U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/15/98 - 09/16/98 ** EVENT NUMBERS ** 33176 34741 34742 34772 34773 34774 34775 34776 34777 34778 34779 34780 34781 34782 34783 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33176 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WOLF CREEK REGION: 4 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [ ] [ ] STATE: KS |NOTIFICATION TIME: 13:53 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 08:00[CST]| |NRC NOTIFIED BY: JENNIFER YUNK |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "CURRENT WESTINGHOUSE NRC APPROVED METHODOLOGY FOR DETERMINATION OF FUEL | | ROD INTERNAL PRESSURE AND CLADDING CORROSION WAS FOUND TO BE NOT AS | | CONSERVATIVE AS PREVIOUSLY BELIEVED. AS A RESULT, CALCULATION OF | | 10CFR50.46 ECCS ACCEPTANCE CRITERIA MAY BE AFFECTED. THE MAGNITUDE OF THIS | | EFFECT HAS NOT BEEN SPECIFICALLY CALCULATED FOR WOLF CREEK. THIS | | DETERMINATION IS BASED ON NEWER MODELS STILL UNDER DEVELOPMENT BY | | WESTINGHOUSE. THE NEWER MODELS ARE BELIEVED BY WESTINGHOUSE TO MORE | | ACCURATELY PREDICT FUEL CLADDING BEHAVIOR. THE EFFECT OF THIS EVALUATION | | IS TO SHOW THAT POTENTIALLY FOR LBLOCA, THE 17% CLADDING OXIDATION | | REQUIREMENT OF 10CFR50.46 MAY NOT BE MET FOR CERTAIN LIMITING FUEL RODS | | CONTAINING INTEGRAL FUEL BURNABLE ABSORBER (IFBA). THESE GENERIC | | EVALUATIONS INDICATE THAT IFBA RODS COULD EXPERIENCE GAP RE-OPENING | | SOMETIME IN THE SECOND HALF OF THEIR SECOND CYCLE OF OPERATION UNDER THE | | MOST DEMANDING PLANT CONDITIONS. WOLF CREEK HAS OPERATED ONE CYCLE WITH | | IFBA RODS. 'BEST ESTIMATE' CALCULATIONS PERFORMED BY WESTINGHOUSE INDICATE | | THAT GAP RE-OPENING MAY NOT NECESSARILY OCCUR, EVEN FOR THE MOST LIMITING | | FUEL ROD IN THE MOST LIMITING PLANT." | | | | "WESTINGHOUSE HAS CONSERVATIVELY EVALUATED THE POSSIBILITY OF GAP REOPENING | | AND CONCLUDED IT DOES NOT REPRESENT A SUBSTANTIAL SAFETY HAZARD. | | WESTINGHOUSE CONCLUDES THAT A PLANT COULD BE SHUTDOWN SAFELY, SINCE PLANT | | CONTROL MECHANISMS WOULD FUNCTION PROPERLY AND A COOLABLE GEOMETRY WOULD BE | | MAINTAINED TO THE EXTENT REQUIRED FOR DESIGN BASIS ACCIDENTS. IN ADDITION, | | 10CFR100 LIMITS FOR OFFSITE DOSE WOULD NOT BE EXCEEDED IN ANY POSTULATED | | EVENT." | | | | "WESTINGHOUSE HAS NOTIFIED THE NRC OF THIS ISSUE AND IS CURRENTLY | | ADDRESSING FUEL PERFORMANCE ANALYSIS METHODOLOGY TO REFINE THEIR MODEL AND | | RESOLVE THIS ISSUE. WESTINGHOUSE HAS ALSO DETERMINED THAT THIS ISSUE IS | | NOT REPORTABLE PER 10CRF21 REQUIREMENTS. WOLF CREEK IS MAKING THIS | | VOLUNTARY REPORT BECAUSE THIS ISSUE MIGHT BE OF GENERIC INTEREST OR | | CONCERN." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | *** UPDATE ON 09/15/98 @ 1357 EDT FROM AUSTIN TO GOULD *** | | | | IN 1996, WESTINGHOUSE DETERMINED THAT THE EXISTING MODELS FOR CLAD | | OXIDATION OF THE ZIRCALOY-4 CLADDING, HELIUM RELEASE AND THE INTEGRATED | | FUEL BURNABLE ABSORBER COATED FUEL PELLETS MAY NOT BE CONSERVATIVE. AFTER | | INCORPORATING THIS DATA INTO A BOUNDING GENERIC ANALYSIS, WESTINGHOUSE | | DETERMINED THAT THE PELLET CLAD GAP MAY REOPEN FOR HIGH DUTY INTEGRATED | | FUEL BURNABLE ABSORBER RODS AS EARLY AS THE SECOND HALF OF THEIR SECOND | | DUTY CYCLE. WESTINGHOUSE HAS INFORMED WOLF CREEK NUCLEAR OPERATING | | CORPORATION THAT BASED ON THE WOLF CREEK GENERATING STATION PLANT SPECIFIC | | ANALYSIS, THE GAP REOPENING IS EXPECTED TO OCCUR IN CYCLE 10. WITH | | CONTINUED FULL POWER OPERATION, THE BURNUP CORRESPONDING TO GAP REOPENING | | WILL OCCUR ON OR ABOUT 10/18/98. HOWEVER, THE PLANT SPECIFIC ANALYSIS | | DEMONSTRATES THAT THE 17% TOTAL LOCALIZED OXIDATION LIMIT SPECIFIED IN | | 10CFR50.46 CONTINUES TO BE MET. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R4DO (MURRAY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34741 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 09/05/98 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 17:55 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/05/98 | +------------------------------------------------+EVENT TIME: 15:53[EDT]| |NRC NOTIFIED BY: BILL WOODBURY |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PIERCE SKINNER 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | High Pressure Coolant Injection (HPCI) Declared Inoperable | | | | On 09/05/98, the HPCI system was declared inoperable due to a through-wall | | leak on an instrument line for the system flow measurement orifice. The | | leak is located on a threaded connection and measures approximately 0.25" | | long. The leak was discovered while looking for leaks (leak tightness | | inspection) during quarterly operational surveillance testing of the HPCI | | system. The leak rate is 0.125 gpm when HPCI is operating and 60 drops/min | | when HPCI is not operating. HPCI was declared inoperable and a 14-day | | limiting condition of operation was entered for HPCI per Technical | | Specification 3.5. All other emergency core cooling systems and the RCIC | | system are fully operable if needed. The leak will be repaired and system | | testing completed prior to restoring the HPCI system to an operable status. | | | | The NRC resident inspector was notified of this event by the licensee. | | | | * * * Update at 1453 on 09/15/98 from Glen Thearling to Trocine * * * | | | | The licensee is retracting this event notification because the leak was | | determineed to be from the threads of the fitting rather than through wall. | | | | The licensee plans to notify the NRC resident inspector. The NRC | | operations officer notified the R2DO (Julian). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34742 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/05/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 20:35 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/05/98 | +------------------------------------------------+EVENT TIME: 19:45[EDT]| |NRC NOTIFIED BY: J. FREEMAN |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID LEW RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Technical Specification Shutdown Entered Due to the 'B' Isolation Condenser | | Being Isolated and Declared Inoperable. | | | | At 2030 EDT, a plant shutdown was initiated due to the 'B' isolation | | condenser being declared inoperable. The 'B' isolation condenser has | | indication of a tube leak, and it has been isolated. The isolation | | condenser will not be repaired prior to the end of the 7-day limiting | | condition for operation (LCO) (Technical Specification 3.8). Therefore, | | Oyster Creek is required to be in Cold Shutdown within the next 30 hours. | | There was no release, and the 'B' isolation condenser tube bundle will be | | replaced. All other emergency core cooling systems and the emergency | | diesel generators are fully operable if needed. | | | | The NRC resident inspector was be notified of this event by the licensee. | | | | * * * Update at 0503 on 09/07/98 from Mike McKenna to Jolliffe * * * | | | | The licensee determined by water chemistry samples that no tube leak exists | | on the 'B' isolation condenser. Thus, at 0230 on 09/06/98, the licensee | | declared the 'B' isolation condenser operable, exited the action statement | | for Technical Specification 3.8, and stopped the power reduction at 65% | | power. | | | | The licensee notified the NRC resident inspector. The NRC operations | | officer notified the R1DO (Dave Lew). | | | | * * * Update at 1449 on 09/15/98 from David Pietruski to Trocine * * * | | | | The following text is a portion of a facsimile received from the licensee: | | | | "On 09/06/98 at 1428 EDT, Oyster Creek Nuclear Generating Station | | terminated the plant shutdown that had commenced on 09/05/98 at 2030 EDT | | (as described above) and resumed full power operations. The plant had | | commenced a shutdown due to an isolation condenser being declared | | inoperable and recognizing that the postulated repairs could not be | | completed prior to expiration of the LCO clock. Subsequent reviews of the | | data revealed that the original information which was used as the bases for | | declaring the condenser inoperable was erroneous." | | | | The licensee notified the NRC resident inspector. The NRC operations | | officer notified the R1DO (Dan Holody). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34772 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GINNA REGION: 1 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 04:44 [ET]| |RX TYPE: [1] W-2-LP |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 00:51[EDT]| |NRC NOTIFIED BY: ROY GILLOW |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION SHIFTED TO RECIRC MODE DUE TO AN INCREASE IN RADON | | CAUSED BY A TEMPERATURE INVERSION. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT 0051 EDT, CONTROL ROOM VENTILATION WENT INTO RECIRC MODE DUE TO A | | SIGNAL FROM R-37 (CONTROL ROOM PARTICULATE RADIATION MONITOR). ALL SYSTEM | | FANS AND DAMPERS OPERATED AS EXPECTED. RADIATION PROTECTION PERSONNEL TOOK | | AIR SAMPLES FROM [THE] TURBINE BUILDING. ANALYSIS OF SAMPLES DETERMINED | | THAT ACTIVITY PRESENT WAS FROM NATURALLY OCCURRING SOURCES SUCH AS RADON | | AND RADON DECAY PRODUCTS." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | HOO NOTE: THIS ALSO OCCURRED ON 09/04/98 - SEE EVENT #34735. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34773 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 11:59 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 11:30[EDT]| |NRC NOTIFIED BY: PIETRUSKI |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE DISCOVERED A DRAIN LINE ON THE PLANT'S CONTAINMENT SPRAY SYSTEM | | DID NOT MEET ANSI PIPING STANDARD B.31.1. | | | | AS A RESULT OF ADDITIONAL ENGINEERING STUDIES REGARDING THE CAPABILITY OF | | SMALL BORE PIPING TO MEET ALLOWABLE PIPE STRESS CRITERIA, IT WAS DISCOVERED | | THAT A DRAIN LINE ON THE PLANT'S CONTAINMENT SPRAY SYSTEM DID NOT MEET THE | | REQUIREMENTS OF ANSI PIPING STANDARD B.31.1 AS REQUIRED BY THE PLANT'S | | LICENSING BASES. THEIR ANALYSIS, HOWEVER, HAS DETERMINED THAT THIS PIPING | | MEETS ASME SECTION III, APPENDIX F, THEREBY SUPPORTING CONTINUED | | OPERABILITY. APPROPRIATE CORRECTIVE ACTIONS (MODIFICATIONS), WHEN | | DETERMINED, WILL BE COMPLETED DURING THE UPCOMING OUTAGE WHICH IS SCHEDULED | | TO COMMENCE ON 09/26/98. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34774 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 13:12 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 09:30[EDT]| |NRC NOTIFIED BY: VINCENT FALLACARA |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY 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 +------------------------------------------------------------------------------+ | BLOWN CONTROL LOGIC FUSE AND INOPERABLE PRESSURE TRANSMITTER DUE TO HUMAN | | ERROR DURING HIGH PRESSURE COOLANT INJECTION (HPCI) HIGH FLOW LOGIC TESTING | | | | DURING THE PERFORMANCE OF A HPCI HIGH FLOW LOGIC TEST, A POWER SURGE CAUSED | | A FUSE IN THE CONTROL LOGIC TO BLOW AND CAUSED A PRESSURE TRANSMITTING | | SWITCH TO BECOME INOPERABLE. THE POWER SURGE IS CURRENTLY BELIEVED TO HAVE | | BEEN CAUSED BY HUMAN ERROR, BUT THIS IS STILL UNDER INVESTIGATION. | | | | THE HPCI SYSTEM WAS TAKEN OUT OF SERVICE FOR PERFORMANCE OF THIS | | SURVEILLANCE TEST. AS A RESULT OF THIS INCIDENT, THE UNIT WILL REMAIN IN | | THE APPLICABLE 14-DAY LIMITING CONDITION FOR OPERATION UNTIL THE HPCI | | SYSTEM HAS BEEN RETURNED TO SERVICE. ALL OTHER EMERGENCY CORE COOLING | | SYSTEMS ARE OPERABLE AND AVAILABLE IF NEEDED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34775 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ENVIRO CARE OF UTAH |NOTIFICATION DATE: 09/15/98 | | CITY: CLIVE REGION: 4 |NOTIFICATION TIME: 14:11 [ET]| | COUNTY: TOOELE STATE: UT |EVENT DATE: 09/15/98 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 12:15[MDT]| | DOCKET: |LAST UPDATE DATE: 09/15/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BLAINE MURRAY RDO | | |DON COOL, NMSS EO | +------------------------------------------------+JOSEPH GIITTER, AEOD IRD | |NRC NOTIFIED BY: GAUTHIER(NAT RES CTR) | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER REPORTED A RADIOACTIVE SPILL OCCURRED AT THE | | ENVIRO CARE OF UTAH RADIOACTIVE DISPOSAL FACILITY. | | | | RADIOACTIVE WASTE BEING TRANSPORTED (BY R&R TRUCKING INC.) TO THE ENVIRO | | CARE FACILITY HAD A SMALL LEAK IN ONE OF THE 55-GALLON DRUMS ON THE TRAILER | | DUE TO A SEAL BREACH WHICH RESULTED IN LESS THAN 1 CUP SPILLING ONTO THE | | TRAILER'S FLOOR. THEY SURVEYED THE MATERIAL, ISOLATED THE DRUM, AND | | SECURED THE SPILL. THE REGIONAL ENVIRONMENTAL PROTECTION AGENCY (EPA) WAS | | NOTIFIED BY NATIONAL RESPONSE CENTER; AND THEY WILL ALSO NOTIFY EPA RAD, | | DEPARTMENT OF ENERGY, AND CENTER FOR DISEASE CONTROL. | | | | ABB NUCLEAR FUELS, THE SHIPPER, WAS CONTACTED, AND STATED THAT THE SHIPMENT | | WAS SOLIDIFIED FILTRATE (A CLAY-TYPE MATERIAL) URANIUM WITH A LOW ACTIVITY | | (1,000 PICOCURIES/GM) MEASURING 50 DPM ON A SMEAR OF THE TRAILER. (REFER TO | | THE HOO LOG FOR A CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34776 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SAN ONOFRE REGION: 4 |NOTIFICATION DATE: 09/15/98 | |UNIT: [ ] [2] [3] STATE: CA |NOTIFICATION TIME: 14:19 [ET]| |RX TYPE: [1] W-3-LP,[2] CE,[3] CE |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 09:55[PDT]| |NRC NOTIFIED BY: WILLIAMS |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY 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 DETERMINED THE PROCESS MONITORING SYSTEM DOES NOT MEET THE | | UFSAR DESIGN BASIS. | | | | UFSAR SECTION 11.5, "PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND | | SAMPLING SYSTEMS," SUB SECTION 11.5.1.1, "DESIGN BASES - PROCESS MONITORING | | SYSTEMS," STATES THE SYSTEM WILL: "PROVIDE CONTINUOUS REMOTE INDICATION AND | | RECORDING OF AIRBORNE RADIOACTIVE CONTAMINATION IN THE FORM OF PARTICULATES | | AND IODINES IN AREAS WHERE PERSONNEL NORMALLY HAVE ACCESS." THE EXISTING | | PROCESS MONITORING SYSTEM, HOWEVER, DOES NOT CURRENTLY INCLUDE CONTINUOUS | | PARTICULATE AND IODINE MONITORING TO DETERMINE RADIOACTIVE CONTAMINATION IN | | AREAS WHERE PERSONNEL NORMALLY HAVE ACCESS. | | | | THIS UFSAR REFERENCES REG GUIDE 8.8, "INFORMATION RELEVANT TO ENSURING THAT | | OCCUPATIONAL RADIATION EXPOSURES AT NUCLEAR POWER STATIONS WILL BE AS LOW | | AS IS REASONABLY ACHIEVABLE," AND ONE OF THE "ALARA" PROGRAM OBJECTIVES IN | | THIS REGULATORY GUIDE IS ON RADIATION MONITORING SYSTEMS. | | | | COMPLIANCE WITH THE OCCUPATIONAL EXPOSURE LEVELS IN 10 CFR PART 20 IS | | PERFORMED USING ROUTINE AIRBORNE RADIOACTIVITY SURVEYS AND JOB-SPECIFIC | | AIRBORNE RADIOACTIVITY SAMPLING. THE LICENSEE BELIEVES THIS CONDITION HAS | | NO SAFETY SIGNIFICANCE, AND THE EXISTING PERSONNEL LEVELS ARE WELL BELOW | | NRC REGULATORY LIMITS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34777 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 15:36 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 13:45[CDT]| |NRC NOTIFIED BY: GREG JANAK |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE OF BOTH DEMAND STEP COUNTERS FOR CONTROL BANK 'D' TO OPERATE AS | | EXPECTED DURING THE PERFORMANCE OF MAINTENANCE | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON SEPTEMBER 9, 1998, AT 1558 HOURS, UNIT 1 ENTERED [TECHNICAL | | SPECIFICATION] 3.0.3 DUE TO PERFORMING MAINTENANCE ON THE ROD CONTROL PULSE | | TO ANALOG CONVERTER. DURING THIS MAINTENANCE, BOTH DEMAND STEP COUNTERS | | FOR CONTROL BANK 'D' DID NOT OPERATE AS EXPECTED. THIS VIOLATED [TECHNICAL | | SPECIFICATION] 3.1.3.2.b WHICH STATES THAT A MAXIMUM OF ONE DEMAND POSITION | | INDICATOR PER BANK MAY BE INOPERABLE." | | | | "THE DEMAND STEP COUNTERS FOR CONTROL BANK 'D' WERE RETURNED TO AN OPERABLE | | STATUS ON SEPTEMBER 9, 1998, AT 1620 HOURS." | | | | "THIS EVENT IS BEING REPORTED UNDER 10 CFR 50.73(a)(2)(i)(B) WHICH | | REQUIRED THE LICENSEE TO REPORT ANY OPERATION OR CONDITION PROHIBITED BY | | THE PLANT'S TECHNICAL SPECIFICATIONS." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34778 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PEACH BOTTOM REGION: 1 |NOTIFICATION DATE: 09/15/98 | |UNIT: [2] [ ] [ ] STATE: PA |NOTIFICATION TIME: 15:54 [ET]| |RX TYPE: [2] GE-4,[3] GE-4 |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 14:03[EDT]| |NRC NOTIFIED BY: ED EILOLA |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY 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 Y 62 POWER OPERATION | 62 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ISOLATION OF THE REACTOR WATER CLEANUP SYSTEM DUE TO HIGH SYSTEM FLOW WHILE | | PRESSURIZING THE SYSTEM FOLLOWING MAINTENANCE | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THE UNIT 2 REACTOR WATER CLEANUP SYSTEM ISOLATED ON HIGH SYSTEM FLOW. THE | | HIGH SYSTEM FLOW OCCURRED WHILE PRESSURIZING THE SYSTEM FOLLOWING PLANNED | | MAINTENANCE IN ACCORDANCE WITH SYSTEM PROCEDURES. THE PLANT EFFECTS WERE | | AN ISOLATION (GROUP II) OF [UNIT 2] REACTOR WATER CLEANUP DUE TO HIGH FLOW, | | 125%. THE ISOLATION ACTUATED AS DESIGNED AND WENT TO COMPLETION. [THE | | LICENSEE] VERIFIED BY VISUAL OBSERVATION AND TEMPERATURE MONITORING THAT NO | | ACTUAL SYSTEM BREACH OCCURRED. AN INVESTIGATION INTO THE EVENT IS IN | | PROGRESS." | | | | THE LICENSEE STATED THAT THE ISOLATION SIGNAL HAS BEEN RESET BUT THAT THE | | REACTOR WATER CLEANUP SYSTEM WAS STILL ISOLATED AT THE TIME OF THIS | | NOTIFICATION. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34779 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: SCIENSKI |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 96 POWER OPERATION | 96 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DETERMINED THE HIGH PRESSURE TRIP EXCEEDED ITS TECHNICAL | | SPECIFICATION LIMIT FOR TIME DELAY ON THE ISOLATION CONDENSERS. | | | | THE TIME DELAY FOR THE HIGH PRESSURE TRIP EXCEEDED THE 3 SECOND (3.40 | | SECONDS) LIMIT FOR THE AS-FOUND VALUE. THE AS-LEFT VALUE WAS ADJUSTED AS | | REQUIRED TO WITHIN THE 3 SECOND (2.15 SECONDS) TECHNICAL SPECIFICATION TIME | | DELAY LIMIT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1742 ON 09/15/98 FROM STEVE FULLER TO TROCINE * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION REGARDING THE TIME DELAY | | SETTING OF A HIGH PRESSURE TRIP INSTRUMENT (ISOLATION CONDENSER AUTOMATIC | | INITIATION ON HIGH REACTOR PRESSURE). UPON FURTHER REVIEW OF THE ISOLATION | | CONDENSER AUTOMATIC INITIATION LOGIC, THE LICENSEE DETERMINED THAT THE | | INITIATION FUNCTION WAS STILL OPERABLE ON BOTH LOGIC CHANNELS EVEN THOUGH | | THE TIME DELAY SETTING ON ONE INSTRUMENT WAS OUTSIDE THE ESTABLISHED LIMIT. | | THEREFORE, THE LICENSEE BELIEVES THAT BOTH INSTRUMENT CHANNELS WERE | | OPERABLE AND THAT THIS EVENT WAS NOT REPORTABLE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R1DO (HOLODY). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34780 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DUANE ARNOLD REGION: 3 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: IA |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 14:07[CDT]| |NRC NOTIFIED BY: KEVIN STEIMER/DAVE EILERS |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS/REG 3 RDO | |NTRA TRANSPORTATION EVENT |JOSEPHINE PICCONE EO | | |DON COOL/NMSS EO | | |JOSEPH GIITTER/AEOD IRD | | |CAUDLE JULIAN/REG 2 RDO | | |RUTHERFORD (VIA NRC) DOT | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY OF REMOVABLE CONTAMINATION ABOVE DEPARTMENT OF TRANSPORTATION | | (DOT) LIMITS ON THE INSIDE IMPACT LIMITERS OF AN EMPTY SHIPPING CASK WHICH | | WAS RECEIVED BY THE LICENSEE ON 09/14/98 | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "INITIAL RECEIPT SURVEYS ON NRC TYPE 'B' SHIPPING CASK (NRC 9010) REVEALED | | CONTAMINATION LEVELS IN EXCESS OF 22,000 dpm/100cmý (DOT LIMIT). | | CONTAMINATION LEVELS OF APPROXIMATELY 40,000 dpm/100cmý WERE LOCATED ON THE | | THE INSIDE SURFACES OF THE IMPACT LIMITERS OF THE SHIPPING CASK. | | CONTAMINATION SURVEYS ON THE SHIPPING CASK EXTERNAL TO THE IMPACT LIMITERS | | WERE WITHIN DOT CONTAMINATION LIMITS. THE PACKAGE (SHIPPING CASK AND | | IMPACT LIMITERS) IS ENCLOSED BY A PERSONNEL BARRIER. NO DETECTABLE | | CONTAMINATION WAS FOUND ON THE EXTERNAL SURFACES OF THE PERSONNEL BARRIER. | | THE FINAL DELIVERY CARRIER HAS BEEN NOTIFIED OF THE SITUATION IN ACCORDANCE | | WITH 10CFR20.1906(d). THE CASK IS CURRENTLY IN THE PROCESS OF BEING | | DECONTAMINATED. AN ISOTOPIC ANALYSIS IS [ALSO] BEING PERFORMED ON THE | | SMEARS TO DETERMINE THE ISOTOPES PRESENT." | | | | "THIS IS CONSIDERED A 1-HOUR IMMEDIATE NOTIFICATION PURSUANT TO | | 10CFR20.1906(d)(1), 10CFR71.47, AND 49CFR173.443(d)." | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR, THE SHIPPER (FRANK W. | | HAKE AND ASSOCIATES LOCATED IN TENNESSEE), AND THE CARRIER (TRISTATE). | | (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34781 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 17:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 12:45[CDT]| |NRC NOTIFIED BY: GREG JANAK |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BLAINE MURRAY RDO | |NLTR LICENSEE 24 HR REPORT | | |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 +------------------------------------------------------------------------------+ | AUXILIARY FEEDWATER PUMP QUARTERLY SURVEILLANCE TEST NOT PERFORMED | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "DURING A SYSTEM ENGINEERING REVIEW OF SURVEILLANCES FOR AUXILIARY | | FEEDWATER PUMP #14, IT WAS DISCOVERED THAT THE QUARTERLY SURVEILLANCE | | SCHEDULED TO BE PERFORMED ON JULY 9, 1998, WAS NOT PERFORMED PER [TECHNICAL | | SPECIFICATION] 4.0.5. THIS SURVEILLANCE GRACE PERIOD ENDED ON AUGUST 7, | | 1998. THIS MAKES AUXILIARY FEEDWATER PUMP #14 INOPERABLE [AS OF THE] TIME | | OF DISCOVERY PER TECHNICAL SPECIFICATION 3.7.1.2, WHICH REQUIRES | | RESTORATION WITHIN 72 HOURS." | | | | THE MISSED SURVEILLANCE TEST WAS DISCOVERED AT 1245 CDT ON SEPTEMBER 15, | | 1998. AT THE TIME OF THIS EVENT NOTIFICATION, THE LICENSEE HAD COMPLETED | | THE REQUIRED SURVEILLANCE TESTING AND WAS IN THE PROCESS OF CLOSING OUT THE | | PAPERWORK PRIOR TO RESTORING THE PUMP TO OPERABLE STATUS. | | | | THE LICENSEE MADE THIS 24-HOUR EVENT NOTIFICATION IN ACCORDANCE WITH | | LICENSE NPF-076, SECTION 2G. THE LICENSEE ALSO PLANS TO SUBMIT AT 30-DAY | | LICENSEE EVENT REPORT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34782 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/15/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 18:10 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 17:35[EDT]| |NRC NOTIFIED BY: DALE BRODSKY |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY RDO | |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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | M/R Y 100 POWER OPERATION | 0 HOT STANDBY | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL REACTOR TRIP FROM 100% POWER BECAUSE OF HIGH CONDENSATE CONDUCTIVITY | | | | THE LICENSEE MANUALLY TRIPPED THE REACTOR FROM 100% POWER BECAUSE OF HIGH | | CONDUCTIVITY (GREATER THAN 1 æmho) IN THE CONDENSATE SYSTEM. ALL CONTROL | | RODS FULLY INSERTED, AND AUXILIARY FEEDWATER AUTOMATICALLY STARTED AS | | EXPECTED. ALL SYSTEMS FUNCTIONED AS REQUIRED, AND THERE WAS NOTHING THAT | | WAS UNUSUAL OR NOT UNDERSTOOD. | | | | THE LICENSEE CURRENTLY BELIEVES THAT THE HIGH CONDUCTIVITY MAY HAVE | | RESULTED FROM SALT WATER INTRUSION INTO THE CONDENSATE SYSTEM FROM THE | | BLOWDOWN SYSTEM, SINCE MANIPULATIONS OF THE BLOWDOWN SYSTEM WERE BEING | | PERFORMED AT THE TIME OF THE EVENT. THE CAUSE OF THIS EVENT IS STILL UNDER | | INVESTIGATION. | | | | THE UNIT IS CURRENTLY STABLE IN MODE 3. PRESSURIZER HEATERS AND SPRAYS, | | NORMAL CHARGING AND LETDOWN, AND THE REACTOR COOLANT PUMPS ARE BEING | | UTILIZED FOR PRIMARY SYSTEM PRESSURE, INVENTORY, AND TRANSPORT CONTROL. | | AUXILIARY FEEDWATER IS SUPPLYING WATER TO THE STEAM GENERATORS, AND | | SECONDARY STEAM IS BEING DUMPED TO THE CONDENSER. ALL EMERGENCY CORE | | COOLING SYSTEMS ARE CURRENTLY OPERABLE AND AVAILABLE WITH THE EXCEPTION OF | | ONE TRAIN OF HIGH HEAD SAFETY INJECTION WHICH IS OUT OF SERVICE FOR | | MAINTENANCE. BOTH EMERGENCY DIESEL GENERATORS ARE ALSO OPERABLE AND | | AVAILABLE IF NEEDED. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE APPLICABLE STATE | | AND LOCAL GOVERNMENT AGENCIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34783 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 09/15/98 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 18:35 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 09/15/98 | +------------------------------------------------+EVENT TIME: 18:00[EDT]| |NRC NOTIFIED BY: PHILIP RAINHA |LAST UPDATE DATE: 09/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAN HOLODY 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE OF A SPENT FUEL POOL COOLING SERVICE WATER SUPPLY CHECK VALVE TO | | MEET ITS SEAT LEAKAGE ACCEPTANCE CRITERIA DURING SURVEILLANCE TESTING | | | | A SPENT FUEL POOL COOLING SERVICE WATER SUPPLY CHECK VALVE (SW-CV-963) | | FAILED TO MEET ITS SEAT LEAKAGE ACCEPTANCE CRITERIA DURING MONTHLY | | SURVEILLANCE TESTING. THIS PLACED THE UNIT IN A LIMITING CONDITION FOR | | OPERATION (LCO) IN ACCORDANCE WITH TECHNICAL SPECIFICATION 3/4.9.15. THIS | | LCO REQUIRES THE LICENSEE SUSPEND ALL OPERATIONS INVOLVING THE ADDITION OF | | IRRADIATED FUEL TO THE SPENT FUEL POOL AND INITIATE CORRECTIVE ACTIONS TO | | RESTORE THE SPENT FUEL COOLING SYSTEM OPERABLE STATUS AS SOON AS POSSIBLE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR AND THE STATE OF | | CONNECTICUT. | +------------------------------------------------------------------------------+