U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/19/95 - 09/20/95 ** EVENT NUMBERS ** 29181 29346 29347 29348 29349 29350 29351 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29181 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 08/10/95 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 13:03 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 08/08/95 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: FRAN SULLIVAN |LAST UPDATE DATE: 09/19/95 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JEROME BLAKE RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | POTENTIAL FOR AN AUTOMATIC ENGINEERED SAFETY FEATURE ACTUATION THAT WAS NOT | | PART OF A PREPLANNED SEQUENCE DURING TESTING. | | | | AT 1230 ON AUGUST 10, 1995, THE LICENSEE IDENTIFIED THAT AN AUTOMATIC | | ENGINEERED SAFETY FEATURE COULD HAVE ACTUATED THAT WAS NOT PART OF A | | PREPLANNED SEQUENCE DURING TESTING. AS A RESULT OF THE PERFORMANCE OF | | SURVEILLANCE PROCEDURE SP358A TO TEST THE 2-OUT-OF-3 ENGINEERED SAFETY | | FEATURE ACTUATION LOGIC, THE LICENSEE IDENTIFIED A SUSPECTED PROBLEM OF THE | | ENGINEERED SAFETY MATRIX. TROUBLESHOOTING ON AUGUST 8, 1995, REVEALED THAT | | THE WIRING MATRIX WAS SUCH THAT CORE FLOOD VALVE 25 (WHICH IS A CONTAINMENT | | ISOLATION VALVE FOR THE CORE FLOOD TANK) WOULD HAVE GONE CLOSED IF 1 OUT OF | | 3 CHANNELS TRIPPED IN LIEU OF 2 OUT OF 3 CHANNELS. DURING PRE-PLANNED | | TESTING, PERFORMANCE OF A SURVEILLANCE PROCEDURE, OR ANY TIME ONE | | PARTICULAR CHANNEL IS TRIPPED; THE CORE FLOOD VALVE WOULD HAVE CLOSED. THIS | | DID NOT ACTUALLY OCCUR BUT COULD HAVE HAPPENED AT ANY TIME. THE VALVE IS | | NORMALLY CLOSED, AND THERE WAS NO VALVE MOVEMENT. THE LICENSEE HAS | | CORRECTED THE PROBLEM. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 2043 ON 9/19/95 BY SULLIVAN TAKEN BY WEAVER * * * | | THE ORIGINAL NOTIFICATION WAS MADE BECAUSE A DETERMINATION OF WHETHER OR | | NOT AN ESF ACTUATION OCCURRED COULD NOT BE MADE WITHIN FOUR HOURS. SINCE | | NO INDICATION OF AN ESF ACTUATION WAS DISCOVERED, THE LICENSEE IS | | RETRACTING THIS EVENT. NO LER WILL BE SUBMITTED. THE LICENSEE WILL | | INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29346 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 09/19/95 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 13:32 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 09/19/95 | +------------------------------------------------+EVENT TIME: 12:05[CDT]| |NRC NOTIFIED BY: JOHN JOHNSON |LAST UPDATE DATE: 09/19/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 78 POWER OPERATION | 78 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTRABAND FOUND IN THE PROTECTED AREA - | | | | THE CONTRABAND HAS BEEN TAKEN INTO CUSTODY BY THE SECURITY FORCE. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. SEE HOO LOG FOR DETAILS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29347 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/19/95 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 16:39 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/19/95 | +------------------------------------------------+EVENT TIME: 16:00[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/19/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 +------------------------------------------------------------------------------+ | - BOTH COMPONENT COOLING WATER PUMPS (CCW) INOPERABLE FOR 12 MINUTES - | | | | THE PLANT ENTERED TECH SPEC 3.0.3 WHEN THE DISCHARGE CHECK VALVE OF THE | | EAST CCW PUMP STUCK OPEN. THE EAST PUMP WAS DECLARED INOPERABLE BECAUSE OF | | THE STUCK OPEN CHECK VALVE. THE WEST PUMP, WHICH IS IN PARALLEL OPERATION | | WITH THE EAST PUMP, WAS ALSO DECLARED INOPERABLE BECAUSE OF THE REVERSE | | FLOW THAT WOULD OCCUR THROUGH THE EAST PUMP. | | | | TECH SPEC 3.0.3 WAS EXITED WHEN THE EAST PUMP WAS MANUALLY ISOLATED, THUS | | PREVENTING REVERSE FLOW THROUGH THE PUMP AND CHECK VALVE. THE PLANT IS NOW | | IN TECH SPEC 3.7.3.1 BECAUSE OF THE ONE INOPERABLE CCW PUMP. THIS IS A 72 | | HOUR LCO. CHECK VALVE REPAIR IS IN PROGRESS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 29348 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SIEMENS POWER CORPORATION |NOTIFICATION DATE: 09/19/95 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 19:15 [ET]| |COMMENTS: LEU CONVERSION (UF6 to UO2) |EVENT DATE: 09/19/95 | | FABRICATION & SCRAP RECOVERY |EVENT TIME: 12:30[PDT]| | COMMERICAL LWR FUEL |LAST UPDATE DATE: 09/19/95 | | CITY: RICHLAND REGION: 4 +-----------------------------+ | COUNTY: BENTON STATE: WA |PERSON ORGANIZATION| |LICENSE#: SNM-1227 AGREEMENT: Y |BLAINE MURRAY RDO | | DOCKET: 07001257 |ROBERT PIERSON EO | +------------------------------------------------+ | |NRC NOTIFIED BY: LOREN MAAS | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE CRITICALITY SAFETY ANALYSIS CONTAINS AN INVALID ASSUMPTION RELATED TO | | URANIUM DENSITY | | | | THE ASSUMED DENSITY IN THE CENTRIFUGE CHUTE (LINE 2 ADU PROCESS) WAS 85O | | GRAMS OF URANIUM PER LITER. DENSITIES AS HIGH AS 1100 GRAMS OF URANIUM PER | | LITER WERE FOUND IN THE PROCESS TRAIN. THIS ERROR WAS DISCOVERED AS PART | | OF AN ONGOING REVIEW TO RECONFIRM THE CRITICALITY SAFETY ANALYSIS | | ASSUMPTIONS. | | | | CALCULATIONS HAVE ALREADY BEEN PERFORMED WHICH SHOW THAT NO CREDIBLE | | CRITICALITY PATHWAY EXISTS UNDER WORST CASE CONDITIONS. HOWEVER THEIR | | LICENSE REQUIRES THAT A SECOND PARTY REVIEW THE CALCULATIONS. PROCESS LINES | | ONE AND TWO WERE SHUTDOWN AT 1600 PDT PENDING COMPLETION OF THE SECOND | | PARTY REVIEW. THE REVIEW IS EXPECTED TO BE COMPLETED TOMORROW. | | | | THE LICENSEE WILL NOTIFY THE REGIONAL OFFICE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29349 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 09/19/95 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:28 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/19/95 | +------------------------------------------------+EVENT TIME: 20:00[EDT]| |NRC NOTIFIED BY: STEVEN DENNIS |LAST UPDATE DATE: 09/19/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -THE SAFETY PARAMETER DISPLAY SYSTEM IS NOT AVAILABLE UNDER ALL CONDITIONS- | | | | ON 9/15/95 AT 1200 PROBLEMS WITH THE COOLING FAN TO THE INVERTER SUPPLYING | | POWER TO THE SAFETY PARAMETER DISPLAY SYSTEM (SPDS) WERE DISCOVERED. AS A | | RESULT, THE INVERTER WAS REMOVED FROM SERVICE AND POWER TO SPDS WAS | | SWITCHED TO THE ALTERNATE POWER SUPPLY. THIS ALSO ELIMINATED THE 30 MINUTE | | BATTERY BACKUP SUPPLY TO SPDS THROUGH THE INVERTER. | | | | SINCE THEN A REVIEW OF THE CURRENT POWER SUPPLY CONFIGURATION TO SPDS | | INDICATED THAT UNDER CERTAIN CONDITIONS, INCLUDING A LOSS OF POWER AND A | | LOSS OF COOLANT ACCIDENT, THE SPDS WOULD NOT BE IMMEDIATELY AVAILABLE. | | MANUAL ACTION CAN BE TAKEN TO RESTORE POWER AS DIRECTED BY EMERGENCY | | OPERATING PROCEDURES. CURRENTLY SPDS IS AVAILABLE BUT BECAUSE OF THE | | EXISTING CONDITION, NOT IMMEDIATELY AVAILABLE FOR ALL POTENTIAL EVENTS IN | | WHICH IT WOULD BE RELIED UPON. | | | | BASED ON THIS, AND REFERENCING NUREG 1022 REGARDING LOSS OF SPDS, THE | | LICENSEE IS MAKING THIS 50.72 REPORT. THE ESTIMATED RETURN TO SERVICE OF | | THE SPDS INVERTER IS 2400 ON 9/20/95. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29350 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 09/19/95 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 21:19 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 09/19/95 | +------------------------------------------------+EVENT TIME: 17:37[EDT]| |NRC NOTIFIED BY: NIX |LAST UPDATE DATE: 09/19/95 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES HOSEY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -THE PLANT MAY BE UNABLE TO MEET THE DESIGN TIME REQUIREMENT IN STARTING | | AUXILIARY SERVICE WATER IN A TORNADO EVENT- | | | | "THE OCONEE TORNADO ANALYSIS CURRENTLY ASSUMES 40 MINUTES FOR OPERATOR | | ACTION TO INITIATE AUXILIARY SERVICE WATER FLOW TO REMOVE SECONDARY DECAY | | HEAT. BASED ON EXPERIENCE DRAWN FROM AN EMERGENCY DRILL (TORNADO EVENT), | | IT WAS CONCLUDED THAT A POTENTIAL PROBLEM WITH MEETING THE 40 MINUTES | | ASSUMED IN THE TORNADO ANALYSIS MAY EXIST. THIS EVENT IS BEING | | CONSERVATIVELY REPORTED. DUKE POWER WILL CONTINUE TO EVALUATE THE DESIGN | | BASIS REQUIREMENTS FOR THE AUXILIARY SERVICE WATER SYSTEM AND UPDATE THIS | | REPORT, AS NECESSARY, IN THE FUTURE." | | | | THE TIME REQUIRED TO COMPLETE OTHER COMPETING REQUIRED ACTIONS DELAYED | | IMPLEMENTING THE ABNORMAL OPERATING PROCEDURE WHICH STARTS THE AUXILIARY | | SERVICE WATER PUMP. THIS DELAY CAUSED THE 40 MINUTE TIME REQUIREMENT TO BE | | EXCEEDED. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29351 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUSQUEHANNA REGION: 1 |NOTIFICATION DATE: 09/20/95 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 05:46 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/20/95 | +------------------------------------------------+EVENT TIME: 04:15[EDT]| |NRC NOTIFIED BY: BOYLE |LAST UPDATE DATE: 09/20/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THE PLANT FAILED THE MAIN STEAM ISOLATION VALVE | | LOCAL LEAK RATE TEST (LLRT). | | | | THIS WAS DETERMINED FROM THE DATA EVALUATION FROM THE MAIN STEAM ISOLATION | | VALVE LLRT INDICATING THAT THE LEAKAGE THROUGH THE MAIN STEAM ISOLATION | | VALVES HAS DEGRADED BEYOND THE TS 3.6.1.2.C LIMIT OF 21.7 SLM(46 SCFH). THE | | AS FOUND LEAKAGE WAS 27.4 SLM. THE LEAKAGE OF THE MSIVs ABOVE THE TS LIMIT | | CONSTITUTES AN EVENT FOUND WHILE THE REACTOR IS SHUTDOWN THAT RESULTED IN A | | DEGRADATION OF PRINCIPLE SAFETY BARRIERS. | | | | THE LICENSEE WAS ALLOWED TO RESTROKE THE VALVES PER PROCEDURES TO ATTEMPT | | TO GET A BETTER SEAL. THIS WAS DONE AND A RETEST WAS PERFORMED WITH THE | | RESULTING DATA BEING SATISFACTORY. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+