U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/09/94 - 09/12/94 ** EVENT NUMBERS ** 27657 27698 27757 27762 27763 27764 27765 27766 27767 27768 27769 27770 27771 27772 27773 27774 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27657 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 08/10/94 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 18:01 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 08/10/94 | +------------------------------------------------+EVENT TIME: 17:05[EDT]| |NRC NOTIFIED BY: GERALD MANAGHAN |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: WILLIAM HUFFMAN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JENNY JOHANSEN RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | |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 +------------------------------------------------------------------------------+ | INADEQUATE FIRE PROTECTION OF SAFETY RELATED CABLING. | | | | THE FOLLOWING IS THE TEXT OF A FACSIMILE FROM THE LICENSEE: | | "ON 8/10/94, AT 1705, STATION PERSONNEL DETERMINED THAT LGS U/1 (LIMERICK, | | UNIT 1) WAS NOT IN COMPLIANCE WITH APP. 9A, "FIRE PROTECTION EVALUATION | | REPORT" OF THE UFSAR. A FIRE IN THE REMOTE SHUTDOWN ROOM COULD RESULT IN | | UNAVAILABILITY OF THE D12 4 KV SAFEGUARDS BUS REQUIRED TO SUPPORT FIRE SAFE | | SHUTDOWN METHOD "D" DUE TO THE POTENTIAL FOR FIRE INDUCED DAMAGE TO THE | | RELAY CONTROL CABLES. THIS CONDITION WAS DISCOVERED DURING PERFORMANCE OF | | THE IPEEE FIRE RISK ANALYSIS. | | | | UPON PRIOR NOTIFICATION OF POTENTIAL NONCOMPLIANCE, THE REMOTE SHUTDOWN | | ROOM WAS ADDED TO THE FIRE IMPAIRMENT LOG. ADDITIONAL MITIGATING FACTORS | | INCLUDE THAT THIS AREA HAS BEEN INCLUDED AS PART OF THE ROVING FIRE WATCH | | PATROL ROUND IN RESPONSE TO NRC BULLETIN 92-08. | | | | THIS CONDITION CONSTITUTES A VIOLATION OF LGS OPERATING LICENSE CONDITION | | 2.C.(3)a AND IS REPORTABLE UNDER LICENSE CONDITION 2.F. THIS CONDITION ALSO | | RESULTS IN THE PLANT BEING IN A CONDITION OUTSIDE THE DESIGN BASIS AND IS | | REPORTABLE UNDER 10 CFR 50.72(B)(1)(ii)(B). THE CAUSE OF THIS CONDITION IS | | UNDER INVESTIGATION AND ADDITIONAL CORRECTIVE ACTIONS WILL BE DETERMINED | | BASED ON THE RESULTS OF THIS INVESTIGATION." END OF TEXT | | | | THIS REPORT CONCERNS A CONDITION IN THE REMOTE SHUTDOWN ROOM WHICH INVOLVES | | A CONTROL POWER CABLE TRAY. THE CABLE TRAY WAS FOUND TO NOT BE THERMOLAG | | PROTECTED. THE ROOM HAS BEEN ADDED TO THE FIRE WATCH PATROL. LONG TERM | | COMPENSATORY ACTIONS ARE STILL UNDER EVALUATION. THE NRC RESIDENT INSPECTOR | | WILL BE INFORMED. R1DO (JOHANSEN) NOTIFIED. | | | | *** UPDATE @ 1545 EDT 09/09/94 BY DAVID NEFF TAKEN BY MACKINNON*** | | | | LICENSEE IS RETRACTING THIS REPORT BECAUSE FURTHER ANALYSIS OF THE | | POTENTIAL DAMAGE AND THE EFFECTS ON SAFE SHUTDOWN EQUIPMENT HAS BEEN | | PERFORMED. THE SAFE SHUTDOWN PROCEDURE (SE-8 ATTACHMENT D) PREVIOUSLY | | INCLUDED ADEQUATE MANUAL ACTIONS THAT WOULD HAVE ENSURED THE CAPABILITY TO | | ACHIEVE AND MAINTAIN SAFE SHUTDOWN. SPECIFICALLY, FIRE DAMAGE TO THE CABLE | | COULD RESULT IN THE TRIP OF THE D12 4KV SAFEGUARDS BUS. PROCEDURE SE-8 | | ATTACHMENT D ALREADY PROVIDED FOR THE MANUAL OPERATOR ACTIONS NECESSARY TO | | RE-ENERGIZE THE D12 4KV BUS. THEREFORE, THE EXISTING SAFE SHUTDOWN | | ANALYSIS, INCLUDING THE MANUAL ACTIONS CONTAINED IN SE-8, COMPLY WITH OUR | | COMMITMENTS CONTAINED IN THE UFSAR. AS A RESULT, A CONDITION OUTSIDE DESIGN | | BASIS AND A NON-COMPLIANCE WITH LICENSE CONDITION 2.C.3.a DID NOT EXIST. | | R1DO (EBE McCABE) NOTIFIED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27698 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATERFORD REGION: 4 |NOTIFICATION DATE: 08/23/94 | |UNIT: [3] [ ] [ ] STATE: LA |NOTIFICATION TIME: 12:28 [ET]| |RX TYPE: [3] CE |EVENT DATE: 08/23/94 | +------------------------------------------------+EVENT TIME: 10:55[CDT]| |NRC NOTIFIED BY: DOUGLAS ORTEGA |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | CONTROLLED VENTILATION AREA SYSTEM (CVAS) TRAINS 'A' AND 'B' DECLARED | | INOPERABLE DUE TO A LEAKING HIGH PRESSURE SAFETY INJECTION (HPSI) PUMP | | DISCHARGE RELIEF VALVE. | | | | A HPSI PUMP 'A' DISCHARGE RELIEF VALVE (#SI-214A) WAS FOUND LEAKING | | (APPROXIMATELY 500 ML PER MINUTE) TO THE HPSI PUMP ROOM SUMP. THIS LEAKAGE | | IS IN EXCESS OF THE DESIGN BASIS LEAKAGE FOR THE CVAS. CVAS TRAINS 'A' & | | 'B' WERE DECLARED INOPERABLE & T/S LCO 3.0.3 WAS ENTERED AT 1055. HPSI | | PUMP 'A' WAS ISOLATED AND TAGGED OUT AT 1114 AND DECLARED INOPERABLE. | | ISOLATING THE HPSI PUMP ALSO ISOLATED THE LEAKING RELIEF VALVE. THEREFORE, | | T/S 3.0.3 WAS EXITED AT 1114. BOTH CVAS TRAINS ARE NOW OPERABLE. THE HPSI | | T/S LCO (3.5.2) IS A 72 HOUR LCO. | | | | THE LICENSEE INTENDS TO GAG THE RELIEF VALVE. FURTHER ACTION IS UNDER | | EVALUATION. THE LICENSEE WILL INFORM REGION IV IN LIEU OF THE NRC RESIDENT | | INSPECTOR. | | | | ***UPDATE @ 1547 EDT 09/09/94 BY G SCOTT TAKEN BY MACKINNON*** | | | | LICENSEE IS RETRACTING THIS EVENT. THE FOLLOWING IS THE TEXT OF A FACSIMILE | | SUBMITTED BY THE LICENSEE. | | | | "THE ORIGINAL DETERMINATION THAT THIS EVENT WAS REPORTABLE WAS BASED ON THE | | INFORMATION GATHERED BY THE CONTROL ROOM WITHIN 1 HOUR OF THE EVENT | | OCCURRENCE. AN INVESTIGATION INTO THE FACTS OF THE EVENT DETERMINED THAT | | AT NO TIME DID THE LEAKAGE RATE CREATE A CONDITION WHICH WOULD CAUSE THE | | CVAS TO BE INOPERABLE OR OUTSIDE OF ITS DESIGN BASIS. THE PURPOSE OF | | TECHNICAL SPECIFICATION 3.0.3 IS TO DEFINE THE ACTION TO TAKE WHEN PLANT | | CONDITIONS ARE NOT COVERED BY A LIMITING CONDITION OF OPERATIONS (LCO) OR | | AN ASSOCIATED ACTION STATEMENT. I.E. WHEN THE PLANT IS IN A CONDITION | | PROHIBITED BY TECHNICAL SPECIFICATIONS. HOWEVER, BECAUSE THE CVAS WAS IN | | FACT OPERABLE DURING THIS TIME FRAME, W3 WAS NOT IN A CONDITION PROHIBITED | | BY TECHNICAL SPECIFICATIONS AND ENTRY INTO T.S. 3.0.3 AND THE SUBSEQUENT 1 | | HOUR NOTIFICATION TO THE NRC WAS UNNECESSARY." | | | | "ACCORDINGLY, REPORTING OF THIS EVENT IN ACCORDANCE WITH 10CFR50.72 AND | | 10CFR50.73 IS NOT REQUIRED." END OF TEXT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R4DO(HOWELL) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27757 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 09/08/94 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 13:31 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 12:55[EDT]| |NRC NOTIFIED BY: PATRICK WALSH |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EBE McCABE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SERVICE WATER CHECK VALVE FAILED ITS FORWARD FLOW TEST DURING PERFORMANCE | | OF QUARTERLY SURVEILLANCE TEST PROCEDURE (SERVICE WATER VALVE OPERABILITY | | TEST), PLACING LICENSEE IN TECH SPEC REQUIRED SHUTDOWN PER TECH SPEC | | 3.8.3.1. | | | | DURING PERFORMANCE OF SURVEILLANCE PROCEDURE N2-OSP-SWP-Q001, SERVICE WATER | | VALVE OPERABILITY TEST, CHECK VALVE 2SWP*V802A FAILED ITS FORWARD FLOW | | TEST. 2SWP*V802A IS THE SERVICE WATER RETURN FROM DIVISION 1 SWITCHGEAR | | UNIT COOLERS. WITH THE DIVISION 1 SWITCHGEAR UNIT COOLERS INOPERABLE THE | | ASSOCIATED DIVISION AC/DC SWITCHGEAR IS DECLARED INOPERABLE. TECH SPEC | | 3.8.3.1 REQUIRES RESTORATION OF THE DC SWITCHGEAR WITHIN 2 HOURS OR BE IN | | HOT SHUTDOWN WITHIN 12 HOURS AND COLD SHUTDOWN WITHIN THE FOLLOWING 24 | | HOURS. PLANT SHUTDOWN COMMENCED AT 1255 ON 09/08/94. CURRENT PLANS INCLUDE | | THE FOLLOWING: 1) REFINE THE TEST METHOD TO DETERMINE THE DEGRADED | | COMPONENTS, 2) EVALUATE THE TEST RESULTS BASED ON SERVICE WATER TEMPERATURE | | FOR UNIT COOLER OPERABILITY, & 3) DEVELOP A WORK PLAN TO REPAIR THE | | DEGRADED COMPONENTS. PLANT SHUTDOWN WILL PROCEED AT 5% AN HOUR FOR THE | | FIRST 2 HOURS AND 10% AN HOUR THERE AFTER. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ***UPDATE @ 1945 EDT 9/08/94 BY DEMETRIUS WILLIS TAKEN BY MACKINNON*** | | | | EXITED TECH SPEC REQUIRED SHUTDOWN AT 1945 EDT. ENGINEERING ISSUED A DESIGN | | CHANGE WHICH REMOVED THE INTERNALS OF CHECK VALVE 2SWP*V802A. THE CHECK | | VALVE WITHOUT ITS INTERNALS PASSED ITS FORWARD FLOW SURVEILLANCE TEST. | | LICENSEE HAD A SIMILAR PROBLEM WITH TRAIN "B" CHECK VALVE (2SWP*V802B) AND | | HAD ITS INTERNALS REMOVED SOMETIME LAST YEAR. LOWEST REACTOR POWER REACHED | | WAS 95% POWER. R1DO (EBE McCABE) NOTIFIED. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ***UPDATE @ 1800 EDT 09/09/94 BY DEMETRIUS WILLIS TAKEN BY MACKINNON*** | | | | LICENSEE MADE A MISTAKE. TRAIN "B" CHECK VALVE 2SWP*V802B INTERNALS WERE | | NOT REMOVED AS STATED ABOVE IN UPDATE TAKEN AT 1945 EDT 09/08/94. LICENSEE | | HAS PAPER WORK TO REMOVE THE INTERNALS BUT AS OF THIS TIME THE INTERNALS OF | | THIS VALVE HAVE NOT BEEN REMOVED AND THE LICENSEE DID NOT KNOW WHEN THE | | INTERNALS WOULD BE REMOVED. RESIDENT INSPECTOR WILL INFORMED. R1DO (EBE | | McCABE) NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27762 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 09/08/94 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 23:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/08/94 | +------------------------------------------------+EVENT TIME: 20:28[CDT]| |NRC NOTIFIED BY: CLARK |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |ART HOWELL RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STEVEN VARGA EO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION |BAGWELL FEMA | |AESF 50.72(b)(2)(ii) ESF ACTUATION |CALLAN R4 | | |BEACH R4 | | |ROE NRR | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 97 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC REACTOR SCRAM FROM 97% POWER, WITH FAILURE OF THE MAIN GENERATOR | | AND THE TURBINE TO AUTOMATICALLY TRIP. | | | | RIVER BEND HAD AN AUTOMATIC REACTOR SCRAM AT 2028 CDT FROM 97% POWER. THE | | EXACT CAUSE OF THE SCRAM IS UNKNOWN AND IS BEING INVESTIGATED. THE SCRAM | | APPEARED ROUTINE FOR APPROXIMATELY 5 MINUTES, WHEN OPERATORS NOTED THAT IT | | APPEARED THAT THE MAIN GENERATOR AND THE TURBINE HAD FAILED TO TRIP. | | OPERATORS THEN MANUALLY TRIPPED THE MAIN TURBINE AND THE MAIN GENERATOR | | OUTPUT BREAKERS. | | | | THE TRIPPING OF THE MAIN GENERATOR OUTPUT BREAKERS CAUSED AN "ELECTRICAL | | TRANSIENT", RESULTING IN A LOSS OF NORMAL CONDENSATE AND FEEDWATER AND A | | MAIN STEAM ISOLATION. OPERATORS UTILIZED MANUAL OPERATION OF THE SAFETY | | RELIEF VALVES (SRV's) TO CONTROL REACTOR PRESSURE, IN ADDITION TO MAIN | | STEAM LINE DRAIN CAPABILITY (FROM UPSTREAM OF THE INBOARD MSIV's). RCIC | | (REACTOR CORE ISOLATION COOLING) WAS INITIALLY STARTED MANUALLY, BUT | | IMMEDIATELY TRIPPED (FOR REASONS UNKNOWN AND BEING INVESTIGATED). OPERATORS | | THEN MANUALLY UTILIZED HIGH PRESSURE CORE SPRAY (HPCS) TO MAINTAIN AND | | CONTROL REACTOR VESSEL LEVEL. | | | | THE LOWEST LEVEL REACHED DURING THE EVENT WAS APPROXIMATELY +2" (NARROW | | RANGE), WHICH IS BETWEEN LEVEL 3 AND LEVEL 2. THERE WERE NO AUTOMATIC | | INITIATIONS OF ECCS EQUIPMENT (SETPOINTS ARE LEVEL 2). REACTOR PRESSURE, | | TEMPERATURE AND LEVEL ARE CURRENTLY STABLE, WITH PRESSURE BEING MAINTAINED | | BETWEEN 800-1000#, TEMPERATURE AT 500F AND LEVEL NORMAL AT +36" (NARROW | | RANGE). OPERATORS ARE IN THE PROCESS OF TRYING TO ESTABLISH ALTERNATE | | METHODS OF PRESSURE CONTROL. THERE WERE ALSO VARIOUS PRIMARY AND BALANCE OF | | PLANT (BOP) ISOLATIONS AND SYSTEM ACTUATIONS ASSOCIATED WITH THE EVENT, BUT | | A DETAILED LISTING WAS NOT AVAILABLE AT THE TIME OF THE CALL. | | | | THE UNUSUAL EVENT WAS DECLARED AT THE DISCRETION OF THE SHIFT SUPERVISOR AT | | 2209 CDT, BASED ON THE JUDGMENT THAT AUGMENTED SUPPORT WAS DESIRABLE TO AID | | IN RESTORING SYSTEMS AND TO ENSURE NO OTHER DIFFICULTIES WERE INCURRED. THE | | PLANT DID NOT MEET ANY OF THE EAL (EMERGENCY ACTION LEVEL) CRITERIA WHICH | | WOULD REQUIRE DECLARING AN UNUSUAL EVENT. | | | | WHEN THE OPERATORS MANUALLY TRIPPED THE MAIN GENERATOR OUTPUT BREAKERS, THE | | NORMAL STATION BUSES (WHICH RECEIVE POWER FROM PREFERRED BUSES) EXPERIENCED | | A VERY SLOW TRANSFER CAUSING A LOSS OF AUXILIARY SYSTEMS (MAIN FEED AND | | CONDENSATE PUMPS, RECIRCULATION PUMPS, ETC...). THE NORMAL RPS (REACTOR | | PROTECTION SYSTEM) POWER SUPPLIES (VIA THE MG SETS) WERE ALSO LOST DURING | | THE ELECTRICAL TRANSIENT, WHICH CAUSED SOME OF THE ISOLATIONS EXPERIENCED, | | AND OPERATORS QUICKLY TRANSFERRED TO THE ALTERNATE RPS POWER SUPPLY. THE | | PLANT SAFETY BUSES REMAINED ENERGIZED THROUGHOUT THE EVENT (NORMALLY | | POWERED FROM OFF-SITE POWER), AND THE EMERGENCY DIESEL GENERATORS WERE | | NEVER REQUIRED TO START. | | | | OPERATORS ARE IN THE PROCESS OF RESTORING AT LEAST ONE RECIRCULATION PUMP | | AND ONE MAIN STEAM LINE TO SERVICE. NORMAL CONDENSATE AND FEED HAS ALREADY | | BEEN RESTORED. HPCS REMAINS RUNNING, BUT IS NO LONGER INJECTING BECAUSE | | VESSEL LEVEL IS BEING ADEQUATELY MAINTAINED VIA THE CRDH (CONTROL ROD DRIVE | | HYDRAULIC) SYSTEM. THE CALLER STATED THAT THE COOLDOWN EXPERIENCED IS | | CURRENTLY BEING PLOTTED, HOWEVER, THERE WAS NO MAJOR LOWERING OF RX VESSEL | | PRESSURES OR LEVELS. THE UNIT IS NOT EXPERIENCING ANY PROBLEMS WITH | | SUPPRESSION POOL COOLING OR SRV OPERATIONS. ALL RODS FULLY INSERTED INTO | | THE CORE ON THE REACTOR SCRAM. THE LICENSEE NOTIFIED THE RESIDENT | | INSPECTOR, WHO IS IN THE CONTROL ROOM AT THIS TIME, AND STATE AND LOCAL | | AUTHORITIES. THE LICENSEE INTENDS TO TERMINATE THE UNUSUAL EVENT IN A | | FAIRLY SHORT TIME FRAME. | | | | AT 0030 EDT, THE RESIDENT INSPECTOR (WARD SMITH) BRIEFED THE FOLLOWING | | INDIVIDUALS ON THE EVENT: R4RA (CALLAN), R4 (BEACH, HARREL), R4DO (HOWELL), | | NRR EO (VARGA) AND NRR PD 3&4 (ROE). | | | | ** UPDATE DATE/TIME: 9/9/94 @ 0155 EDT *FROM LICENSEE: CLARK BY: McGINTY** | | THE LICENSEE TERMINATED THE UNUSUAL EVENT AT 0055 CDT. THE INITIAL LOOK AT | | THE COMPUTER PRINTOUT INDICATES THAT THE REACTOR SCRAM WAS DUE TO A LEVEL | | TRANSIENT, SPECIFICALLY A HIGH LEVEL (LEVEL 8, +51") TURBINE TRIP AND | | REACTOR SCRAM SIGNAL. THE EXACT CAUSE OF THE TRANSIENT IS STILL UNDER | | INVESTIGATION. THE ABNORMAL CONDITIONS REGARDING THE TURBINE GENERATOR | | TRIP (AS WELL AS THE RCIC TRIP) ARE STILL BEING EVALUATED. THE LICENSEE | | HAS RESTORED THE MAIN STEAM LINES TO SERVICE AND ARE CONTROLLING PRESSURE | | WITH NORMAL STEAM BYPASS. REACTOR PRESSURE VESSEL LEVEL CONTROL HAS BEEN | | RE-ESTABLISHED WITH THE NORMAL CONDENSATE AND FEEDWATER SYSTEM. THEY ARE | | STILL PURSUING THE RESTART OF A RECIRCULATION PUMP (ESTABLISHING DESIRABLE | | DELTA T AND PRESSURE CONDITIONS). THE INITIAL PLANS ARE TO PROCEED TO COLD | | SHUTDOWN. THE PLANT IS STABLE IN HOT STANDBY. | | | | HOO NOTIFIED THE R4DO (HOWELL) AND FEMA (NUSE). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27763 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 09/09/94 | |UNIT: [1] [ ] [ ] STATE: VA |NOTIFICATION TIME: 01:42 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 00:20[EDT]| |NRC NOTIFIED BY: MOSHER |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: TIM McGINTY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM CLINE 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 8 POWER OPERATION | 8 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WHILE AT 8% POWER DURING A SHUTDOWN TO ENTER A REFUELING OUTAGE, AN | | UNPLANNED TURBINE TRIP AND FEEDWATER TRANSIENT CAUSED A MAIN FEEDWATER PUMP | | TRIP AND AUX FEED PUMP ACTUATION. | | | | AT 0020 EDT ON 9/9/94, ALL THREE AUXILIARY FEEDWATER (AFW) PUMPS STARTED | | WHEN ALL MAIN FEEDWATER PUMPS TRIPPED DUE TO HIGH-HIGH LEVEL (75% NARROW | | RANGE) IN THE "A" STEAM GENERATOR (THE OTHER SG LEVELS WERE ALSO HIGH). THE | | HIGH-HIGH LEVEL OCCURRED DUE TO A FEEDWATER TRANSIENT WHICH STARTED WHEN | | THE UNIT WAS TAKEN OFF-LINE AND AN UNPLANNED MAIN TURBINE TRIP OCCURRED (AT | | 0017 EDT). AT THIS TIME THE CAUSE OF THE TURBINE TRIP IS UNKNOWN AND IS | | BEING INVESTIGATED. | | | | THE AFW PUMPS (TWO MOTOR DRIVEN AND ONE STEAM DRIVEN) HAVE BEEN SECURED AND | | ARE IN STANDBY, WITH MAIN FEEDWATER RESTORED TO SERVICE. THE UNIT HAS | | COMPLETED ITS SHUTDOWN AND IS IN HOT STANDBY AND BORATING, MAKING | | PREPARATIONS TO COOL DOWN. THE MAIN CONDENSER IS AVAILABLE FOR STEAMING | | VIA THE BYPASSES. ALL EDG's AND ECCS's ARE OPERABLE, AND THERE WERE NO | | PROBLEMS LINING UP THE ELECTRICAL BUSES FOR THE SHUTDOWN. WHEN THE UNIT IS | | BELOW 30% POWER, A TURBINE TRIP DOES NOT CAUSE AN AUTOMATIC REACTOR TRIP. | | | | THE LICENSEE INFORMED THE RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27764 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 09/09/94 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 09:29 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: HUTTON |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EBE MCCABE 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 +------------------------------------------------------------------------------+ | STATE AND LOCAL AGENCIES WILL BE NOTIFIED THAT THE PLANT WILL PERFORM A | | CONTROLLED SHUTDOWN TO ENTER A REFUELING OUTAGE AT 12 NOON ON 09/09/94. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27765 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: ZION REGION: 3 |NOTIFICATION DATE: 09/09/94 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 09:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 00:00[CDT]| |NRC NOTIFIED BY: MOWERY |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 N 0 | 0 | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ZION STATION REPORTED A DEFECTIVE SHAFT AND EXTENSION IN AN EMERGENCY | | DIESEL GENERATOR (EDG) MANUFACTURED BY COOPER-BESSEMER. | | | | MR. J.D. MOWERY OF COOPER-BESSEMER, RECIPROCATING PRODUCTS DIVISION, OF | | GROVE CITY, PENNSYLVANIA, REPORTED THAT A DEFECT EXISTS IN THE SHAFT (PART | | # KSV-76-7b, SERIAL #3H2501-5) AND EXTENSION (PART #KSV-76-7C, SERIAL # | | 3K0801-5) IN THE "KSV" EMERGENCY DIESEL GENERATOR SYSTEM WHICH COULD RESULT | | IN A FAILURE OF THE SHAFT. SUCH A FAILURE WOULD PROHIBIT THE GENERATION OF | | AN ENGINE SPEED SIGNAL AND THE EDG WOULD AUTOMATICALLY SHUT DOWN ON A | | SENSED-ZERO SPEED CONDITION. THIS NOTIFICATION IS THE RESULT OF A FAILURE | | OF A SHAFT AND EXTENSION ON AN EDG AT ZION UNIT "2A". THE ROOT CAUSE OF | | THIS DEFECT WAS IMPROPER DESIGN IN THE THREAD ENGAGEMENT OF THE SHAFT AND | | EXTENSION, WHEREBY THE DESIGN OF THE SHAFT MALE THREADS AND THE EXTENSION | | FEMALE THREAD WERE .125" SHORT OF MINIMUM ENGAGEMENT WHEN ASSEMBLED. | | | | ZION STATION HAS REPLACED THE TWO-PIECE SHAFT AND EXTENSION WITH A SINGLE- | | PIECE SHAFT KSV-76-E. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27766 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: COOPER INDUSTRIES OF GROVE CITY, PA |NOTIFICATION DATE: 09/09/94 | | CITY: GROVE CITY REGION: 1 |NOTIFICATION TIME: 09:21 [ET]| | COUNTY: STATE: PA |EVENT DATE: 09/09/94 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 09/09/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | | | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: J.D. MOWERY | | |HQ OPS OFFICER: GREG SCARFO | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COOPER-BESSEMER OF GROVE CITY, PENNSYLVANIA, REPORTS THAT DEFECTIVE | | THERMOCOUPLES MAY EXIST IN "KSV" EMERGENCY DIESEL GENERATORS (EDGs). | | | | MR. J.D. MOWERY OF COOPER-BESSEMER, RECIPROCATING PRODUCTS DIVISION, OF | | GROVE CITY, PENNSYLVANIA, REPORTED A DEFECT IN THERMOCOUPLES (PART #s | | 2-01J-026-027, 2-01J-026-029, 2-01J-026-049, 2-01J-026-050, AND | | 2-01J-026-051) UTILIZED IN THE "KSV" EMERGENCY DIESEL GENERATOR SYSTEM. THE | | DEFECTIVE THERMOCOUPLES WERE MANUFACTURED BY NORAL INCORPORATED BETWEEN | | JULY 1989 AND SEPTEMBER 15, 1991. THE THERMOCOUPLES ARE INSTALLED IN THE | | EXHAUST SYSTEM OF THE EDG AND MONITOR THE TEMPERATURE OF THE EXHAUST GAS. | | IF A FAILURE OF THE THERMOCOUPLE OCCURS, IT COULD BE CARRIED BY THE EXHAUST | | STREAM INTO THE TURBOCHARGER WITH CATASTROPHIC RESULTS. THIS NOTIFICATION | | IS THE RESULT OF SUCH A FAILURE WHICH OCCURRED ON THE "2B" EDG AT THE ZION | | STATION. THE ROOT CAUSE OF THIS DEFECT IS THE CRIMPING OF THE FERRULE ONTO | | THE TUBE AND SHEATH OF THE THERMOCOUPLE DURING THE TIME SPECIFIED. | | THERMOCOUPLES MANUFACTURED BY NORAL INCORPORATED SINCE SEPTEMBER, 1991, | | HAVE THE FERRULE BRAZEN ONTO THE TUBE AND SHEATH. UTILITIES WHICH HAVE | | RECEIVED SHIPMENTS OF THESE THERMOCOUPLES INCLUDE ENTERGY, NIAGARA-MOHAWK, | | AND COMMONWEALTH EDISON. CORRECTIVE ACTIONS AT THE UTILITIES SHOULD | | INCLUDE A FULL INSPECTION OF ALL THERMOCOUPLES ON THE EDGs AND IN STORES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 27767 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: POWER RESOURCES, HIGHLAND URANIUM |NOTIFICATION DATE: 09/09/94 | | CITY: GLEN ROCK REGION: 4 |NOTIFICATION TIME: 10:20 [ET]| | COUNTY: STATE: WY |EVENT DATE: 09/09/94 | |LICENSE#: SUA-1511 AGREEMENT: N |EVENT TIME: 08:20[MDT]| | DOCKET: |LAST UPDATE DATE: 09/09/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ART HOWELL RDO | | |PAPERIELLO EO | +------------------------------------------------+BANGART SP | |NRC NOTIFIED BY: KEARNEY |SHULL FEMA | |HQ OPS OFFICER: TIM McGINTY |FLOYD EPA | +------------------------------------------------+BERGER HHS | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BILL KEARNEY, OF POWER RESOURCES INC. AT THE HIGHLAND URANIUM PROJECT | | LOCATED IN GLEN ROCK, WYOMING, NOTIFIED THE OPERATIONS CENTER OF A MONITOR | | WELL THAT HAS BEEN PLACED ON EXCURSION STATUS. | | | | WELL "CN-15" IS ON EXCURSION STATUS AS OF TODAY. THIS INDICATES THE | | POTENTIAL THAT SOME OF THE MINING FLUIDS HAVE GONE OUT OF THE MINE FIELD | | AREA. THE LICENSEE REPORTED THAT THEIR IS NO HAZARD TO HUMAN HEALTH AND | | SAFETY NOR THE ENVIRONMENT AT THIS TIME. THE LICENSEE IS REQUIRED BY THEIR | | LICENSE TO NOTIFY THE NRC WITHIN 24 HRS IF A WELL HAS BEEN PLACED ON | | EXCURSION STATUS. THE SITE CURRENTLY HAS THREE WELLS ON EXCURSION STATUS. | | THE LICENSEE WILL ALSO BE SUBMITTING A DETAILED REPORT WITHIN DAYS. | | | | THE RESULTS OF THE SAMPLE INDICATE 14 MG/L OF CHLORIDES (18.2 MG/L LIMIT), | | 258 MG/L BICARBONATE (247 MG/L LIMIT) AND A CONDUCTIVITY OF 951 | | MICRO-MHO's/CM (LIMIT OF 852), WITH THE LEVEL OF U3O8 <.1 MG/L. THE | | INFORMATION WAS REPORTED IN ACCORDANCE WITH LICENSE CONDITION 12.3. THE | | LICENSEE INFORMED MIKE LAYTON OF NMSS. | | | | ALSO, USDA(KECIA) AND DOE(TANNER) WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27768 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/09/94 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:04 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 10:48[EDT]| |NRC NOTIFIED BY: ROSS |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |EBE MCCABE 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 +------------------------------------------------------------------------------+ | AN ENGINEERING EVALUATION DETERMINED THAT A FAULT ON AN UNINTERRUPTIBLE | | POWER SUPPLY (UPS) COULD PREVENT THE FEEDWATER COOLANT INJECTION (FWCI) | | SYSTEM FROM PERFORMING ITS SAFETY FUNCTION. | | | | WHILE PERFORMING AN ENGINEERING REVIEW OF SAFETY BUS "E4", IT WAS | | DETERMINED THAT A FAULT IN AN UPS, WHICH PROVIDES BACKUP POWER TO THE PLANT | | COMPUTER, COULD DEGRADE THE OUTPUT OF THE "E4" BUS AND PREVENT THE FWCI | | SYSTEM FROM PERFORMING ITS SAFETY FUNCTION DURING A LOSS OF OFFSITE POWER. | | NORMALLY, THE "C2" BUS SUPPLIES THE UPS AS A SECONDARY POWER SUPPLY. THE | | LICENSEE HAS DISCONNECTED THE UPS FROM THE "E4" BUS TO PREVENT THIS | | SCENARIO FROM OCCURRING. THE UPS CURRENTLY UTILIZES THE "C2" 480V BUS AS A | | PRIMARY POWER SUPPLY AND THE "DC-1A" 480V BUS AS A SECONDARY SUPPLY. STATE | | AND LOCAL AGENCIES WERE NOTIFIED. THE LICENSEE INFORMED THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27769 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/09/94 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 13:30 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 11:14[CDT]| |NRC NOTIFIED BY: RICK PARLATO |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CYNTHIA PEDERSON 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NORMAL FEEDER SUPPLY BREAKER (2A52-70) TO 4.16KV SAFEGUARDS BUS (2A06) | | OPENED UNEXPECTEDLY CAUSING EMERGENCY DIESEL GENERATOR (GO2) TO AUTOSTART | | AND SUPPLY POWER TO SAFEGUARDS BUS (2A06). THIS PLACED LICENSEE IN TECH | | SPEC 15.3.7.B.1.D (NORMAL OFFSITE POWER TO SAFEGUARDS BUS NOT AVAILABLE, 7 | | DAY LCO). | | | | PLANT ELECTRICIANS WERE INSTALLING A MODIFICATION ON EDG (GO2) CONTROL | | PANEL TO MOVE ITS SYNCHRONIZING CIRCUIT (LICENSEE IS ADDING TWO MORE EDGs | | TO THEIR SITE) WHEN A GROUND ON A POTENTIAL TRANSFORMER CAUSED THE | | UNDERVOLTAGE RELAYS ON SAFEGUARDS BUS (2A06) TO ACTUATE, WHICH OPENED ITS | | NORMAL FEEDER BREAKER (2A52-70). OPENING OF THIS FEEDER BREAKER CAUSED EDG | | (GO2) TO AUTOMATICALLY START AND SUPPLY POWER TO THE BUS. DEENERGIZATION OF | | THE BUS CAUSED BATTERY CHARGER (D08) TO STRIP (THIS WAS EXPECTED) AND | | PLACED LICENSEE IN TECH SPEC 15.3.7.B.1.H (3 HOUR LCO ACTION STATEMENT) FOR | | 15 MINUTES. EDG (GO2) IS STILL SUPPLYING POWER TO SAFEGUARDS BUS (2A06). | | LICENSEE IS INVESTIGATING THE EXACT CAUSE OF THE BREAKER OPENING. AFTER | | CORRECTING WHY THE BREAKER OPENED LICENSEE WILL SYNCHRONIZE SAFEGUARDS BUS | | WITH OFFSITE POWER AND THEN SECURE THE EDG. LICENSEE WILL REMAIN IN TECH | | SPEC 15.3.7.B.1.D UNTIL NORMAL OFFSITE POWER IS RESTORED TO SAFEGUARDS BUS | | (2A52-70). | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27770 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/09/94 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 15:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CYNTHIA PEDERSON RDO | |ADAS 50.72(b)(2)(i) DEG/UNANALYZED COND | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POST ACCIDENT SAMPLE RETURN LINE CHECK VALVE (NS-357) FAILED TYPE B & C | | LEAK TEST. | | | | POST ACCIDENT SAMPLE RETURN CHECK VALVE EXCEEDED ITS TECH SPEC LIMIT OF | | 0.6La (>66,000ccm) DURING TYPE B & C CONTAINMENT LEAK TESTING. LICENSEE | | SAID THAT THE CALCULATED LEAK RATE OF THE CHECK VALVE WAS 15.49La. LICENSEE | | WILL REPAIR THE VALVE BEFORE THEY COMPLETE THEIR REFUELING OUTAGE. LICENSEE | | THINKS THAT THE CHECK VALVE IS STUCK OPEN. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27771 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FERMI REGION: 3 |NOTIFICATION DATE: 09/09/94 | |UNIT: [2] [ ] [ ] STATE: MI |NOTIFICATION TIME: 16:02 [ET]| |RX TYPE: [2] GE-4 |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 15:10[EDT]| |NRC NOTIFIED BY: BOB GAILLIEZ |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CYNTHIA PEDERSON RDO | |BBBB 20.403 UNSPECIFIED PARAGRAPH |BOB PIERSON EO | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LICENSEE REPORTED THIS EVENT UNDER 10 CFR 20.1906 (PROCEDURES FOR RECEIVING | | AND OPENING PACKAGES) PARAGRAPH "D". | | | | DURING A PACKAGE RECEIPT SURVEY BY RADIATION PROTECTION PERSONNEL A PACKAGE | | EXCEEDED THE EXTERNAL SURFACE RADIATION LIMIT OF 200 mr/hr AS SPECIFIED IN | | 10 CFR 71.47 "A". INITIAL SURVEYS OF THE TOP OF THE PACKAGE ARE 350 mr/hr. | | THE CARRIER OF THE PACKAGE IS HITTMAN TRANSPORT AND IT WAS TRANSPORTED FROM | | SCIENTIFIC ECOLOGY CORPORATION, TENN. THE PACKAGE CONTAINS SUPER COMPACTED | | DRY RADIOACTIVE WASTE AND IT WAS BEING RETURNED TO THEM. THE CRIBBING IN | | THE TRANSPORTATION VEHICLE LOCATED ABOVE THE PACKAGE MADE THE PACKAGE | | APPEAR THAT ITS EXTERNAL SURFACE RADIATION LEVELS WERE LESS THAN | | 200milrem/hr. LICENSEE SAID THAT NOBODY WAS OVEREXPOSED BY THIS PACKAGE | | (THIS INCLUDES THE TRUCK DRIVER). | | LICENSEE WILL NOTIFY THE CARRIER AND INFORM REGION 3 OF THIS EVENT. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27772 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 09/09/94 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 17:01 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 09/09/94 | +------------------------------------------------+EVENT TIME: 16:40[EDT]| |NRC NOTIFIED BY: BURTON |LAST UPDATE DATE: 09/09/94 | |HQ OPS OFFICER: GREG SCARFO +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |EBE MCCABE RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |STEVEN VARGA EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |EARLE FEMA | |NLCO TECH SPEC LCO A/S | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 HOT SHUTDOWN | 0 HOT SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AN NOUE WAS DECLARED AT 1640EDT WHEN BORIC ACID RESIDUES WERE DISCOVERED | | DURING AN INSPECTION OF CONTAINMENT IN PREPARATION FOR MAIN STEAM ISOLATION | | VALVE (MSIV) MAINTENANCE. THE BORIC ACID RESIDUES WERE THE RESULT OF A | | SMALL LEAK FROM A REACTOR COOLANT SYSTEM (RCS) FLOW TAP. | | | | AN NOUE WAS DECLARED AT 1640EDT WHEN BORIC ACID RESIDUES WERE DISCOVERED ON | | THE CONTAINMENT FLOOR DURING A VISUAL INSPECTION OF THE CONTAINMENT IN | | PREPARATION FOR REPAIRS OF MSIV "C". AN INVESTIGATION DETERMINED THE | | SOURCE OF THE BORIC ACID TO BE A MANUAL VALVE ON A 0.75" FLOW TAP FROM RCS | | LOOP "C". THE LEAK RATE WAS SO SMALL THAT IT WAS UNDETECTABLE FROM CONTROL | | ROOM INSTRUMENTATION DURING PLANT OPERATIONS. UPON DISCOVERY, THE UNIT | | ENTERED TECHNICAL SPECIFICATION ACTION STATEMENT 3.4.6.2 AND PROCEEDED TO | | COLD SHUTDOWN AS SPECIFIED. | | | | THE CRACKED VALVE ON THE FLOW TAP LINE WILL BE REPLACED. THE CRITERIA FOR | | EXITING THE NOUE IS ENTRY INTO COLD SHUTDOWN. A RESTART IS NOT EXPECTED | | UNTIL 09/12/94. THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. STATE | | AND LOCAL AGENCIES HAVE BEEN NOTIFIED. | | | | ***UPDATE AT 08:21 @ 09/10/94 BY FETTERMAN TO GOULD*** THE NOUE WAS | | TERMINATED AT 08:07 DUE TO THE PLANT BEING IN COLD SHUTDOWN. RI WILL BE | | INFORMED. FEMA(STINEDURF), EO(VARGA) & RDO(EBE McCABE) WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |IRRETRIEVABLE WELL LOGGING SOURCE | |EVENT NUMBER: 27773 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SCHULMBERGER TECHNOLOGY CORP |NOTIFICATION DATE: 09/09/94 | | CITY: HOUSTON REGION: 4 |NOTIFICATION TIME: 17:45 [ET]| | COUNTY: HARRIS STATE: TX |EVENT DATE: 09/09/94 | |LICENSE#: 42-00090-03 AGREEMENT: Y |EVENT TIME: 17:45[CDT]| | DOCKET: |LAST UPDATE DATE: 09/09/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ART HOWELL RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: DOUGLAS AITKEN | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |EIRR 39.77(c) WELL LOGGING SOURCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ANADRILL, A SUBSIDIARY OF SCHULMBERGER TECHNOLOGY CORP LOCATED IN HOUSTON, | | TEXAS, REPORTED THAT THREE STUCK WELL LOGGING SOURCES WILL MOST PROBABLY | | HAVE TO BE ABANDONED. THE WELL IS LOCATED IN THE GULF OF MEXICO ON EUGENE | | ISLAND, BLOCK 157 AND IS LEASED TO SHELL OFFSHORE INCORP. WELL NAME IS | | OSC-G-11951-ST2 AND ITS WELL LOCATION IDENTIFIER NUMBER IS API # | | 17-709-41015. THE THREE SOURCES THAT MIGHT BE ABANDONED ARE AMERICIUM-241 | | BERYLLIUM (NEUTRON SOURCE), 7.5 CURIES, NSR-P 624; CESIUM-137 (GAMMA | | SOURCE) 1.7 CURIES, GSR-Z 1530; AMERICIUM-241, 50 MICROCURIES, ASR-A-946. | | IF THEY CANNOT REMOVE THE SOURCES THEY WILL CEMENT THEM IN PLACE (SOURCES | | ARE 15,000 FEET BELOW SEA LEVEL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27774 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VOGTLE REGION: 2 |NOTIFICATION DATE: 09/11/94 | |UNIT: [1] [ ] [ ] STATE: GA |NOTIFICATION TIME: 02:10 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/94 | +------------------------------------------------+EVENT TIME: 00:36[EDT]| |NRC NOTIFIED BY: MEYER |LAST UPDATE DATE: 09/11/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM CLINE 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 | A/R Y 1 STARTUP | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT HAD A REACTOR TRIP FROM <1% POWER(5X10E5 AMPS) WHILE THEY WERE | | SHUTTING DOWN FOR THEIR REFUELING OUTAGE. | | | | THE TRIP WAS CAUSED BY SPIKING OF THE N-32 SOURCE RANGE NUCLEAR INSTRUMENT. | | INVESTIGATION OF THE CAUSE AND REPAIR IS IN PROGRESS. THEY SUSPECT THAT THE | | CAUSE WAS POSSIBLY DUE TO A PROBLEM WITH THE DETECTOR OR A CONNECTOR. | | ALL RODS FULLY INSERTED AND THERE WAS NO INJECTION AND NO SAFETY RELIEF | | VALVES LIFTED. THE AUX FEED WATER WAS IN SERVICE PRIOR TO THE REACTOR TRIP | | AND THERE WAS NO ESF ACTUATION. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+