U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/19/98 - 08/20/98 ** EVENT NUMBERS ** 34647 34650 34651 34652 34653 34654 34655 34656 34657 34658 34659 34660 +----------------------------------+ +-----------------------+ |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: 08/19/98 | |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. | | | | * * * UPDATE AT 1156 EDT ON 08/19/98 FROM E.BREWER TO S.SANDIN * * * | | | | THE FOLLOWING INFORMATION WAS PROVIDED BY THE LICENSEE AS AN UPDATE TO THE | | ONGOING INVESTIGATION: | | | | "DURING A REVIEW OF A PROCEDURE ASSOCIATED WITH FIRE DETECTOR INSPECTION, | | IT WAS DISCOVERED THAT A WORK REQUEST USED TO IMPLEMENT THE PROCEDURE HAD | | BEEN DELETED. THE PROCEDURE IS USED TO SATISFY A REQUIREMENT TO REMOVE AND | | TEST NON-RESTORABLE SPOT-TYPE DETECTORS. THERE ARE CURRENTLY 20 | | NON-RESTORABLE SPOT-TYPE HEAT DETECTORS AT CATAWBA. OF THESE, TWELVE ARE | | SPECIFIC LICENSING COMMITMENTS. ALL TWELVE ARE LOCATED IN THE CONTROL | | ROOM." | | | | "THE TWELVE DETECTORS WERE DECLARED INOPERABLE DUE TO THE MISSING TESTING | | REQUIREMENT. THE DETECTORS HAVE BEEN REPLACED." | | | | "FACILITY OPERATING LICENSE CONDITIONS 2.C(8) FOR UNIT 1 AND 2.C(6) FOR | | UNIT 2 REQUIRE THAT THE LICENSEE IMPLEMENT AND MAINTAIN ALL PROVISIONS OF | | THE FIRE PROTECTION PROGRAM AS DESCRIBED IN THE UPDATED FINAL SAFETY | | ANALYSIS REPORT. IT WAS DETERMINED THAT THIS CONDITION IS A VIOLATION OF | | THE FIRE PROTECTION PROGRAM AND, THEREFORE, IS REPORTABLE TO THE NRC WITHIN | | 24 HOURS IN ACCORDANCE WITH LICENSE CONDITION 2.F." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R2DO (BARR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34650 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 08/19/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 12:39 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/19/98 | +------------------------------------------------+EVENT TIME: 11:45[EDT]| |NRC NOTIFIED BY: ANDREW WISNIEWSKI |LAST UPDATE DATE: 08/19/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE 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 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE INFORMED THAT THE WEATHER ALERT RADIO SYSTEM WAS INOPERABLE | | FOR REASONS UNKNOWN. | | | | AT 1145 EDT, THE CONTRACTOR RESPONSIBLE FOR MAINTAINING THE WEATHER ALERT | | RADIO SYSTEM NOTIFIED THE LICENSEE THAT THE AMES HILL NOAA TRANSMITTER WAS | | INOPERABLE. THE CONTRACTOR HAS INITIATED REPAIRS ALTHOUGH NO ESTIMATE FOR | | RESTORATION IS AVAILABLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND PLANS TO INFORM THE | | STATES OF NEW HAMPSHIRE, VERMONT, AND MASSACHUSETTS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34651 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NEUTRON PRODUCTS, INCORPORATED |NOTIFICATION DATE: 08/19/98 | | CITY: REGION: 1 |NOTIFICATION TIME: 13:10 [ET]| | COUNTY: STATE: MD |EVENT DATE: 08/19/98 | |LICENSE#: MD-3102503 AGREEMENT: Y |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 08/19/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES NOGGLE RDO | | |JOSEPHINE PICCONE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: RAY MANLEY | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE NOTIFICATION INVOLVING A POTENTIAL PERSONNEL OVEREXPOSURE | | WHILE USING A TELETHERAPY SOURCE | | | | THE MARYLAND DEPARTMENT OF THE ENVIRONMENT RADIOLOGICAL HEALTH SERVICES | | OFFICE WAS NOTIFIED BY NEUTRON PRODUCTS, INC., THAT ONE OF THEIR | | TELETHERAPY SERVICE ENGINEER'S THERMOLUMINESCENT DOSIMETERS (TLD) FOR THE | | MONTH OF JULY READ AN OVEREXPOSURE OF 7,078 mREM WHOLE BODY. THE SOURCE OF | | THE OVEREXPOSURE IS UNCLEAR AND UNDER INVESTIGATION AT THIS TIME. THERE | | ARE NO EXPECTED ADVERSE HEALTH CONSEQUENCES. THE LICENSEE HAS REMOVED THE | | ENGINEER FROM LICENSED ACTIVITIES PENDING THE OUTCOME OF THE INVESTIGATION. | | | | SEE THE HOO LOG FOR CONTACT INFORMATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34652 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 08/19/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 15:36 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 08/19/98 | +------------------------------------------------+EVENT TIME: 12:23[CDT]| |NRC NOTIFIED BY: JOHN WASHKO |LAST UPDATE DATE: 08/19/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 58 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNIT 1 WAS MANUALLY SCRAMMED DUE TO FEEDWATER LEVEL CONTROL PROBLEMS DURING | | FEEDWATER PUMP TESTING. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 1223 ON 08/19/98, A MANUAL SCRAM (REACTOR TRIP) WAS INITIATED DUE TO | | FEEDWATER/LEVEL CONTROL PROBLEMS. JUST PRIOR TO THE REACTOR TRIP, | | FEEDWATER PUMP TESTING WAS IN PROGRESS ON THE 1A TURBINE-DRIVEN REACTOR | | FEED PUMP. DURING THIS TESTING, PROBLEMS WERE ENCOUNTERED WITH AUTOMATIC | | LEVEL CONTROL, AND REACTOR WATER LEVEL BEGAN TO DECREASE. THE REACTOR | | OPERATOR ATTEMPTED TO OBTAIN MANUAL CONTROL OF FEEDWATER, BUT DURING THIS | | ATTEMPT, REACTOR LEVEL BEGAN TO RISE AND THE OPERATOR WAS UNABLE TO REGAIN | | LEVEL CONTROL. THE REACTOR OPERATOR THEN MANUALLY SCRAMMED THE REACTOR | | WHEN LEVEL WENT ABOVE THE PREDETERMINED LEVEL OF +50 INCHES. THIS | | PREDETERMINED SCRAM CONTINGENCY WAS DISCUSSED PRIOR TO THE LEVEL CONTROL | | TESTING. DURING THE SCRAM, REACTOR WATER LEVEL DROPPED TO APPROXIMATELY 0 | | INCHES DUE TO THE INITIAL SHRINK ON THE SCRAM. LEVEL CONTROL WAS | | REESTABLISHED BACK TO ITS NORMAL BAND. THE FEEDWATER/LEVEL CONTROL | | ANOMALIES ARE BEING INVESTIGATED AT THIS TIME. THE REMAINDER OF THE PLANT | | RESPONDED AS EXPECTED, WITH THE EXCEPTION THAT THE 1A STATOR WATER COOLING | | PUMP TRIPPED DURING THE ELECTRICAL BUS FAST TRANSFER FOLLOWING THE TRIP OF | | THE MAIN GENERATOR. THE 1B STATOR WATER COOLING PUMP AUTOSTARTED, AS | | EXPECTED, ON THE RESULTANT LOW SYSTEM FLOW. THIS TRIP IS ALSO BEING | | INVESTIGATED." | | | | UNIT 1 IS CURRENTLY STABLE AND IN HOT SHUTDOWN. ALL CONTROL RODS FULLY | | INSERTED, AND ALL ECCS EQUIPMENT IS OPERABLE. NO SAFETIES OF SRVs LIFTED | | AS A RESULT OF THE TRANSIENT. THE PREDETERMINED LEVEL OF +50 INCHES IS | | SLIGHTLY BELOW THE AUTOMATIC REACTOR SCRAM SETPOINT OF +55.5 INCHES. THE | | UNIT IS REMOVING DECAY HEAT VIA THE MAIN STEAMLINE DRAINS TO THE MAIN | | CONDENSER WITH FEEDWATER BEING SUPPLIED BY THE CRD PUMP. THE ELECTRICALLY | | OPERATED FEEDWATER PUMP IS AVAILABLE BUT NOT NEEDED DUE TO THE LOW DECAY | | HEAT. THE LICENSEE ANTICIPATES RESTART ON 08/20/98 PENDING RESOLUTION OF | | THE FEEDWATER CONTROL PROBLEM. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34653 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: USAF RADIOISOTOPE COMMITTEE |NOTIFICATION DATE: 08/19/98 | | CITY: KIRKLAND AFB REGION: 4 |NOTIFICATION TIME: 16:15 [ET]| | COUNTY: STATE: NM |EVENT DATE: 07/22/98 | |LICENSE#: 42-23539AF AGREEMENT: Y |EVENT TIME: : [MDT]| | DOCKET: 03028641 |LAST UPDATE DATE: 08/19/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PHIL HARRELL RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAJOR KRISTIN N. SWENSON | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAE2 20.2202(b)(2) EXCESSIVE RELEASE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL EXPOSURE OF WORKERS AT KIRKLAND AFB DUE TO TRITIUM RELEASE FROM | | DAMAGED RADIOLUMINESCENT EXIT SIGNS | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON JULY 22 1998, THE BIOENVIRONMENTAL ENGINEERING FLIGHT (BEF) WAS | | NOTIFIED OF A NUMBER OF POTENTIALLY RADIOLUMINESCENT EXIT SIGNS THAT WERE | | LEFT ON THE SITE OF THE FORMER USAF HOSPITAL THAT WAS RECENTLY DEMOLISHED. | | IN ACCORDANCE WITH KAFBI 40-201, BEF SURVEYED THE LOCATION AND DETERMINED | | THAT 27 OF THE SIGNS WERE INDEED RADIOLUMINESCENT. SEVEN OF THE SIGNS WERE | | APPARENTLY DAMAGED, AND [FOUR] HAD BROKEN TRITIUM TUBES." | | | | THE LICENSEE TOOK PROMPT CORRECTIVE ACTION TO ISOLATE THE DAMAGED SIGNS AND | | ISSUED A TECHNICAL REPORT DESCRIBING THE SOURCES AND POTENTIAL DOSES | | RECEIVED BY WORKERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34654 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 08/19/98 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 18:55 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/19/98 | +------------------------------------------------+EVENT TIME: 17:13[EDT]| |NRC NOTIFIED BY: D. HARDIN |LAST UPDATE DATE: 08/19/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNITS EXPERIENCED A GROUP 6 ENGINEERED SAFEGUARDS FEATURE (ESF) | | ACTUATION DUE TO AN INVALID SIGNAL FROM A FAILED MAIN STACK RADIATION | | MONITOR. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "BRUNSWICK UNITS 1 AND 2 AT 1713 HOURS ON 8/19/98 RECEIVED AN INADVERTENT | | SECONDARY CONTAINMENT ISOLATION, CONTAINMENT ATMOSPHERIC CONTROL AND | | MONITORING SYSTEM ISOLATION, AND A STANDBY GAS SYSTEM INITIATION SIGNAL. | | THESE ACTUATIONS AND ISOLATIONS WERE DUE TO AN INVALID ACTUATION SIGNAL | | FROM A FAILED MAIN STACK RADIATION MONITOR. ALL SYSTEMS RESPONDED AS | | EXPECTED TO THE ISOLATION SIGNAL." | | | | "THE MAIN STACK RADIATION MONITOR SIGNAL WAS BYPASSED, AND THE ISOLATION | | AND ACTUATION SIGNALS WERE RESET. THE REACTOR BUILDING VENTILATION SYSTEM, | | STANDBY GAS, AND CONTAINMENT ATMOSPHERIC CONTROL AND MONITORING SYSTEMS | | WERE RETURNED TO THEIR NORMAL LINEUPS. AUXILIARY SAMPLING EQUIPMENT IS | | BEING SENT UP IN ACCORDANCE WITH THE TECHNICAL SPECIFICATIONS AND THE | | OFFSITE DOSE CALCULATION MANUAL (ODCM)." | | | | "THIS EVENT HAD MINIMAL SAFETY SIGNIFICANCE DUE TO BEING THE RESULT OF AN | | INVALID SIGNAL AND DUE TO THE FACT THAT ALL SYSTEMS RESPONDED AS DESIGNED." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT #34643. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34655 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/19/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 18:55 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/19/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/19/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN JACOBSON RDO | | DOCKET: 0707002 |JOHN GREEVES EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: RICK LARSON | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4-HOUR 91-01 NRC BULLETIN REPORT INVOLVING UNANALYZED CONDITION DISCOVERED | | DURING URANIUM OXIDE RECLAMATION | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "ON 08/19/98 AT 1500 HOURS, DURING THE COOLDOWN PHASE FOR THE #2 CALCINER, | | AN OPERATIONS OPERATOR DISCOVERED A POWDER/GRANULAR SUBSTANCE AND GREASE | | MIXTURE ON A FLANGE SURFACE OF THE MACHINE. EVALUATIONS OF THE SUBSTANCE | | INDICATED URANIUM OXIDE. NUCLEAR CRITICALITY SAFETY PERSONNEL WERE | | CONTACTED FOR NCSA CONCERNS. AT APPROXIMATELY 1700 HOURS, IT WAS | | DETERMINED THAT THE NUCLEAR CRITICALITY SAFETY EVALUATION (NCSE | | 706_024.001) WAS DEFICIENT IN NOT EVALUATING THIS CONDITION. THIS IS AN | | UNANALYZED EVENT. THE MACHINE IS IN A CONTROLLED SHUTDOWN UNDER GUIDANCE OF | | NCS." | | | | "THERE WAS NO LOSS OF HAZARDOUS RADIOACTIVE MATERIAL OR | | RADIOLOGICAL/RADIOACTIVE CONTAMINATION AS A RESULT OF THIS EVENT." | | | | OPERATIONS DOES NOT EXPECT TO RESUME CALCINER OPERATIONS FOR APPROXIMATELY | | A MONTH DUE TO THE RIGOROUS ANALYSIS REQUIRED FOR CRITICALITY CONCERNS. | | DURING THIS PERIOD OF TIME, MAINTENANCE ACTIVITIES MAY BE AFFECTED. | | HOWEVER, OPERATIONS WILL CONTINUE PRODUCTION WORK. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND DOE SITE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34656 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 08/19/98 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 19:55 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 08/19/98 | +------------------------------------------------+EVENT TIME: 19:30[EDT]| |NRC NOTIFIED BY: ED BURCHFIELD |LAST UPDATE DATE: 08/19/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE IS MAKING A 1-HOUR REPORT PER 10CFR50.72(b)(1)(ii)(B) FOR | | UNITS 2 AND 3, AND A 4-HOUR REPORT PER 10CFR50.72(b)(2)(i) FOR UNIT 1 | | INVOLVING THE LICENSING BASIS ASSUMPTIONS OF CONTAINMENT OVERPRESSURE | | DURING AN ACCIDENT. | | | | THE FOLLOWING IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON AUGUST 19, 1998, AT 1930 HOURS, WE CONSERVATIVELY DETERMINED THAT | | CREDITING CONTAINMENT OVERPRESSURE WHEN CALCULATING THE AVAILABLE NPSH FOR | | THE REACTOR BUILDING SPRAY (RBS) PUMPS IS NOT CONSISTENT WITH THE SYSTEM | | DESIGN BASIS. | | | | "GENERIC LETTER 97-04 REQUESTED LICENSEE SUBMIT INFORMATION NECESSARY TO | | CONFIRM THE ADEQUACY OF THE NPSH AVAILABLE FOR EMERGENCY CORE COOLING | | (INCLUDING CORE SPRAY AND DECAY HEAT REMOVAL) AND CONTAINMENT HEAT REMOVAL | | PUMPS. ON JANUARY 5, 1998, THE REQUESTED INFORMATION FOR OCONEE NUCLEAR | | STATION, UNIT NOS. 1, 2, AND 3 WAS SUBMITTED. IN THE SUBMITTAL, WE STATED | | 'THE CURRENT DESIGN BASIS NPSH ANALYSIS IS DIFFERENT FROM THAT REVIEWED AND | | APPROVED BY THE NRC.' ADDITIONALLY WE IDENTIFIED THAT CONTAINMENT | | OVERPRESSURE WAS CREDITED IN THE CALCULATION OF AVAILABLE NPSH. ON AUGUST | | 11, 1998, THE NRC ISSUED A REQUEST FOR ADDITIONAL INFORMATION RELATED TO | | GENERIC LETTER 97-04. IN THEIR LETTER, THE NRC STATED THEY WERE CONCERNED | | THAT OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3, MAY NOT BE WITHIN THEIR | | LICENSING BASIS BECAUSE IT APPEARED THAT THE CONTAINMENT OVERPRESSURE | | NEEDED TO ASSURE NPSH IS GREATER THAN THE OVERPRESSURE PREVIOUSLY APPROVED | | BY THE NRC STAFF. IN RESPONSE TO THIS CONCERN, WE REVIEWED OUR POSITION | | WITH RESPECT TO THE CREDITING OF CONTAINMENT OVERPRESSURE TO ASSURE | | ADEQUATE NPSH FOR THE RBS PUMPS. | | | | "IN 1996, THE UFSAR WAS REVISED TO INCORPORATE AN UPDATED RBS NPSH | | CALCULATION. THIS CALCULATION ADDRESSED A NUMBER OF NON-CONSERVATIVE | | ASSUMPTIONS THAT WERE CONTAINED IN THE ORIGINAL CALCULATION, INCLUDING A | | MORE CONSERVATIVE BREAK LOCATION, INSTRUMENT UNCERTAINTIES, AND A LOWER | | POST-ACCIDENT WATER LEVEL IN THE REACTOR BUILDING. AS A RESULT, IT WAS | | NECESSARY TO CREDIT CONTAINMENT OVERPRESSURE TO ENSURE ADEQUATE NPSH FOR | | THE RBS PUMPS. THE 10CFR50.59 EVALUATION WHICH SUPPORTED THE INCORPORATION | | OF THE REVISED ANALYSIS INTO THE UFSAR CONCLUDED THAT THE REVISED ANALYSIS | | DID NOT INVOLVE AN UNREVIEWED SAFETY QUESTION. | | | | "THE RATIONALE FOR THIS CONCLUSION WAS: | | | | "1. THE CONTAINMENT OVERPRESSURE REQUIRED TO ASSURE ADEQUATE NPSH FOR THE | | RBS PUMPS IS LESS THAN THE MINIMUM PREDICTED CONTAINMENT PRESSURE BASED ON | | CONSERVATIVE CONTAINMENT ANALYSES. | | | | "2. WE BELIEVED THAT THE PRECEDENT HAS BEEN SET TO UTILIZE CONTAINMENT | | OVERPRESSURE IF NEEDED TO ASSURE ADEQUATE NPSH. THIS BELIEF WAS BASED ON | | THE FACT THAT THE ORIGINAL FSAR CONTAINED A SUMMARY OF AN NPSH ANALYSIS | | WHICH ADDRESSED CASES WITH CONTAINMENT OVERPRESSURE ASSUMED AND CASES | | WITHOUT OVERPRESSURE ASSUMED. THE ORIGINAL SER STATES 'IN ALL CASES FOR | | THE LOW PRESSURE INJECTION PUMPS, THE AVAILABLE NPSH EXCEEDED THE REQUIRED | | NPSH FOR THE WORST CASE ASSUMPTIONS OF MAXIMUM SUMP TEMPERATURE AND NO | | CREDIT FOR BUILDING PRESSURE.' HOWEVER, THIS SER IS SILENT WITH RESPECT TO | | WHETHER OR NOT OVERPRESSURE WAS CREDITED IN THE REVIEW OF THE RBS NPSH | | MARGIN CALCULATIONS. IN ADDITION, OCONEE UNITS 1, 2, AND 3 WERE NOT | | LICENSED TO REGULATORY GUIDE 1.1. THUS , ONE COULD REASONABLY CONCLUDE | | THAT THE ORIGINAL LICENSING OF THE PLANT CONTEMPLATED CREDIT FOR | | OVERPRESSURE FOR THE RBS PUMPS. | | | | "DUKE HAS REVIEWED THE NRC's CONCERN AS DESCRIBED IN THEIR AUGUST 11, 1998, | | LETTER. IT APPEARS THE NRC BELIEVES THAT THE THOUGHT PROCESS USED IN THE | | ORIGINAL LICENSING OF THE PLANT 25 YEARS AGO WAS BASED ON AN ASSUMPTION | | THAT THE AVAILABLE NPSH FOR THE RBS PUMPS SHOULD NOT RELY UPON CONTAINMENT | | OVERPRESSURE. ASSUMING THIS TO BE TRUE, THIS DIFFERENCE IN THE STAFF'S | | POSITION AS COMPARED TO OCONEE'S UNDERSTANDING OF THE ORIGINAL SER LED US | | TO CONCLUDE THAT THE RESULTS OF THE PREVIOUS 10CFR50.59 EVALUATION WOULD BE | | DIFFERENT IF THE STAFF'S PERSPECTIVE ON CREDIT FOR CONTAINMENT OVERPRESSURE | | IS CONSIDERED. THUS, WE HAVE CONSERVATIVELY CONCLUDED THAT THE AVAILABLE | | NPSH FOR THE RBS PUMPS IS NOT CONSISTENT WITH THE ORIGINAL SAFETY | | EVALUATION REPORT AND POTENTIALLY INVOLVES AN USQ AND A CONDITION OUTSIDE | | THE DESIGN BASIS OF THE PLANT THAT SHOULD BE REPORTED UNDER 10CFR50.72. | | NOTE THAT THE LPI AND HPI PUMPS DO NOT RELY UPON CONTAINMENT OVERPRESSURE | | FOR AVAILABLE NPSH. THEREFORE, THIS REPORT IS ISOLATED TO THE RBS SYSTEM. | | | | "THE SAFETY SIGNIFICANCE OF THIS CONDITION IS MINIMAL, BECAUSE, GIVEN | | CONTAINMENT OVERPRESSURE, THE RBS PUMPS CONTINUE TO BE CAPABLE OF | | PERFORMING THEIR INTENDED SAFETY FUNCTION IF REQUIRED. OCONEE HAS | | COMPLETED AN OPERABILITY ANALYSIS USING CONSERVATIVE ASSUMPTIONS AND | | BOUNDING CONTAINMENT ANALYSES WHICH DEMONSTRATE THAT OVERPRESSURE WILL BE | | AVAILABLE AND THE RBS SYSTEM IS OPERABLE. ADDITIONALLY, A LICENSE | | AMENDMENT REQUEST WILL BE SUBMITTED TO RESOLVE THIS ISSUE. | | | | "ADDITIONAL INFORMATION WILL BE PROVIDED IN THE LICENSEE EVENT REPORT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34657 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 08/19/98 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 20:07 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/19/98 | +------------------------------------------------+EVENT TIME: 16:00[CDT]| |NRC NOTIFIED BY: JOHN CARLSON |LAST UPDATE DATE: 08/19/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM DECLARED INOPERABLE DUE TO LOW | | MEASURED PUMP DIFFERENTIAL PRESSURE (D/P) DURING QUARTERLY IN-SERVICE TEST. | | | | TECHNICAL SPECIFICATION REQUIRES THAT THE IN-SERVICE TEST (IST) MEASURED | | HPCS PUMP D/P BE AT LEAST 415 PSID. THE LICENSEE AFTER REVIEWING AN ISSUE | | AT GRAND GULF ESTABLISHED A HIGHER ADMINISTRATIVE LIMIT OF 418.5 PSID. | | DURING THE IST, THE MEASURED D/P WAS 418 PSID. THE HPCS SYSTEM WAS | | DECLARED INOPERABLE WHICH PLACED THE UNIT IN A 14-DAY LCO ACTION STATEMENT. | | THE ENGINEERING DEPARTMENT IS CURRENTLY REVIEWING THE ADMINISTRATIVE LIMIT | | TO DETERMINE WHETHER THE HIGHER D/P IS OVERLY CONSERVATIVE, IN WHICH CASE, | | THE UNIT CAN EXIT THE LCO. THIS REVIEW SHOULD BE COMPLETED WITHIN THE NEXT | | COUPLE OF HOURS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34658 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 08/20/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 02:04 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/19/98 | +------------------------------------------------+EVENT TIME: 23:10[CDT]| |NRC NOTIFIED BY: TIM HOLLAND |LAST UPDATE DATE: 08/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - ESF ACTUATION DURING A TEST DUE TO APPARENT PROCEDURE INADEQUACY - | | | | WITH THE PLANT IN CONDITION 4 (COLD SHUTDOWN) IN A REFUELING OUTAGE, | | THE LICENSEE WAS PERFORMING AN INTEGRATED #1C EMERGENCY DIESEL GENERATOR | | (EDG) - EMERGENCY CORE COOLING SYSTEM TECH SPEC SURVEILLANCE TEST. | | | | THE TEST PROCEDURE STEPS PERMITTED THE RESETTING OF THE 86 #1C EDG LOCKOUT | | RELAYS PRIOR TO RESETTING THE HIGH PRESSURE CORE SPRAY (HPCS) SYSTEM | | INITIATION SIGNAL. THIS RESULTED IN AN AUTOMATIC START OF THE #1C EDG, | | AN UNPLANNED ENGINEERED SAFETY FEATURES (ESF) ACTUATION WITH A VALID HPCS | | SYSTEM INITIATION SIGNAL. | | | | THE LICENSEE STOPPED THE #1C EDG AND RESET THE ESF ACTUATION SIGNAL. | | | | THE LICENSEE IS EVALUATING THE TEST PROCEDURE AND WILL MAKE NECESSARY | | REVISIONS. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34659 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEABROOK REGION: 1 |NOTIFICATION DATE: 08/20/98 | |UNIT: [1] [ ] [ ] STATE: NH |NOTIFICATION TIME: 03:31 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/20/98 | +------------------------------------------------+EVENT TIME: 01:08[EDT]| |NRC NOTIFIED BY: RON STRICKLAND |LAST UPDATE DATE: 08/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - DEAD SEAL RECOVERED FROM THE PLANT SERVICE WATER INTAKE SCREEN - | | | | IN ACCORDANCE WITH THE PLANT OPERATING LICENSE, APPENDIX 'B', SECTION 4.1, | | ENVIRONMENTAL PROTECTION PLAN, THE LICENSEE REPORTED TO THE NATIONAL MARINE | | FISHERIES SERVICE AND THE NEW ENGLAND AQUARIUM THAT THEY RECOVERED A DEAD | | SEAL FROM THE PLANT SERVICE WATER INTAKE SCREEN. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34660 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 08/20/98 | |UNIT: [ ] [3] [ ] STATE: PA |NOTIFICATION TIME: 03:49 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 08/20/98 | +------------------------------------------------+EVENT TIME: 02:00[EDT]| |NRC NOTIFIED BY: KEVIN PATEK |LAST UPDATE DATE: 08/20/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES NOGGLE 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 +------------------------------------------------------------------------------+ | - RWCU SYSTEM AUTO ISOLATED DUE TO A HIGH FLOW CONDITION (ESF ACTUATION) - | | | | WHILE PLACING 1 OF 2 REACTOR WATER CLEANUP (RWCU) SYSTEM DEMINERALIZERS | | IN SERVICE FOLLOWING MAINTENANCE ACTIVITIES, THE RWCU SYSTEM AUTOMATICALLY | | ISOLATED DUE TO A HIGH FLOW CONDITION. THIS ISOLATION CONSTITUTES A | | PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 2 ENGINEERED SAFETY FEATURES | | (ESF) ACTUATION. | | | | THE LICENSEE RESET THE ESF ACTUATION AND RESTORED THE RWCU SYSTEM TO | | OPERABLE STATUS. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+