U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/03/98 - 08/04/98 ** EVENT NUMBERS ** 34597 34598 34599 34600 34601 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34597 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 08/03/98 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 12:56 [ET]| |RX TYPE: [3] CE |EVENT DATE: 08/03/98 | +------------------------------------------------+EVENT TIME: 11:00[CDT]| |NRC NOTIFIED BY: RANDOLPH |LAST UPDATE DATE: 08/03/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THERE WAS A POTENTIAL ERROR IN THE ENERGY | | REDISTRIBUTION FACTORS(ERF) IN THE LOCA ANALYSIS. | | | | ON 7/7/97, CONDITION REPORT 97-1818 WAS ISSUED TO ADDRESS A POTENTIAL ERROR | | IN THE ERF USED IN THE LOCA ANALYSIS. AN EVALUATION WAS PERFORMED BY | | ABB/CE TO DETERMINE THE IMPACT OF ERFs FOR WATERFORD 3. LETTER CA-97-028 | | DATED 11/25/97 SHOWED THAT FOR A PIN-IN-BOX RATIO OF 1.05, PEAK CLADDING | | TEMPERATURE(PCT) WOULD BE EFFECTED BY 36.2øF. THE BOUNDING ANALYSIS FOR | | THE PLANT AT THE TIME OF DISCOVERY(CYCLE 8) RESULTED IN A PCT OF 2177øF AND | | THE CURRENT CYCLE 9 IS 2165øF. ADDING THE ERF ERROR TO THESE PCTs RESULTS | | IN A PCT OF 2213.2øF AND 2201øF, RESPECTIVELY. ACCEPTANCE CRITERIA FOR | | EMERGENCY CORE COOLING SYSTEMS AS STATED IN 10CFR50.46(b)(1) REQUIRES PCT | | NOT EXCEED 2200øF. FAILURE TO CONFORM TO THIS CRITERION IS A VIOLATION OF | | 10CFR50.46 AND IS REPORTABLE TO THE NRC. AT THE TIME OF THIS DISCOVERY THE | | REPORTING CRITERIA WERE NOT FULLY UNDERSTOOD AND NO ACTION WAS TAKEN. | | | | ON DISCOVERY OF THE ORIGINAL ISSUE, A 0.2KW/FT PENALTY WAS INSTALLED IN | | CORE OPERATING LIMITS SUPERVISORY SYSTEM(COLSS) PER RECOMMENDATIONS FROM | | ABB/CE. ONCE THE EVALUATION WAS COMPLETED, THIS PENALTY WAS PERMANENTLY | | INSTALLED AND CORE OPERATING LIMIT REPORT(COLR) FIGURES 6&7 WERE REVISED | | PER 50.59 TO REDUCE THE ALLOWED PEAK LINEAR HEAT GENERATION RATE(PLHGR) BY | | 0.2 KW/FT. THESE ACTIONS PRESCRIBED BY ABB/CE COMPENSATE FOR THE ERROR IN | | ERFs AND RETURN THE PCTs TO 2177øF AND 2166øF. THE NRC WAS INFORMED OF THE | | ERROR ON 6/1/98 VIA THE ANNUAL REPORT ON ABB/CE ECCS PERFORMANCE EVALUATION | | MODELS. | | | | THE RESIDENT INSPECTOR WAS NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34598 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ASPHALT CONTRACTORS INC |NOTIFICATION DATE: 08/03/98 | | CITY: ECLECTIC REGION: 2 |NOTIFICATION TIME: 14:50 [ET]| | COUNTY: STATE: AL |EVENT DATE: 08/01/98 | |LICENSE#: 1045 (AL) AGREEMENT: Y |EVENT TIME: 09:00[CDT]| | DOCKET: |LAST UPDATE DATE: 08/03/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |THOMAS PEEBLES RDO | | |FRED COMBS EO | +------------------------------------------------+JOE GIITTER IRD | |NRC NOTIFIED BY: MCNEES | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE STATE OF ALABAMA REPORTED THAT ONE OF THEIR LICENSEES HAD DAMAGED A | | DEVICE CONTAINING Cs-137 AND Am-241/Be. | | | | ON 8/1/98. ASPHALT CONTRACTORS, INC. (ALABAMA RADIOACTIVE MATERIAL LICENSE | | NO.1045) REPORTED(ALABAMA INCIDENT REPORT 98-12) THAT A CAMPBELL MODEL MC | | SERIES DEVICE CONTAINING APPROXIMATELY 10 MILLICURIES OF Cs-137 AND 50 | | MILLICURIES OF Am-241/Be HAD BEEN DAMAGED AT A JOB SITE NEAR ECLECTIC, AL. | | THE RSO STATED THAT THE SOURCE ROD HAD BEEN SLIGHTLY BENT, BUT HE WAS ABLE | | TO PULL THE SOURCE BACK INTO THE SHIELD. A FIELD TEST FOR CONTAMINATION | | WAS MADE AND NO CONTAMINATION WAS DETECTED. THE DEVICE WAS CLOSED AND | | LOCKED IN THE SHIPPING CASE AND RETURNED TO THE MANUFACTURER'S | | REPRESENTATIVE. | | | | ON 8/3/98 IT WAS CONFIRMED THAT REGIS ENGINEERING HAD RECEIVED AND CHECKED | | THE DEVICE FOR LEAKAGE. IT WAS REPORTED THAT THERE WAS EXTENSIVE DAMAGE TO | | THE ELECTRONICS, BUT NO DAMAGE TO THE SOURCE CAPSULE. DUE TO BENDS AT THE | | TOP END OF THE SOURCE ROD, THE SOURCE ROD ASSEMBLY MAY HAVE TO BE SENT TO | | CAMPBELL PACIFIC TO HAVE THE SOURCE CAPSULE REMOVED AND INSTALLED ON A NEW | | ROD. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34599 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 08/03/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 18:17 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/03/98 | +------------------------------------------------+EVENT TIME: 17:27[EDT]| |NRC NOTIFIED BY: HYNE |LAST UPDATE DATE: 08/03/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM MOSLAK RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 70 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR SCRAM FROM 70% POWER DUE TO LOW REACTOR WATER | | LEVEL. | | | | THIS OCCURRED WHILE THEY WERE RESTORING THE "A" CONDENSATE PUMP BACK TO | | SERVICE AFTER MAINTENANCE. DURING THE FILLING AND VENTING OF THE "A" | | CONDENSATE PUMP, THE "B" CONDENSATE BOOSTER PUMP TRIPPED OFF LINE, | | RESULTING IN AN AUTOMATIC LOW REACTOR WATER LEVEL SCRAM PRIOR TO THE | | MANUALLY INITIATED SCRAM. FEEDWATER PUMPS DID NOT TRIP. ALL RODS FULLY | | INSERTED, BUT INITIAL INDICATIONS COULD NOT VERIFY THAT THREE RODS HAD | | INSERTED, SO THEY ENTERED EOP-3. UPON VERIFYING ALL RODS INSERTED EOP-3 | | WAS EXITED. BOTH HPCI AND RCIC STARTED WITH RCIC INJECTING FOR <3 MINS, BUT | | THEY HAVE NOT YET DETERMINED IF HPCI INJECTED PRIOR TO BEING SECURED. NO | | SAFETY RELIEF VALVES LIFTED DURING THIS EVENT. THE CAUSE OF THE "B" | | CONDENSATE BOOSTER PUMP TRIPPING IS BEING INVESTIGATED, BUT THEY SPECULATE | | THAT WHEN THE SUCTION VALVE WAS CRACKED OPEN ON THE "A" PUMP, AIR WENT TO | | THE OPERATING CONDENSATE PUMP CAUSING IT TO CAVITATE RESULTING IN LOW | | SUCTION TO THE "B" CONDENSATE BOOSTER PUMP WHICH COULD HAVE CAUSED THE PUMP | | TO TRIP. THE CONDENSER IS BEING USED AS THE HEAT SINK. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34600 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 08/04/98 | |UNIT: [ ] [2] [ ] STATE: NJ |NOTIFICATION TIME: 00:53 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/03/98 | +------------------------------------------------+EVENT TIME: 21:50[EDT]| |NRC NOTIFIED BY: JOE SULLIVAN |LAST UPDATE DATE: 08/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |TOM MOSLAK RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 2 UNEXPECTEDLY DEENERGIZED THE "2A" 4KV BUS DURING SURVEILLANCE | | TESTING DUE TO A FAILURE OF THE STATION POWER TRANSFORMER TO AUTO TRANSFER. | | | | THE FOLLOWING IS A PORTION OF A FACSIMILE RECEIVED: | | | | "THIS IS A NOTIFICATION FOR AN EVENT THAT RESULTED IN THE ACTUATION OF AN | | ENGINEERED SAFETY FEATURE (ESF)." | | | | "DURING THE PERFORMANCE OF A '2A' 4KV BUS AUTO TRANSFER TEST (IN ACCORDANCE | | WITH S2.OP-ST.4KV-0001), THE '2A' 4KV BUS BECAME DEENERGIZED WHEN THE | | TRANSFER FROM 24 STATION POWER TRANSFORMER (SPT) TO 23 SPT FAILED. THIS | | RESULTED IN AN ESF ACTUATION SIGNAL TO START [THE] '2A' DIESEL GENERATOR | | (DG). THE '2A' DG WOULD HAVE STARTED AND LOADED HAD IT NOT BEEN CLEARED | | AND TAGGED FOR ONGOING MAINTENANCE. INVESTIGATION OF THE CAUSE OF THE | | TRANSFER FAILURE IS UNDERWAY. ALL SAFETY RELATED EQUIPMENT RESPONDED AS | | EXPECTED TO THE EVENT GIVEN PLANT CONDITIONS." | | | | THE BUS REMAINS DEENERGIZED TO ASSIST TROUBLESHOOTING EFFORTS. THERE WAS | | NO INTERRUPTION IN SHUTDOWN COOLING OR SPENT FUEL POOL COOLING AS A RESULT | | OF THIS EVENT. | | | | THE LICENSEE WILL INFORM LOCAL AUTHORITIES (LAC) AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34601 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 08/04/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 05:41 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/04/98 | +------------------------------------------------+EVENT TIME: 03:47[CDT]| |NRC NOTIFIED BY: MARK RASMUSSEN |LAST UPDATE DATE: 08/04/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BRUCE BURGESS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |WILLIAM BECKNER EO | |AESF 50.72(b)(2)(ii) ESF ACTUATION |FRANK CONGEL IRD | | |DAN SULLIVAN FEMA | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | UNIT 1 DECLARED AN UNUSUAL EVENT AT 0413CDT DUE TO A LOSS OF OFFSITE POWER | | > 15 MINUTES. | | | | THE 345KV LINE SUPPLYING SYSTEM AUXILIARY TRANSFORMERS (SATs) 142-1 AND | | 142-2 RECEIVES POWER FROM TWO SWITCHYARD AIR CIRCUIT BREAKERS (ACB) 5-6 AND | | 6-7. ACB 5-6 WAS OPEN PRIOR TO THIS EVENT DUE TO A LIGHTNING STRIKE ON THE | | OFFSITE TRANSMISSION LINES. WHEN FIELD OPERATORS ATTEMPTED TO CLOSE THIS | | ACB, IT FAILED TO CLOSE AND FOR REASONS UNKNOWN GENERATED A LOCAL BREAKER | | BACKUP SIGNAL OPENING ACB 6-7, THUS ISOLATING THE POTENTIAL FAULT ON THE | | 345KV LINE. THIS DEENERGIZED BOTH SATs RESULTING IN A LOSS OF OFFSITE POWER | | TO BOTH 4160VAC ESF BUSES 141 AND 142. BOTH EMERGENCY DIESEL GENERATORs | | (EDGs) AUTOSTARTED AND CLOSED ONTO THEIR RESPECTIVE BUSES. UNIT 1 IS | | CURRENTLY STABLE WITH ALL ECCS EQUIPMENT AVAILABLE. UNIT 1 WILL CONTINUE | | TO OPERATE BOTH EDGs UNTIL THE 345KV SWITCHYARD PROBLEM IS RESOLVED. THE | | LICENSEE WILL TERMINATE THE UNUSUAL EVENT ONCE OFFSITE POWER IS RESTORED. | | | | THE LICENSEE INFORMED STATE/LOCAL AGENCIES AND WILL INFORM THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+