U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/18/98 - 08/19/98 ** EVENT NUMBERS ** 34647 34648 34649 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34647 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 08/18/98 | |UNIT: [1] [2] [ ] STATE: SC |NOTIFICATION TIME: 10:05 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/17/98 | +------------------------------------------------+EVENT TIME: 17:50[EDT]| |NRC NOTIFIED BY: ED BREWER |LAST UPDATE DATE: 08/18/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EDWARD MCALPINE RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | MISSED SURVEILLANCE ON HEAT DETECTORS IN THE FIRE PROTECTION SYSTEM | | | | THE CATAWBA FIRE PROTECTION PROGRAM CONTAINS A REQUIREMENT TO PERFORM A | | VISUAL INSPECTION OF ALL ACCESSIBLE SPOT-TYPE HEAT DETECTORS EVERY 6 | | MONTHS. DURING A REVIEW OF IMPROVED TECHNICAL SPECIFICATIONS AND COMPARING | | THEM TO PRESENT TECHNICAL SPECIFICATIONS, IT WAS DISCOVERED THAT THIS | | REQUIREMENT WAS NOT INCORPORATED INTO AN IMPLEMENTING PROCEDURE AND HAD NOT | | BEEN PERFORMED. THIS CONSTITUTES A VIOLATION OF OPERATING LICENSE | | COMMITMENT 16.9.6, WHICH STATES THAT ALL PROVISIONS OF THE APPROVED FIRE | | PROTECTION PROGRAM BE IMPLEMENTED AND MAINTAINED IN EFFECT. | | | | AN INSPECTION WAS PERFORMED, AND ALL DETECTORS WERE VERIFIED TO BE | | ACCEPTABLE. THE REQUIREMENT WILL BE INCORPORATED INTO AN IMPLEMENTING | | PROCEDURE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34648 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 08/18/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 12:53 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 08/18/98 | +------------------------------------------------+EVENT TIME: 09:08[CDT]| |NRC NOTIFIED BY: TODD GRANLUND |LAST UPDATE DATE: 08/18/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 63 POWER OPERATION | 63 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 EXPERIENCED A REACTOR WATER CLEANUP (RWCU) ISOLATION WHILE PLACING | | THE SYSTEM IN SERVICE DUE TO LIFTING OF A RELIEF VALVE. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT APPROXIMATELY 0908 [CDT] THIS MORNING, THE UNIT 1 REACTOR WATER CLEANUP | | SYSTEM (RWCU) WAS BEING RESTORED PER LOA-RT-101. THE RWCU SYSTEM WAS | | UNISOLATED. THE RWCU REGENERATIVE HEAT EXCHANGER WAS BEING WARMED (175øF). | | THE DIVISION 1 AND 2 RWCU HIGH DIFFERENTIAL FLOW ALARMS WERE RECEIVED. THE | | NUCLEAR STATION OPERATOR MANUALLY ISOLATED 1G33-F001 AND 1G33-F004 PRIMARY | | CONTAINMENT ISOLATION VALVES. THE 1G33-F001 [VALVE] WAS CLOSED ~ 5 SECONDS | | AFTER THE DIVISION 1 HIGH DIFFERENTIAL FLOW SIGNAL WAS RECEIVED. THE | | 1G33-F004 [VALVE] WAS FULL CLOSED AT THE SAME TIME THE DIVISION 2 HIGH | | DIFFERENTIAL FLOW SIGNAL WAS RECEIVED. THE HIGH DIFFERENTIAL FLOW ALARM | | HAS A 45-SECOND TIME DELAY PRIOR TO THE AUTOMATIC ISOLATION OF ITS | | RESPECTIVE VALVE. INVESTIGATION REVEALED THE CAUSE OF THE HIGH | | DIFFERENTIAL FLOW WAS A RELIEF VALVE LIFTING (1G33-F340A). THE REASON THE | | RELIEF VALVE LIFTED IS NOT KNOWN AND IS BEING INVESTIGATED. THE RWCU | | SYSTEM REMAINS SHUT DOWN UNTIL THE CAUSE IS DETERMINED. AFFECTED SYSTEMS | | INCLUDE RWCU AND [THE] LEAK DETECTION SYSTEMS. [THE] EFFECT ON THE PLANT | | IS MINIMAL AS THE RWCU SYSTEM WAS NOT IN OPERATION AT THE TIME." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: A PREVIOUS RWCU ISOLATION OCCURRED ON 08/17/98 WHILE ATTEMPTING | | TO PLACE THE SYSTEM IN SERVICE - SEE EVENT #34646. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34649 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 08/18/98 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 15:31 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 08/18/98 | +------------------------------------------------+EVENT TIME: 12:01[PDT]| |NRC NOTIFIED BY: HOWARD SMITH |LAST UPDATE DATE: 08/18/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A MORE LIMITING MAIN FEEDWATER LINE BREAK DURING | | OPERATOR SIMULATOR TRAINING. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON AUGUST 18, 1998, AT 1201 PDT, [SOUTHERN CALIFORNIA EDISON (SCE)] | | CONCLUDED THE FOLLOWING CONSTITUTED A REPORTABLE CONDITION UNDER | | 10CFR50.72(b)(1)(ii) FOR A CONDITION OUTSIDE THE DESIGN BASIS OF THE | | PLANT." | | | | "SCE PERSONNEL IDENTIFIED THAT ONE OF THE DESIGN BASIS ACCIDENT SCENARIOS | | OF RECORD WAS NO LONGER THE LIMITING CASE. SPECIFICALLY, THE MAIN | | FEEDWATER LINE BREAK (MFLB) ACCIDENT ANALYSIS [LINE BREAK WITH SINGLE | | FAILURE OF ONE TRAIN OF 1E EMERGENCY POWER] WOULD NOT BOUND A MFLB WITH A | | SINGLE FAILURE OF A VITAL BUS." | | | | "SPECIFICALLY, AN EMERGENCY FEEDWATER ACTUATION SIGNAL (EFAS) COUPLED WITH | | THE OPENING OF THE ISOLATION VALVES TO THE RUPTURED GENERATOR [THE VALVES | | WOULD NORMALLY REMAIN CLOSED AS LONG AS THE VITAL BUS PROVIDED POWER], | | COULD RESULT IN INADVERTENTLY SUPPLYING FEEDWATER TO A FAULTED STEAM | | GENERATOR - SUFFICIENTLY DEPLETING THE AVAILABLE INVENTORY OF CONDENSATE | | STORAGE TANK T-121 BELOW THE MINIMUM DESIGN VOLUME NEEDED TO BRING THE | | PLANT TO COLD SHUTDOWN. IN THE EVENT OF A FEEDWATER LINE BREAK, EXCESSIVE | | CONDENSATE COULD BE LOST TO THE CONTAINMENT BEFORE OPERATORS COULD TAKE | | ACTION TO SECURE THE FEED TO THE FAULTED STEAM GENERATOR." | | | | "HOWEVER, THIS EVENT HAS NO ACTUAL SAFETY SIGNIFICANCE, SINCE CONDENSATE | | STORAGE TANK T-120 CAN SUPPLEMENT TANK T-121, TO PROVIDE SUFFICIENT | | INVENTORY TO BRING THE PLANT TO COLD SHUTDOWN. SCE IS CONTINUING TO | | INVESTIGATE THIS CONDITION AND WILL PROVIDE A LICENSEE EVENT REPORT WITHIN | | 30 DAYS." | | | | "BOTH UNITS ARE IN MODE 1 AT 100% POWER." | | | | THE ABOVE CONDITION WAS IDENTIFIED BY OPERATORS DURING SIMULATOR TRAINING. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+