURVEYS WERE PERFORMED IMMEDIATELY AFTER THE EVACUATION. RATES | | WERE ALL LESS THAN 2 mR/HR. THE AREA RADIATION MONITOR ON THE +46 FOOT | | LEVEL DID NOT ALARM. A VISUAL INSPECTION OF THE ASSEMBLY SHOWED NO | | APPARENT DAMAGE. A CAMERA WILL BE USED LATER TO INSPECT ALL COMPONENTS | | INVOLVED IN THE EVENT. TEAMS HAVE BEEN FORMED TO DETERMINE CIRCUMSTANCES | | OF THE EVENT AND ROOT CAUSES. IN ADDITION, A RECOVERY TEAM IS BEING FORMED | | TO STABILIZE THE ASSEMBLY AND THEN MOVE IT TO STORAGE. THE PRESS RELEASE | | WAS TO BOTH LOCAL AND NATIONAL NEWS ORGANIZATIONS. | | | | THE LICENSEE NOTIFIED THE RESIDENT INSPECTOR. THE HOO NOTIFIED THE R4DO | | (P. HARRELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32237 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 04/29/97 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 10:40 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/29/97 | +------------------------------------------------+EVENT TIME: 07:43[EDT]| |NRC NOTIFIED BY: BILL WEBSTER |LAST UPDATE DATE: 04/29/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |AL BELISLE 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 1 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - MANUAL REACTOR TRIP FROM 1% DUE TO A ROD CONTROL SYSTEM URGENT FAILURE - | | | | AT 1226 ON 04/28/97, WHILE STARTING UNIT 1 UP FROM A REFUELING OUTAGE, | | THE REACTOR WAS CRITICAL AT 1E-7 AMPS ON THE INTERMEDIATE RANGE NUCLEAR | | INSTRUMENTATION DETECTORS (LESS THAN 1% POWER) FOR THE PERFORMANCE OF LOW | | POWER CORE PHYSICS TESTING. | | | | AT 0046 ON 04/29/97, A ROD CONTROL SYSTEM URGENT FAILURE ALARM WAS RECEIVED | | WHILE MOVING THE ROD CONTROL SELECTOR SWITCH IN SUPPORT OF THE TESTING. | | LICENSEE TROUBLESHOOTING OF THE ROD CONTROL SYSTEM PROBLEM WAS UNSUCCESSFUL | | IN DETERMINING THE CAUSE. | | | | AT 0743 ON 04/29/97, CONTROL ROOM OPERATORS MANUALLY TRIPPED THE REACTOR | | FROM A POWER LEVEL OF 1E-7 AMPS. ALL CONTROL RODS INSERTED COMPLETELY. UNIT | | 1 IS STABLE IN MODE 3 (HOT SHUTDOWN) AT 547øF. | | | | THE LICENSEE IS DETERMINING CORRECTIVE ACTION AND INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32238 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/29/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:14 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/28/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:15[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 04/29/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |WAYNE KROPP RDO | | DOCKET: 0707001 | | +------------------------------------------------+ | |NRC NOTIFIED BY: A. CARVER | | |HQ OPS OFFICER: HENRY BAILEY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | | | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ON 4/28/97 ADDITIONAL INSPECTIONS OF THE FIRE PROTECTION SYSTEMS IN PLANT | | PROCESS BUILDINGS WERE PERFORMED. HOLES WERE DISCOVERED IN INSPECTION TEST | | VALVE PIPING IN THE C-335 PROCESS BUILDING WHICH AFFECT THE OPERABILITY OF | | TWO BUILDING SPRINKLER SYSTEMS (SYSTEMS 9 AND 28). THIS SITUATION | | INVALIDATES THE RESULTS OF THE ANNUAL TECHNICAL-SPECIFICATION-REQUIRED | | SURVEILLANCE. | | | | THE AFFECTED SYSTEMS WERE DECLARED INOPERABLE AND HOURLY FIRE PATROLS WERE | | INITIATED AS REQUIRED BY TSR 2.4.4.5. FURTHER INSPECTIONS AND REPAIRS ARE | | ONGOING AT THIS TIME. | | | | THESE DEFICIENCIES ARE IN ADDITION TO THOSE IDENTIFIED IN NRC NOTIFICATION | | WORK SHEET NUMBERS 32148, 32162, 32170, 32215, 32222, 32228, AND 32231. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32239 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: KENTUCKY ELECTRIC STEEL |NOTIFICATION DATE: 04/29/97 | | CITY: ASHLAND REGION: 2 |NOTIFICATION TIME: 14:26 [ET]| | COUNTY: BOYD STATE: KY |EVENT DATE: 04/28/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 23:30[EDT]| | DOCKET: |LAST UPDATE DATE: 04/29/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |C. CASTO RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: V. JEFFS |RUTHERFORD EPA | |HQ OPS OFFICER: HENRY BAILEY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STATE OF KENTUCKY, DEPARTMENT OF RADIATION CONTROL, REPORTED ELEVATED | | RADIATION READING DETECTED AT STEEL PLANT. | | | | AT 2330 ON 4/28/97, ELEVATED RADIATION LEVELS (20 æR/HR) WERE DETECTED NEAR | | A RAIL CAR FULL OF DUST AT A STEEL PLANT (KENTUCKY ELECTRIC STEEL) NEAR | | ASHLAND KENTUCKY. THE BAG HOUSE WHERE THE DUST WAS COLLECTED WAS THEN | | SURVEYED AND A LEVEL OF 80 æR/HR WAS FOUND IN THE AREA. THE DUST IS | | COLLECTED AS A BYPRODUCT OF THE STEEL MAKING PROCESS. A CONSULTANT (SEG OF | | OAK RIDGE, TN) CAME TO THE SITE AND IDENTIFIED THE ISOTOPE AS Cs-137. AN | | INVESTIGATION IS CONTINUING. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32240 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AUTOMATIC SWITCH COMPANY |NOTIFICATION DATE: 04/29/97 | | CITY: FLORHAM PARK REGION: 1 |NOTIFICATION TIME: 15:47 [ET]| | COUNTY: STATE: NJ |EVENT DATE: 04/29/97 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 04/29/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KATHLEEN DOLCE RDO | | |AL CHAFFEE, NRR EO | +------------------------------------------------+VERN HODGE, RVIB NRR | |NRC NOTIFIED BY: RANDY P. SMITH | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC SWITCH COMPANY (ASCO) 10 CFR PART 21 NOTIFICATION OF A POTENTIAL | | SAFETY-RELATED PROBLEM WITH ASCO HV-266000-007J SCRAM SOLENOID PILOT VALVES | | POSSIBLY SUPPLIED TO SEVERAL BOILING WATER REACTOR NUCLEAR POWER PLANTS | | THROUGH GENERAL ELECTRIC (THIS NOTIFICATION MAY BE RELATED TO THE | | TECHNICAL SPECIFICATION SHUTDOWN REPORTED BY OYSTER CREEK ON 04/22/97 - | | EVENT #32196) | | | | DURING PERFORMANCE MAINTENANCE TESTING OF SCRAM SOLENOID PILOT VALVES AT | | OYSTER CREEK NUCLEAR PLANT, 13 OUT OF 36 SCRAM SOLENOID VALVES INSTALLED IN | | THE PLANT EXHIBITED EXCESSIVE AIR LEAKAGE. AN INVESTIGATION BY THE | | UTILITY, GENERAL ELECTRIC, AND ASCO CONCLUDED THAT THE LEAKAGE WAS THE | | RESULT OF HARDENING OF THE CORE DISC IN THE SCRAM SOLENOID PILOT VALVE | | PILOT HEAD. SUBSEQUENT INVESTIGATION BY ASCO ALSO INDICATED THAT SOME SCRAM | | SOLENOID PILOT VALVES IN THE OYSTER CREEK PLANT MAY HAVE BEEN SHIPPED WITH | | CORE DISCS FABRICATED FROM COMMERCIAL GRADE BUNA-N (NITRILE) MATERIAL | | RATHER THAN THE REQUIRED NUCLEAR GRADE FLUOROCARBON MATERIAL. | | | | ASCO IS CONTINUING ITS INVESTIGATION (IN COOPERATION WITH THE UTILITY AND | | GENERAL ELECTRIC) TO DETERMINE THE ROOT CAUSE OF THIS PROBLEM AND THE | | POPULATION OF SUSPECT SCRAM SOLENOID PILOT VALVES. THE EVIDENCE CURRENTLY | | SUGGESTS THAT THE SUBSTITUTION OF THE BUNA-N MATERIAL OCCURRED IN A PORTION | | OF THE FIRST LOT OF SCRAM SOLENOID PILOT VALVES MANUFACTURED AFTER A 1994 | | DESIGN CHANGE THAT CHANGED THE CORE DISCS TO THE FLUOROCARBON MATERIAL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32241 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TURKEY POINT REGION: 2 |NOTIFICATION DATE: 04/29/97 | |UNIT: [3] [4] [ ] STATE: FL |NOTIFICATION TIME: 18:15 [ET]| |RX TYPE: [3] W-3-LP,[4] W-3-LP |EVENT DATE: 04/29/97 | +------------------------------------------------+EVENT TIME: 12:54[EDT]| |NRC NOTIFIED BY: JOHN EATON |LAST UPDATE DATE: 04/29/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 4 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FITNESS-FOR-DUTY REPORT | | | | A LICENSEE SUPERVISOR TESTED POSITIVE FOR ALCOHOL BASED UPON A FOR-CAUSE | | TEST. THE INDIVIDUAL'S ACCESS WAS DENIED, AND THE LICENSEE PLANS TO | | PERFORM A REVIEW OF THE INDIVIDUAL'S WORK ACTIVITIES BACK TO THE | | INDIVIDUAL'S LAST FITNESS-FOR-DUTY TEST DATE. (REFER TO THE HOO LOG FOR | | ADDITIONAL INFORMATION.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32242 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FARLEY REGION: 2 |NOTIFICATION DATE: 04/29/97 | |UNIT: [1] [2] [ ] STATE: AL |NOTIFICATION TIME: 21:26 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 04/29/97 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: JIM HUNTER |LAST UPDATE DATE: 04/29/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CASTO RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | VOLUNTARY NOTIFICATION OF A PLAN TO REMOVE POWER FROM THE EMERGENCY | | OPERATING FACILITY (EOF) DUE TO PLANNED MAINTENANCE | | | | AT APPROXIMATELY 2200 EDT, THE LICENSEE PLANS TO PERFORM MAINTENANCE ON THE | | BREAKER THAT SUPPLIES POWER TO THE EOF. THE MAINTENANCE ACTIVITIES WILL | | REMOVE THE BREAKER FROM SERVICE AND INTERRUPT POWER TO THE EOF. THIS IN | | TURN WILL CAUSE THE EOF TO BE INOPERABLE. IF POWER TO THE EOF WAS | | INTERRUPTED DUE TO A FAILURE RATHER THAN A PLANNED ACTIVITY, A ONE-HOUR | | REPORT WOULD BE REQUIRED. | | | | THE LICENSEE'S EMERGENCY PLAN REQUIRES THE LICENSEE TO STAFF THE EOF WITHIN | | 75 MINUTES FROM THE TIME OF AN EMERGENCY CLASSIFICATION. HOWEVER, THE | | LICENSEE ANTICIPATES THAT THE PLANNED MAINTENANCE ACTIVITIES WILL TAKE | | APPROXIMATELY 45 MINUTES. IN ADDITION, THE ALTERNATE EOF WILL REMAIN | | OPERABLE DURING THE MAINTENANCE ACTIVITIES. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC OPERATIONS CENTER WHEN POWER TO THE | | EOF IS RESTORED. THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * 2223 APRIL 29, 1997, UPDATE FROM HUNTER RECEIVED BY TROCINE * * * | | | | THE LICENSEE REPORTED THAT THE EOF WAS RETURNED TO SERVICE AT 2208 EDT. IT | | HAD BEEN REMOVED FROM SERVICE AT 2131 EDT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | CENTER NOTIFIED THE R2DO (CASTO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32243 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HATCH REGION: 2 |NOTIFICATION DATE: 04/30/97 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 04:36 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 04/30/97 | +------------------------------------------------+EVENT TIME: 02:30[EDT]| |NRC NOTIFIED BY: COLEMAN |LAST UPDATE DATE: 04/30/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CASTO RDO | |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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE | | | | THE LICENSEE HAS DECLARED THE HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM | | INOPERABLE DUE TO AN INTERMITTENT GROUND ON THE ASSOCIATED DC ELECTRICAL | | BUS. AFTER PERFORMING A MONTHLY SURVEILLANCE TEST ON THE HPCI SYSTEM, A | | GROUND OCCURRED ON THE 'B' STATION SERVICE BATTERY BUS WHEN THE HPCI | | AUXILIARY OIL PUMP WAS STOPPED. THE BREAKER FOR THE PUMP WAS OPENED, AND | | THE GROUND CLEARED. HOWEVER, MAINTENANCE TECHNICIANS WERE UNABLE TO FIND | | ANY PROBLEM WITH THE PUMP MOTOR, AND WHEN THE BREAKER WAS RECLOSED, THE | | GROUND DID NOT RECUR. THE LICENSEE THEN REPEATED THE HPCI SURVEILLANCE, AND | | THE GROUND AGAIN OCCURRED WHEN THE AUXILIARY OIL PUMP WAS STOPPED. THE | | LICENSEE IS CONTINUING TO INVESTIGATE THE PROBLEM. THE NRC RESIDENT | | INSPECTOR WILL BE INFORMED. | +------------------------------------------------------------------------------+