U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/11/95 - 09/12/95 ** EVENT NUMBERS ** 29314 29315 29316 29317 29318 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29314 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SEQUOYAH REGION: 2 |NOTIFICATION DATE: 09/11/95 | |UNIT: [1] [2] [ ] STATE: TN |NOTIFICATION TIME: 11:22 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/11/95 | +------------------------------------------------+EVENT TIME: 10:25[EDT]| |NRC NOTIFIED BY: GEORGE SANDERS |LAST UPDATE DATE: 09/11/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KEN BARR 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ALL FOUR EMERGENCY DIESEL GENERATOR (EDG) HEAD BOLTS TORQUED BY A HYDRAULIC | | TORQUE WRENCH WHICH WAS OUT OF CALIBRATION BY 30%. EDGS 1A, 1B, & 2B | | DECLARED INOPERABLE. | | | | MAINTENANCE TESTING AND EQUIPMENT REPORT DATED 08/10/95 (EQUIPMENT # | | 540600-ASSIGNMENT # 95-1079.1) INDICATED THAT HYDRAULIC TORQUE WRENCH | | 540600 WAS FOUND OUT OF CALIBRATION BY APPROXIMATELY 30% ON THE HIGH END | | RANGE. THE CALIBRATION REPORT COVERS DATES FROM 01/24/95 TO 08/03/95. | | DURING THIS PERIOD ALL FOUR EDG SETS (ALL 8 ENGINES/2 PER SET, BRUCE GM | | ELECTROMOTIVES) HAD AN 18 MONTH REQUIRED INSPECTION PERFORMED. THE | | INSPECTION REQUIRES THE POWER PACK CRAB BOLT NUT (HEAD BOLTS) BE LOOSENED | | ONE FLAT AND THEN TORQUED TO 1800 Ft-lbs. THE OUT-OF-CAL TORQUE WRENCH | | WOULD ONLY REACH 1270 Ft-lbs AND NOT THE REQUIRED 1800 Ft-lbs. | | FIELD DATA WAS TAKEN DURING THE RETORQUING OF THE 2A-A DIESEL GENERATOR. | | THE POWER PACK CRAB BOLTS ON 2A-A EDG WERE RETORQUED TO THE REQUIRED 1800 | | Ft-lbs AND THE 2A-A EDG WAS DECLARED OPERABLE AT 1015ET. | | EVALUATION OF THE FIELD FROM 2A-A EDG RETORQUING INDICATES THAT THE | | "AS-FOUND" TORQUE VALUES WERE IN THE VICINITY OF THE 1270 Ft-lbs FOUND IN | | THE MAINTENANCE TESTING AND EQUIPMENT REPORT DATED 08/10/95. | | DISCUSSIONS WITH THE EDG VENDOR (EMD) INDICATES THAT A EDG WITH POWER PACK | | CRAB BOLT NUTS TORQUED TO 1270 Ft-lbs WOULD NOT BE CAPABLE OF A 100 HOUR | | CONTINUOUS RUN. BASED ON THE ABOVE FIELD DATA, THE 1A-A, 1B-B, AND 2B-B EDG | | POWER PACK CRAB BOLT NUTS ARE BELIEVED TO BE IN A SIMILAR "AS-FOUND" | | CONDITION. (ie NOT TORQUED TO THE REQUIRED 1800 Ft-lbs). | | THEREFORE, THE 1A-A, 1B-B, AND 2B-B EDGs WOULD NOT BE CAPABLE OF PERFORMING | | THEIR INTENDED FUNCTION. (ie A LONG CONTINUOUS RUN). | | LICENSEE DECLARED EDGs 1A-A, 1B-B, & 2B-B INOPERABLE AND ENTERED TECH SPEC | | 3.8.1.1 E (TWO HOURS TO GET 1A-A EDG OPERABLE OR HAVE TO SHUTDOWN). IF 1A-A | | EDG IS RESTORED WITHIN 2 HOURS LICENSEE WILL STILL BE IN TECH SPEC 3.8.11 B | | (72 HOURS TO RESTORE EDGs 1B-B AND 2B-B TO AN OPERABLE STATUS) | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | ***UPDATE AT 2131 @ 9/11/95 BY MARSHALL TO GOULD***THE LICENSEE IS | | RETRACTING THIS EVENT SINCE THEY HAVE DETERMINED THAT THE DIESELS WERE NOT | | INOPERABLE BECAUSE THE CRAB BOLT NUTS HAD NOT BEEN UNDER TORQUED. THE 2A-A | | UNIT'S CRAB BOLT NUTS WHICH HAD BEEN RETORQUED WITH AN IMPROPERLY | | CALIBRATED TORQUE WRENCH WAS OVER TORQUED TO ~2200 FT-LBS BUT THE | | MANUFACTURER SAID THAT IT WOULD NOT AFFECT THE OPERABILITY OF THE UNIT. THE | | RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29315 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 09/11/95 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 11:31 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 09/11/95 | +------------------------------------------------+EVENT TIME: 08:45[EDT]| |NRC NOTIFIED BY: MCCARTNEY |LAST UPDATE DATE: 09/11/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR 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 N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE NOTIFIED THE STATE OF NORTH CAROLINA DEPARTMENT OF | | ENVIRONMENT, HEALTH AND NATURAL RESOURCES OF A NATIONAL POLLUTANT DISCHARGE | | ELIMINATION SYSTEM NONCOMPLIANCE CONDITION. | | | | THE NOTIFICATION WAS MADE AT 08:45 @ 9/11/95 TO THE STATE OF NORTH | | CAROLINA, DEPT OF ENVIRONMENT, HEALTH AND NATURAL RESOURCES, WATER QUALITY | | SECTION PERTAINING TO A NATIONAL POLLUTANT DISCHARGE ELIMINATION | | SYSTEM(HARRIS NDPES PERMIT #NC0039586) NONCOMPLIANCE CONDITION. THE OUT OF | | SPECIFICATION PARAMETER WAS ZINC AT THE COOLING TOWER BLOWDOWN OUTFALL. THE | | LIMIT IS 1PPM. SAMPLING AND ANALYSIS AT 16:45 @ 9/8/95 REVEALED THAT A | | CONCENTRATION OF 3PPM ZINC WAS PRESENT IN THE COOLING TOWER BASIN. THE | | INCREASE IN ZINC CONCENTRATION WAS CAUSED BY A PH EXCURSION(PH DECREASED | | FROM ~6 TO ~ 3) ON 9/8/95 THAT "ACID SHOCKED" THE SERVICE WATER PIPING, | | RESULTING IN THE RELEASE OF ZINC INTO THE COOLING TOWER BASIN. THE CAUSE OF | | THE PH DECREASE IS STILL UNDER INVESTIGATION. THE ZINC CONCENTRATION WAS | | RESTORED TO WITHIN PERMIT LIMITATIONS AT 23:45 @ 9/10/95. MONITORED ZINC AT | | THE OUT FALL TO THE LAKE WAS .026PPM. THE RI WAS INFORMED. | | | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29316 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 09/11/95 | |UNIT: [1] [ ] [ ] STATE: PA |NOTIFICATION TIME: 13:09 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 09/11/95 | +------------------------------------------------+EVENT TIME: 12:50[EDT]| |NRC NOTIFIED BY: FORST |LAST UPDATE DATE: 09/12/95 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |WILLIAM RULAND RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |CHAFFEE EO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS |CALDWELL FEMA | |ADEG 50.72(b)(1)(ii) DEGRAD COND DURING OP | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE MANUALLY SCRAMMED THE REACTOR DUE TO A STUCK OPEN MAIN STEAM | | LINE SAFETY RELIEF VALVE. | | | | THE LICENSEE DECLARED AN UNUSUAL EVENT DUE TO SAFETY RELIEF VALVE | | (PSV-41-1F013M) FAILING OPEN WHILE THE PLANT WAS AT 100% POWER. THEY | | ATTEMPTED TO REDUCE REACTOR PRESSURE TO CLOSE THE VALVE, BUT THE VALVE | | REMAINED OPENED, SO THE REACTOR WAS MANUALLY SCRAMMED FROM 100% POWER. ALL | | CONTROL RODS FULLY INSERTED INTO THE CORE. APPROXIMATELY 10 MINS AFTER THE | | SCRAM, THE REACTOR VESSEL PRESSURE DECREASED TO 500LBS AT WHICH TIME THE | | OUTBOARD MSIV'S WERE CLOSED. THE SAFETY RELIEF VALVE CONTINUED TO STAY OPEN | | AFTER THE MSIV'S WERE CLOSED (REACTOR VESSEL PRESSURE CONTINUED TO | | DECREASE). SAFETY RELIEF VALVE (PSV-41-1F013M) FINALLY CLOSED STABILIZING | | REACTOR VESSEL PRESSURE AT 370LBS. THE CAUSE OF THE SAFETY RELIEF VALVE | | FAILING OPEN IS UNKNOWN AND BEING INVESTIGATED. THE RI WAS INFORMED ALONG | | WITH STATE AND LOCAL AGENCIES. THERE WILL ALSO BE A PRESS RELEASE. | | | | ***UPDATE AT 14:57 BY KLENK TO GOULD*** THE PLANT IS GOING TO A COLD S/D | | CONDITION. THE LICENSEE BELIEVES THAT SAFETY RELIEF VALVE (PSV-41-1F013M) | | MAY STILL BE OPEN, ALTHOUGH THEY HAVE INDICATIONS THAT THE SAFETY RELIEF | | VALVE IS CLOSED, SINCE REACTOR VESSEL PRESSURE HAS DECREASED TO 110LBS AND | | IS CONTINUING TO DECREASE. LICENSEE WILL EXIT THE UNUSUAL EVENT | | CLASSIFICATION WHEN THEY HAVE PLACED SHUTDOWN COOLING INTO SERVICE. THE RI | | WAS INFORMED. | | | | ***UPDATE AT 15:21 BY BRAUN TO GOULD*** THE LICENSEE UPDATED THIS EVENT TO | | INCLUDE A TS REQUIRED S/D, DEGRADED CONDITION, AND RPS ACTUATION AS PART OF | | THEIR REPORTABILITY REQUIREMENTS. THEY ALSO STATED THAT DURING THE | | TRANSIENT, THE PLANT EXCEEDED THE TS COOLDOWN RATE. THE RI WAS INFORMED. | | | | ***UPDATE AT 0231 ET 09/12/95 BY JIM HUTTON TAKEN BY MACKINNON*** UNUSUAL | | EVENT TERMINATED AT 0227 ET WHEN LICENSEE ESTABLISHED SHUTDOWN COOLING. | | LICENSEE IS USING "B" RHR PUMP FOR SHUTDOWN COOLING. "A" RHR PUMP SHOWED | | ABNORMAL FLOW CHARACTERISTICS WHEN RUNNING IN THE SUPPRESSION POOL COOLING | | MODE OF OPERATION. LICENSEE IS STILL USING "A" RHR PUMP FOR SUPPRESSION | | COOLING BUT THEY CONSIDER THE PUMP TECHNICALLY INOPERABLE. LICENSEE SAID | | THAT THEIR OTHER TWO RHR PUMPS ARE FULLY OPERABLE IF NEEDED. ALL OTHER ECCS | | SYSTEMS, AND THEIR EDGs ARE FULLY OPERABLE. THE SAFETY RELIEF VALVE WHICH | | OPENED IS LOCATED ON MAIN STEAM LINE "D" AND THE LICENSEE SAID THAT THEY | | DID NOT KNOW AT THE PRESENT TIME WHY THE SAFETY RELIEF VALVE OPENED. | | COOLDOWN RATE FOR THE FIRST HOUR AFTER THE REACTOR SCRAM WAS 150 DEGREES F | | (TECH SPEC LIMIT IS 100 DEGREES F). SHIFT SUPERVISOR SAID THAT WHEN HE CAME | | ON SHIFT WHICH IS 1830 ET SUPPRESSION POOL TEMPERATURE WAS 108 DEGREES F | | AND DECREASING (THEY WERE ALREADY IN SUPPRESSION POOL COOLING MODE OF | | OPERATION). LICENSEE WILL NOTIFY MONTGOMERY COUNTY, CHESTER COUNTY, BERKS | | COUNTY, AND THE STATE OF PENNSYLVANIA EMERGENCY MANAGEMENT OF THE | | TERMINATION OF THEIR UNUSUAL EVENT. R1DO (BILL RULAND), EO(JOSE CALVO), & | | FEMA (BERNICE CARR) NOTIFIED. | | | | RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29317 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 09/11/95 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 14:34 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/11/95 | +------------------------------------------------+EVENT TIME: 13:51[EDT]| |NRC NOTIFIED BY: MLACHAK |LAST UPDATE DATE: 09/11/95 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MADERA RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP/REACTOR SCRAM DUE TO RCIC INJECTION INTO REACTOR | | VESSEL AT POWER. | | | | AN AUTOMATIC TURBINE TRIP AND REACTOR SCRAM OCCURRED WHEN THE REACTOR CORE | | ISOLATION COOLING (RCIC) SYSTEM AUTOMATICALLY STARTED AND INJECTED TO THE | | REACTOR VESSEL DUE TO THE FAILURE OF AN INSTRUMENT POWER SUPPLY. ALL | | CONTROL RODS INSERTED FOLLOWING THE SCRAM. BOTH TURBINE-DRIVEN REACTOR | | FEED PUMPS ALSO TRIPPED DUE TO THE RCIC INJECTION, AND REACTOR VESSEL LEVEL | | DECREASED TO THE LEVEL 2 SETPOINT (+130" ABOVE TAF), RESULTING IN THE | | AUTOMATIC INITIATION OF AND INJECTION BY THE HIGH PRESSURE CORE SPRAY | | (HPCS) SYSTEM. REACTOR VESSEL LEVEL HAS BEEN RECOVERED AND IS CURRENTLY | | BEING MAINTAINED USING THE MOTOR-DRIVEN FEEDWATER PUMP. ALL OTHER SYSTEMS | | FUNCTIONED AS EXPECTED. | | | | THE LICENSEE STATED THAT THE EVENT WAS CAUSED BY THE FAILURE OF AN ECCS | | DIVISION II INSTRUMENT POWER SUPPLY (E12-K701). THIS POWER SUPPLY HAD | | PREVIOUSLY FAILED ON 8/31/95, RESULTING IN A RCIC INJECTION AND TURBINE | | TRIP/REACTOR SCRAM, AND HAD BEEN REPLACED. [SEE SIMILAR EVENT #29264 ON | | 8/31/95.] THE LICENSEE IS CURRENTLY INVESTIGATING THE CAUSE OF THE POWER | | SUPPLY FAILURE. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | | | | ***UPDATE AT 15:58 BY MLACHAK TO GOULD*** THE LICENSEE WILL BE MAKING A | | PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 29318 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/12/95 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 04:39 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/12/95 | +------------------------------------------------+EVENT TIME: 03:00[CDT]| |NRC NOTIFIED BY: JOE WALECH |LAST UPDATE DATE: 09/12/95 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN MADERA RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 6 STARTUP | 6 STARTUP | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION SHUTDOWN DUE TO HPCI BEING DECLARED INOPERABLE. | | | | ON SEPTEMBER 11, 1995 AT 2355 CDT WHILE PERFORMING THE LOW PRESSURE HPCI | | SURVEILLANCE TEST DURING REACTOR STARTUP, A HPCI EXHAUST DRAIN POT HIGH | | LEVEL ALARM WAS RECEIVED AND WOULD NOT CLEAR. THE HPCI TURBINE WAS MANUALLY | | TRIPPED AND THE HPCI SYSTEM WAS SUBSEQUENTLY DECLARED INOPERABLE. DUE TO | | THE LICENSEE'S INABILITY TO COMPLETE HPCI LOW PRESSURE STARTUP TESTING | | WITHIN THE 12 HOUR STARTUP TIME CLOCK FOR HPCI, AN ORDERLY SHUTDOWN WAS | | INITIATED AT 0300 CDT ON SEPTEMBER 12, 1995. THE CAUSE OF THE EXHAUST DRAIN | | POT HIGH LEVEL IS UNKNOWN AT THIS TIME AND AN INVESTIGATION IS UNDERWAY. | | LICENSEE IS IN TECHNICAL SPECIFICATION 3.5.C.3 (WHICH STATES THAT WITH HPCI | | DECLARED INOPERABLE REACTOR VESSEL DOME PRESSURE MUST BELOW 150 psig WITHIN | | THE NEXT 24 HOURS) AND ALSO IN A TECHNICAL SPECIFICATION REQUIRED SHUTDOWN. | | | | RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+