U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/08/98 - 05/11/98 ** EVENT NUMBERS ** 34055 34062 34184 34191 34192 34193 34194 34195 34196 34197 34198 34199 34200 34201 34202 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34055 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 04/10/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 17:26 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 04/10/98 | +------------------------------------------------+EVENT TIME: 16:45[EDT]| |NRC NOTIFIED BY: DAVE PIETRUSKI |LAST UPDATE DATE: 05/08/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GLENN MEYER 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - TECH SPEC BASES & UFSAR DISAGREE ON MAX PLANT HEATUP & COOLDOWN CYCLES - | | | | WHILE REVIEWING THE LICENSEE ADMINISTRATIVE CONTROLS FOR TRACKING | | THE NUMBER OF PLANT HEATUPS AND COOLDOWNS, THE LICENSEE DISCOVERED A | | DISCREPANCY BETWEEN THE TECHNICAL SPECIFICATION BASES (SECTION 3.3) | | AND THE UFSAR SECTION 5.2. THE TECHNICAL SPECIFICATION BASES STATE | | THAT THE NUMBER OF PLANT HEATUPS AND COOLDOWNS IS LIMITED TO 120 CYCLES. | | HOWEVER, THE UFSAR HAS BEEN UPDATED TO REFLECT MORE RECENT TECHNOLOGIES | | AND PLACED THE LIMIT AT 300 CYCLES. FURTHER LICENSEE EVALUATION REVEALED | | THAT STARTING ON THE DAY THAT THE PLANT PERFORMED ITS 121st HEATUP, THE | | PLANT WAS BEING OPERATED OUTSIDE OF ITS DESIGN BASES. | | | | THE LICENSEE PERFORMED AN OPERABILITY DETERMINATION AND ALTHOUGH AGREEMENT | | ON THE CORRECT NUMBER OF ALLOWABLE CYCLES IS CURRENTLY BEING DETERMINED, | | IT WILL BE NO LESS THAN 240 CYCLES. THEREFORE, THE REACTOR VESSEL IS WELL | | WITHIN ITS ACTUAL ALLOWABLE NUMBER OF CYCLES. | | | | THE LICENSEE IS ALSO DETERMINING THE NECESSITY OF A REQUEST FOR A CHANGE TO | | THE TECHNICAL SPECIFICATIONS AND PLANS TO SUBMIT A LICENSEE EVENT REPORT ON | | THIS EVENT TO THE NRC WITHIN 30 DAYS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION 2027 5/8/98 FROM CIGANIK TAKEN BY STRANSKY * * * | | | | AFTER FURTHER REVIEW AND ANALYSIS, THE LICENSEE HAS CONCLUDED THAT THE UNIT | | IS WITHIN ITS DESIGN BASIS WITH RESPECT TO THE NUMBER OF HEATUP AND | | COOLDOWN CYCLES. THEREFORE, THE LICENSEE IS RETRACTING THIS EVENT | | NOTIFICATION. THE NRC RESIDENT INSPECTOR WILL BE INFORMED. NOTIFIED R1DO | | (McFADDEN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34062 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 04/12/98 | |UNIT: [1] [ ] [ ] STATE: AZ |NOTIFICATION TIME: 11:06 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 04/12/98 | +------------------------------------------------+EVENT TIME: 04:25[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 05/08/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHARLES CAIN RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE DISCOVERED DURING TESTING THAT THE UNIT 1 "A" EMERGENCY DIESEL | | GENERATOR WOULD NOT RESTART ON A VALID SIGNAL IF MANUALLY OVERRIDDEN DUE TO | | AN INCORRECTLY INSTALLED ELECTRICAL JUMPER. | | | | "ON APRIL 12, 1998 AT APPROXIMATELY 0425 MST, PALO VERDE NUCLEAR GENERATING | | STATION (PVNGS) UNIT 1 OPERATIONS PERSONNEL DETERMINED, WHILE SHUTDOWN FOR | | ITS SEVENTH REFUELING OUTAGE, THAT EMERGENCY DIESEL GENERATOR 'A' COULD NOT | | RESPOND TO ALL EVENTS AS DESCRIBED IN THE UPDATED FINAL SAFETY ANALYSIS | | REPORT (UFSAR). THE SPECIFIC SCENARIO, DESCRIBED IN THE UFSAR, IS A DIESEL | | GENERATOR START DUE TO AN INADVERTENT ACTUATION OF A SAFETY INJECTION | | ACTUATION SIGNAL (SIAS) OR CONTAINMENT SPRAY ACTUATION SIGNAL (CSAS) | | FOLLOWED BY A MANUAL OVERRIDE AND SHUTDOWN OF THE EMERGENCY DIESEL | | GENERATOR. IF A SUBSEQUENT LOSS OF POWER TO THE 'A' ENGINEERED SAFEGUARDS | | FEATURES (ESF) BUS OCCURS, THE MANUAL OVERRIDE SHOULD BE REMOVED AND THE | | EMERGENCY DIESEL GENERATOR WILL RESTART. THIS FEATURE REMOVING THE MANUAL | | OVERRIDE WAS DISCOVERED TO NOT BE FUNCTIONAL. THE 'A' EMERGENCY DIESEL | | GENERATOR WAS NOT REQUIRED TO BE OPERABLE PRIOR TO DISCOVERY, THEREFORE, | | THE SAFETY SIGNIFICANCE WAS NEGLIGIBLE. | | | | "THE DISCOVERY THAT THE REMOVAL OF THE MANUAL OVERRIDE WAS NOT FUNCTIONAL | | WAS THE FIRST PERFORMANCE ON UNIT 1 EMERGENCY DIESEL GENERATOR 'A' OF NEW | | SURVEILLANCE PROCEDURE STEPS IMPLEMENTED SINCE THE ISSUANCE OF GENERIC | | LETTER (GL) 96-01, 'TESTING OF SAFETY-RELATED LOGIC CIRCUITS.' THE | | APPARENT CAUSE WAS A PERMANENT JUMPER THAT WAS INSTALLED ACROSS THE | | INCORRECT TERMINAL CONTACTS. THE DURATION THAT THIS CONDITION HAS EXISTED | | IS NOT YET KNOWN, BUT THE ASSUMPTION THAT IT HAS EXISTED FOR SIGNIFICANTLY | | LONGER THAN THE ALLOWED OUTAGE TIME PERMITTED BY TECHNICAL SPECIFICATION | | 3.8.1.1 AND 3.8.1.2 RESULTED IN A DETERMINATION THAT THE EMERGENCY DIESEL | | GENERATOR WAS INCAPABLE OF FULFILLING ITS SAFETY FUNCTION FOR AN | | INADVERTENT ACTUATION FOLLOWED BY A MANUAL OVERRIDE THEN A SUBSEQUENT LOSS | | OF POWER. | | | | "THE TESTING OF THIS FEATURE HAD ALREADY BEEN SUCCESSFULLY COMPLETED ON THE | | 'B' EMERGENCY DIESEL GENERATOR. IT ALSO HAD BEEN SUCCESSFULLY COMPLETED ON | | BOTH EMERGENCY DIESEL GENERATORS IN UNIT 2. THE WIRING OF THE JUMPER HAS | | BEEN CHECKED AND VERIFIED CORRECT IN UNIT 3. NO AUTOMATIC OR MANUAL | | RPS/ESF ACTUATIONS OCCURRED AND NONE WERE REQUIRED. | | | | "THE DISCOVERY THAT THE MANUAL OVERRIDE WAS NOT CAPABLE OF BEING REMOVED | | DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER OR RESULT | | IN ANY RELEASES OF RADIOACTIVE MATERIALS. THERE WERE NO ADVERSE EFFECTS TO | | THE SAFE OPERATION OF THE PLANT OR HEALTH AND SAFETY OF THE PUBLIC. | | | | "UNIT 1 IS IN ITS 29TH DAY OF ITS SEVENTH REFUELING OUTAGE. THE CORE HAS | | BEEN REFUELED WITH ALL RODS IN. REACTOR COOLANT SYSTEM PRESSURE IS | | ATMOSPHERIC AND TEMPERATURE IS 115 DEGREES FAHRENHEIT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION 1624 5/8/98 FROM ROBERSON TAKEN BY STRANSKY * * * | | | | THE LICENSEE REPORTED THAT THE EDG WOULD HAVE AUTOMATICALLY STARTED IN TEST | | MODE IF CALLED UPON, AND THIS CONDITION WAS COVERED BY OPERATING | | PROCEDURES. THIS EVENT ALONE WOULD NOT HAVE PREVENTED THE FULFILLMENT OF A | | SAFETY FUNCTION. THEREFORE, THE LICENSEE IS RETRACTING THIS EVENT | | NOTIFICATION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R4DO | | (SANBORN). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34184 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GRAND GULF REGION: 4 |NOTIFICATION DATE: 05/06/98 | |UNIT: [1] [ ] [ ] STATE: MS |NOTIFICATION TIME: 01:24 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/05/98 | +------------------------------------------------+EVENT TIME: 21:45[CDT]| |NRC NOTIFIED BY: TERRY HOLCOMBE |LAST UPDATE DATE: 05/08/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - CONTAINMENT ISOLATION SYSTEM INOP & SBGT SYSTEM START DUE TO BLOWN FUSE - | | | | DURING MAINTENANCE ACTIVITIES, A FUSE BLEW IN THE LOGIC SYSTEM FOR THE | | PRIMARY AND SECONDARY CONTAINMENT ISOLATION SYSTEMS. THE BLOWN FUSE | | RESULTED IN A LOSS OF POWER TO RELAYS THAT ISOLATED SOME CONTAINMENT | | ISOLATION VALVES AS WELL AS STARTED THE STANDBY GAS TREATMENT (SBGT) | | SYSTEM. | | | | THE FUSE WAS REPLACED, SYSTEMS WERE RESET TO NORMAL, AND MAINTENANCE | | ACTIVITIES WERE RESUMED. | | | | THIS EVENT IS CONSERVATIVELY BEING REPORTED TO THE NRC IN ACCORDANCE WITH | | 10CFR50.72(b)(2)(ii) [ESF ACTUATION] BECAUSE OF THE POTENTIAL THAT AN | | INVALID ACTUATION OF A SYSTEM NOT SPECIFICALLY LISTED (EXEMPTED) IN | | 10CFR50.72(b)(2)(ii)(B)(3) MAY HAVE OCCURRED. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * RETRACTION 1641 5/8/98 FROM STAFFORD TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS DETERMINED THAT THIS EVENT DID NOT INVOLVE ANY ESF | | ACTUATIONS. THEREFORE, THIS EVENT NOTIFICATION IS BEING RETRACTED. THE NRC | | RESIDENT INSPECTOR WILL BE INFORMED. NOTIFIED R2DO (SANBORN). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34191 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CATAWBA REGION: 2 |NOTIFICATION DATE: 05/07/98 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 18:43 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/07/98 | +------------------------------------------------+EVENT TIME: 17:45[EDT]| |NRC NOTIFIED BY: CHRISTOPHER ORR |LAST UPDATE DATE: 05/09/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 50 POWER OPERATION | 30 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUXILIARY FEEDWATER (AFW) SYSTEM DECLARED INOPERABLE DUE TO ELEVATED | | SUCTION SOURCE WATER TEMPERATURE. | | | | AT 1530, FOLLOWING A POWER REDUCTION FOR AN UNRELATED PROBLEM, THE LICENSEE | | DETERMINED THAT THE UPPER SURGE TANK (NORMAL SUCTION SOURCE FOR THE AFW | | SYSTEM) WATER TEMPERATURE WAS 230øF. THE AFW SYSTEM MAXIMUM DESIGN | | TEMPERATURE LISTED IN THE UPDATED FINAL SAFETY ANALYSIS REPORT IS 138øF. | | ALL THREE AFW PUMPS WERE DECLARED INOPERABLE DUE TO THIS ELEVATED | | TEMPERATURE. | | | | THE LICENSEE DISCOVERED THAT RECIRCULATION VALVE 1-CM-127 WAS PERMITTING | | EXCESSIVE FLOW OF HOT WATER INTO THE UPPER SURGE TANK. THE TEMPERATURE OF | | THE UPPER SURGE TANK WAS REDUCED TO LESS THAN 138øF AT 1730. THE AFW PUMPS | | REMAIN INOPERABLE PENDING THE LICENSEE'S EVALUATION OF THE IMPACT OF THE | | ELEVATED SUCTION TEMPERATURE ON THE AFW SYSTEM. THE APPLICABLE TECHNICAL | | SPECIFICATION LCO REQUIRES THAT ONE AFW PUMP BE RESTORED TO OPERABLE AS | | SOON AS POSSIBLE. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE 1547 5/9/98 FROM ORR TAKEN BY STRANSKY * * * | | | | THE LICENSEE HAS COMPLETED ENGINEERING EVALUATIONS OF THE AFW SYSTEM WHICH | | SHOWED THAT (1) THE UNIT 1 AFW SYSTEM DID NOT SUFFER ANY ADVERSE EFFECTS | | FROM THE HIGH TEMPERATURE, AND (2) WITH VALVE 1CM127 OPEN, THE AFW SYSTEM | | IS OUTSIDE OF ITS DESIGN BASIS SINCE A FAILURE IN THE NONSAFETY-RELATED | | CONDENSATE SYSTEM CAUSES THE INOPERABILITY OF BOTH TRAINS OF THE | | SAFETY-RELATED AFW SYSTEM. THE LICENSEE HAS ISOLATED VALVES 1CM127 AND | | 2CM127 ON UNITS 1 AND 2, RESPECTIVELY, TO PREVENT RECURRENCE UNTIL | | PERMANENT CORRECTIVE ACTIONS CAN BE DEVELOPED. THE NRC RESIDENT INSPECTOR | | WILL BE INFORMED. NOTIFIED R2DO (FREDRICKSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34192 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/08/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 02:59 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/07/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 15:00[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/08/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |PATRICK HILAND RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+ | |NRC NOTIFIED BY: STEVE MAY | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01, 24 HOUR REPORT. | | | | AT 1610 ON 04/21/98, PLANT OPERATIONS PERSONNEL DISCOVERED THAT A NUCLEAR | | CRITICALITY SAFETY APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MAINTAINED | | WITHIN THE X-330 PROCESS BUILDING. | | | | SAMPLE RESULTS FOR CELL #29-5-8 INDICATED THAT THE CELL WAS NOT IN A | | FLUORINATING ENVIRONMENT. WITHOUT A FLUORINATING ENVIRONMENT, THE CELL | | IS IN A UF6-NEGATIVE CONDITION (LESS THAN 10 PPM UF6 AT 2 PSIA). THIS | | CELL HAD PREVIOUSLY BEEN CLASSIFIED AS "PLANNED EXPEDITIOUS HANDLING" | | (PEH) INDICATING THAT THE CELL CONTAINS MORE THAN A SAFE MASS OF URANIUM. | | THIS CELL CONTAINS A PEH DEPOSIT OF UP TO 1687 GRAMS U-235 AT AN ENRICHMENT | | OF 5.4%. THE SAFE MASS FOR A DEPOSIT OF UO2F2 AT 5.4% IS 774 GRAMS U-235. | | NCSA 0330-004.A02, REQUIREMENT #8, REQUIRES THAT ANY CASCADE EQUIPMENT | | (COMPRESSOR) SHUT DOWN (MOTOR TURNED OFF) AND IN A UF6-NEGATIVE CONDITION | | BE SUPPLIED WITH A DRY AIR OR NITROGEN BUFFER AT GREATER THAN 14 PSIA FOR | | MODERATION CONTROL. | | | | PLANT OPERATIONS PERSONNEL PRESSURIZED THE CELL WITH DRY AIR AT GREATER | | THAN 14 PSIA WITHIN EIGHT HOURS TO MAINTAIN MODERATION CONTROL TO MEET THE | | NCSA REQUIREMENT. | | | | PLANT PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND THE DOE SITE | | REPRESENTATIVE. | | | | NOTE: REFER TO SIMILAR EVENT #34189. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34193 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 05/08/98 | |UNIT: [ ] [2] [ ] STATE: GA |NOTIFICATION TIME: 05:19 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/08/98 | +------------------------------------------------+EVENT TIME: 04:01[EDT]| |NRC NOTIFIED BY: STEVE PHILLIPS |LAST UPDATE DATE: 05/08/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |CECIL THOMAS, NRR EO | | |STUART RUBIN IRD | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -AUTO Rx TRIP FROM 100% POWER DUE TO MAIN T/G TRIP DUE TO LIGHTNING STRIKE- | | | | AT 0401, UNIT 2 AUTOMATICALLY TRIPPED FROM 100% POWER DUE TO A MAIN TURBINE | | GENERATOR TRIP SIGNAL CAUSED BY A LIGHTNING STRIKE DURING A SEVERE THUNDER | | STORM. ALL CONTROL RODS FULLY INSERTED INTO THE CORE. THE AUXILIARY | | FEEDWATER SYSTEM ACTUATED, AS EXPECTED, AND STEAM IS BEING DUMPED TO THE | | MAIN CONDENSER. NO SAFETY OR RELIEF VALVES LIFTED. THE 500 KV LINE TO | | WEST MacINTOSH TRIPPED APPARENTLY DUE TO THE LIGHTNING STRIKE. | | | | ALL SYSTEMS FUNCTIONED AS EXPECTED WITH THE FOLLOWING EXCEPTIONS: | | - OIL SPRAYED FROM THE PHASE 'A' MAIN STEPUP TRANSFORMER AND SEVERAL ALARMS | | ANNUNCIATED, AND | | - THE EHC SYSTEM IS INDICATING ZERO PRESSURE WITH BOTH SYSTEM PUMPS | | RUNNING. | | | | UNIT 2 IS STABLE IN MODE 3 (HOT STANDBY). THERE WERE NO PERSONNEL | | INJURIES. THE LICENSEE IS INVESTIGATING THIS EVENT AND INSPECTING THE | | PLANT FOR DAMAGE. | | | | THE STORM CAUSED NO ADVERSE AFFECTS TO UNIT 1. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34194 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 05/08/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 13:44 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/08/98 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: BYRON SHERMAN |LAST UPDATE DATE: 05/08/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND RDO | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | |VERN HODGE NRR | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT REGARDING FAILURE OF 12 VDC INVERTER POWER SUPPLY | | | | ON 2/13/98, A NUCLEAR SYSTEMS POWER SYSTEM (NSPS) 12 VOLT DC POWER SUPPLY | | FAILED, CAUSING THE DIVISION II NSPS INVERTER TO REVERSE TRANSFER TO A | | DEENERGIZED BYPASS TRANSFORMER. THIS CAUSED A LOSS OF SHUTDOWN COOLING AS | | DESCRIBED IN LER 98-003, DATED 3/16/98. THE CAUSE OF THE FAILURE WAS AN | | INADEQUATELY SIZED OUTPUT TRANSISTOR PAIR COMBINED WITH DEGRADED | | CAPACITORS. | | | | THE 12 VDC POWER SUPPLY INVOLVED IN THIS REPORT IS MODEL RMW12-D-20993, | | MANUFACTURED BY KEPCO, INC. IT WAS PURCHASED BY GENERAL ELECTRIC (GE) AS A | | NON-SAFETY RELATED COMPONENT, BUT WAS SUBSEQUENTLY INSTALLED AT CLINTON AS | | PART OF A PANEL SUPPLIED BY GE AS A SAFETY RELATED COMPONENT. KEPCO TYPE | | RMX POWER SUPPLIES ARE IN USE AT CLINTON FOR ALL FOUR DIVISIONS OF NSPS (16 | | TOTAL), NEUTRON MONITORING SYSTEM (24 TOTAL), AND THE DISPLAY CONTROL | | SYSTEM (2 TOTAL). | | | | THE SUPPLIER PROVIDED MARGINALLY RATED OUTPUT TRANSISTORS IN THE POWER | | SUPPLIES. THIS CONDITION, COUPLED WITH PREMATURE AGE RELATED DEGRADATION OF | | ELECTROLYTIC CAPACITORS, RESULTED IN A LARGE CURRENT DRAW WHICH CAUSED THE | | INVERTER TO TRANSFER TO ITS ALTERNATE SOURCE. SINCE THE ALTERNATE SOURCE | | WAS UNAVAILABLE, THE CONDITION RESULTED IN A LOSS OF POWER TO THE NSPS BUS | | LOADS. | | | | THE LICENSEE PLANS TO REPLACE ALL OUTPUT TRANSISTORS AND DEGRADED | | CAPACITORS IN ALL KEPCO TYPE RMX POWER SUPPLIES AND REFURBISH THESE POWER | | SUPPLIES ON A ROUTINE BASIS UNDER A NORMAL PREVENTIVE MAINTENANCE PROGRAM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34195 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/08/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:24 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/08/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:10[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/08/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |PATRICK HILAND RDO | | DOCKET: 0707002 |FRED COMBS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR 91-01 BULLETIN NOTIFICATION INVOLVING A LOSS OF SPACING. | | | | "ON MAY 8, 1998 AT 0110 HOURS OPERATIONS PERSONNEL DISCOVERED THAT A | | NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) WAS NOT BEING MAINTAINED WITH | | THE X-330 PROCESS BUILDING. DRY ACTIVE WASTE (DAW) WAS DISCOVERED STORED | | TOO CLOSE TO A WATER SOLUBLE LAUNDRY BAG (<2 FEET). THIS VIOLATES | | REQUIREMENT #5 OF NCSA-PLANT018.A01 WHICH STATES IN PART, 'DAW SHALL | | MAINTAIN A MINIMUM TWO (2) FEET EDGE-TO-EDGE SPACING FROM ALL OTHER URANIUM | | BEARING MATERIALS/EQUIPMENT.' THIS CONSTITUTES A LOSS OF ONE CONTROL | | (INTERACTION/SPACING) IN THE DOUBLE CONTINGENCY MATRIX FOR CONTINGENCY | | EVENT B.4.1. CONTROL 'A' (INTERACTION/SPACING) WAS LOST. CONTROL 'B' | | (MASS) WAS MAINTAINED THROUGHOUT THIS EVENT. CONTROL 'A' WAS ESTABLISHED | | AT 0150 HOURS UNDER THE DIRECTION OF ON SCENE NUCLEAR CRITICALITY | | PERSONNEL. THERE WAS NO LOSS OF HAZARDOUS/RADIOACTIVE MATERIALS OR | | RADIOLOGICAL CONTAMINATION EXPOSURE AS A RESULT OF THIS EVENT." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE DOE SITE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34196 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/08/98 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/08/98 | +------------------------------------------------+EVENT TIME: 15:10[EDT]| |NRC NOTIFIED BY: M. ENGLAND |LAST UPDATE DATE: 05/08/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROL ROOM VENTILATION DUCTWORK OUTSIDE OF DESIGN BASIS DUE TO SEISMIC | | CONCERNS. | | | | THE LICENSEE HAS DISCOVERED THAT A 20' SECTION OF SEISMIC CLASS 1 DUCTWORK | | ASSOCIATED WITH THE CONTROL ROOM HIGH EFFICIENCY AIR FILTRATION SYSTEM IS | | SUPPORTED BY A SEISMIC CLASS 2 VENTILATION DUCT. THE LICENSEE HAS | | DETERMINED THAT THIS CONFIGURATION IS OPERABLE, BUT IS OUTSIDE OF THE | | SYSTEM DESIGN BASIS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34197 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 05/08/98 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 17:07 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 05/08/98 | +------------------------------------------------+EVENT TIME: 17:07[EDT]| |NRC NOTIFIED BY: JOHN MOYLAN |LAST UPDATE DATE: 05/08/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DRYWELL VACUUM BREAKERS NOT QUALIFIED TO CORRECT SEISMIC REQUIREMENTS | | | | DESIGN SPECIFICATION M516 FOR SWING CHECK VACUUM RELIEF VALVES VRV-261-97A, | | B, C AND D, AND VRV-261-98A, B, C AND D DOES NOT SPECIFY THE CORRECT | | SEISMIC REQUIREMENTS. THE LICENSEE STATED THAT THE VALVES ARE RUGGED AND | | MAY BE QUALIFIED TO THE HIGHER SPECIFICATION, SO THEY ARE CONSIDERED TO BE | | OPERABLE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34198 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 05/09/98 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 04:53 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 05/09/98 | +------------------------------------------------+EVENT TIME: 01:10[PDT]| |NRC NOTIFIED BY: JEANNE KITTLER |LAST UPDATE DATE: 05/09/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LOSS OF POWER TO THE TECHNICAL SUPPORT CENTER. | | | | THE POWER SUPPLY TO THE TECHNICAL SUPPORT CENTER WAS DEENERGIZED AS PART OF | | THE PLANNED DIVISION 1 ELECTRICAL SYSTEMS OUTAGE. THIS PLANNED POWER | | OUTAGE WAS INITIALLY DETERMINED TO NOT BE REPORTABLE PER THE GUIDANCE IN | | NUREG 1022, REVISION 1, WHICH STATES THAT PERFORMING PREVENTATIVE | | MAINTENANCE ON AN OFFSITE EMERGENCY RESPONSE FACILITY IS NOT REPORTABLE IF | | THE FACILITY CAN BE RETURNED TO SERVICE PROMPTLY IN THE EVENT OF AN | | ACCIDENT. | | | | AT 0110 PDT, THE LOSS OF POWER WAS DETERMINED TO BE REPORTABLE PER | | 10CFR50.72(b)(1)(v) DUE TO THE EXTENDED TIME PERIOD IN WHICH THE FACILITY | | WAS WITHOUT POWER. A TEMPORARY POWER SUPPLY TO THE TECHNICAL SUPPORT | | CENTER WAS PROVIDED AT 0115 PDT. THE FACILITY IS NOW CONSIDERED AVAILABLE | | FOR EMERGENCY RESPONSE. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34199 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/09/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:17 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/08/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 17:32[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/09/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |PATRICK HILAND RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+STUART RUBIN IRD | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCAB 76.120(c)(1)(ii) MATL >5X LOWEST LIMIT | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24 HOUR REPORT DUE TO SMALL RELEASE OF UF6 IN TAILS WITHDRAWAL AREA CAUSED | | BY RUPTURED BELLOWS IN TRANSMITTER. | | | | AT 1732 ON 5/8/1998, NINE SMOKE DETECTING DEVICES WITHIN THE X-330 TAILS | | WITHDRAWAL AREA ACTUATED. OPERATIONS PERSONNEL RESPONDING TO THE ALARM | | NOTED VISIBLE SMOKE IN THE TAILS WITHDRAWAL MEZZANINE AREA. THE SOURCE OF | | THE SMOKE WAS IDENTIFIED AS AN OUTGASSING FROM WITHIN THE HEATED | | INSTRUMENTATION CABINET LOCATED UNDER THE MEZZANINE AREA. THE AREA WAS | | IMMEDIATELY EVACUATED, AND EMERGENCY RESPONSE WAS INITIATED. OPERATIONS | | PERSONNEL VENTED THE TAILS STATION TO BELOW ATMOSPHERIC PRESSURE AND THE | | STEAM SUPPLY WAS VALVED CLOSED. EMERGENCY RESPONDERS USED DRY ICE TO FREEZE | | OUT THE MATERIAL AND CRIMPED OFF INSTRUMENTATION LINES IN ORDER TO | | TERMINATE THE RELEASE. THE SOURCE OF THE LEAKAGE WAS DETERMINED TO BE A | | RUPTURED BELLOWS IN ONE OF THE 18 TRANSMITTERS HOUSED IN THE | | INSTRUMENTATION CABINET. | | | | AIR SAMPLES OUTSIDE OF THE AREA WERE LESS THAN DETECTABLE; HOWEVER, INITIAL | | AIR SAMPLES WITHIN THE AREA WERE GREATER THAN PLANT ALLOWABLE LIMITS. THE | | AREA WAS SECURED AND A RADIATION WORK PERMIT IS IN PLACE TO CONTROL ENTRY | | INTO AND EXIT FROM THE TAILS AREA. THERE WAS NO LOSS OF HAZARDOUS OR | | RADIOACTIVE MATERIAL OR RADIOLOGICAL CONTAMINATION OUTSIDE OF THE X-330 | | TAILS WITHDRAWAL STATION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34200 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 05/09/98 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 23:16 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 05/09/98 | +------------------------------------------------+EVENT TIME: 23:04[EDT]| |NRC NOTIFIED BY: BRADDY/HARTKA |LAST UPDATE DATE: 05/10/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CECIL THOMAS EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |AUSTIN FEMA | |NRCS RCS LEAKAGE |STUART RUBIN IRD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 50 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO UNISOLABLE RCS LEAKAGE | | | | THE LICENSEE COMMENCED A UNIT SHUTDOWN IN ACCORDANCE WITH TECHNICAL | | SPECIFICATION 3.1.C.4 AFTER DISCOVERING A 0.25 GPM UNISOLABLE LEAK ON THE | | SEAL INJECTION LINE TO THE "C" REACTOR COOLANT PUMP. THE UNIT WILL BE TAKEN | | TO COLD SHUTDOWN. ALL ESF EQUIPMENT IS AVAILABLE, EXCEPT THE #2 EMERGENCY | | DIESEL GENERATOR WHICH IS OUT OF SERVICE FOR SCHEDULED MAINTENANCE. AN | | UNUSUAL EVENT WAS DECLARED DUE TO THE TECHNICAL SPECIFICATION REQUIRED | | SHUTDOWN. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | | * * * UPDATE 2206 5/10/1998 FROM BRADDY TAKEN BY STRANSKY * * * | | | | THE LICENSEE TERMINATED THE UNUSUAL EVENT WHEN THE UNIT REACHED THE COLD | | SHUTDOWN CONDITION. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED | | R2DO (FREDRICKSON), EO (THOMAS), FEMA (CALDWELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34201 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 05/11/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 00:44 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/10/98 | +------------------------------------------------+EVENT TIME: 20:34[CDT]| |NRC NOTIFIED BY: JIM COOK |LAST UPDATE DATE: 05/11/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GARY SANBORN 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ESF SIGNAL WAS INADVERTENTLY ACTIVATED DURING MAINTENANCE. | | | | DURING PLANNED MAINTENANCE, WHILE PREPARING TO REMOVE A RELAY COIL, THE | | TRIP LEVER MECHANISM WAS INADVERTENTLY TOUCHED THEREBY CAUSING THE RELAY TO | | TRIP. THIS IN TURN CAUSED FURTHER ACTIVATION, AS EXPECTED, OF VARIOUS | | EQUIPMENT INCLUDING SECURING CONTAINMENT PURGE. THE PLANT IS PRESENTLY IN | | REFUELING MODE WITH FUEL HANDLING IN PROGRESS. FUEL MOVEMENT WAS | | IMMEDIATELY STOPPED IN ACCORDANCE WITH TECHNICAL SPECIFICATION 2.8. THE | | PLANT ENTERED ABNORMAL PROCEDURE FOR RESET OF ENGINEERED SAFEGUARDS TO | | RESTORE EQUIPMENT TO NORMAL OPERATIONS. ALL EQUIPMENT WAS RETURNED TO | | NORMAL OPERATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34202 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/11/98 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 04:19 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/11/98 | +------------------------------------------------+EVENT TIME: 01:53[EDT]| |NRC NOTIFIED BY: STEPHEN FREGEAU |LAST UPDATE DATE: 05/11/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JACK MCFADDEN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN ESF SIGNAL WAS INADVERTENTLY ACTIVATED DURING MAINTENANCE. | | | | DURING A TAGOUT PROCEDURE TO SUPPORT PLANNED MAINTENANCE FOR REPACKING A | | RESIDUAL HEAT REMOVAL (RHR) 'C' INJECTION VALVE, IT WAS NOTED THAT THE | | INJECTION PERMISSIVE WAS NO LONGER MADE UP FOR THE VALVE AND THE SYSTEM | | WOULD NO LONGER BE AVAILABLE FOR INJECTION. THE TAGOUT WAS IMMEDIATELY | | ORDERED TO BE CLEARED AND UPON ESTABLISHING POWER, A DIVISION II EMERGENCY | | CORE COOLING SYSTEM (ECCS) INITIATION OCCURRED. THE INITIATION CAUSED AN | | AUTO-START OF EMERGENCY GENERATORS AND THE RHR 'B' AND 'C' SYSTEMS TO ALIGN | | FOR SAFETY INJECTION. NO INJECTION OCCURRED AS THE RHR PUMPS WERE DISABLED | | DUE TO THE REACTOR CAVITY BEING FLOODED WITH THE SPENT FUEL GATES REMOVED. | | THE RHR PUMPS WERE NOT REQUIRED TO BE OPERABLE IN THIS CONDITION. | | | | THE CAUSE OF THE INITIATION IS, PRELIMINARILY, ATTRIBUTED TO THE VESSEL | | LEVEL TRANSMITTERS THAT WERE REENERGIZED WITH THE CLEARANCE OF THE TAGOUT. | | THE INDICATORS FAIL DOWNSCALE WHEN DEENERGIZED AND THE INITIAL SIGNAL WHEN | | REENERGIZED WOULD CAUSE THE ENGINEERED SAFETY SYSTEM (ESF) SIGNAL. THE | | SIGNAL CLEARED AS SOON AS THE INDICATORS RETURNED TO THEIR ACTUAL LEVELS. A | | ROOT CAUSE INVESTIGATION IS UNDERWAY. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+