U.S. Nuclear Regulatory Commission Operations Center Event Reports For 03/06/97 - 03/07/97 ** EVENT NUMBERS ** 31894 31898 31900 31901 31902 31903 31904 31905 31906 31907 31908 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31894 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 03/05/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 12:26 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/05/97 | +------------------------------------------------+EVENT TIME: 11:20[EST]| |NRC NOTIFIED BY: JOHN JENKINS |LAST UPDATE DATE: 03/06/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION DUE TO EVACUATION OF THE SITE ENVIRONMENTAL LABS | | BUILDING FOLLOWING THE DISCOVERY OF APPROXIMATELY 50 GRAMS OF PICRIC ACID | | IN AN UNSTABLE (EXPLOSIVE) FORM | | | | IT WAS DISCOVERED THAT APPROXIMATELY 50 GRAMS OF PICRIC ACID IN THE SITE | | ENVIRONMENTAL LABS BUILDING HAD BECOME UNSTABLE (EXPLOSIVE). THE PICRIC | | ACID IS CURRENTLY IN A CRYSTALLINE STATE AND IS CONSIDERED TO BE VERY | | UNSTABLE. THE CONTROL ROOM WAS NOTIFIED OF THIS DISCOVERY AT 1120, AND | | EVACUATION OF THE BUILDING WAS CONFIRMED TO BE COMPLETE AT APPROXIMATELY | | 1215. | | | | THE SITE ENVIRONMENTAL LABS BUILDING IS LOCATED INSIDE THE LICENSEE'S OWNER | | CONTROLLED AREA OUTSIDE THE FACILITY'S PROTECTED AREA. AS A RESULT, THE | | LICENSEE BELIEVES THAT THIS EVENT WILL NOT IMPACT SAFE OPERATION. | | | | IN ADDITION TO THE CITY OF CHARLOTTE HAZMAT TEAM, THE LICENSEE NOTIFIED THE | | SURROUNDING COUNTIES, THE STATE OF NORTH CAROLINA, AND THE NRC RESIDENT | | INSPECTOR. THE CITY OF CHARLOTTE HAZMAT TEAM WAS DISPATCHED TO THE SCENE. | | A PRESS RELEASE MAY BE ISSUED BY THE LICENSEE. | | | | * * * UPDATE 0142 3/6/97 FROM TRACEY TAKEN BY STRANSKY * * * | | | | THE ACID HAS BEEN RESTABILIZED AND DILUTED SO THAT IT DOES NOT POSE ANY | | FURTHER FIRE OR EXPLOSION HAZARD. THE DILUTED ACID HAS BEEN MOVED TO THE | | LICENSEE'S HAZARDOUS WASTE STORAGE AREA. THE NRC RESIDENT HAS BEEN | | INFORMED. NOTIFIED R2DO (PEEBLES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 31898 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/05/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 19:28 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/05/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:04[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/06/97 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |GEOFFREY WRIGHT RDO | | DOCKET: 0707002 |DONALD COOL, NMSS EO | +------------------------------------------------+FRANK CONGEL, IRD AEOD | |NRC NOTIFIED BY: KEITH WILLIAMSON | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NONR OTHER UNSPEC REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISCELLANEOUS 4-HOUR REPORT - NOTIFICATION OF OFFSITE AGENCIES DUE TO LIME | | SLUDGE LAGOON TOTAL SUSPENDED SOLIDS IN EXCESS OF NATIONAL POLLUTION | | DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT LIMITS | | | | RESULTS FROM SAMPLES TAKEN ON MARCH 3, 1997, AT THE X-611B LIME SLUDGE | | LAGOON (NPDES OUTFALL #005) INDICATED THAT THE TOTAL SUSPENDED SOLIDS | | EXCEEDED PERMIT LIMITS DUE TO EXTREME AMOUNTS OF RAINFALL WHICH CAUSED THE | | LAGOON TO OVERFLOW. THE MEASURED VALUE WAS 43.4 MILLIGRAMS PER LITER, AND | | THE NPDES LIMIT IS 15.0 MILLIGRAMS PER LITER. | | | | OVERFLOW FROM THE LAGOON WOULD FLOW TO THE LITTLE BEAVER CREEK AND | | EVENTUALLY TO THE SCIOTO RIVER. THIS ISSUE INVOLVED SUSPENDED SOLIDS (MUD | | AND SLUDGE) ONLY. THERE WERE NO HAZARDOUS MATERIALS OR RADIOACTIVE | | CONTAMINATION THREATS ASSOCIATED WITH THIS INCIDENT. | | | | AS A RESULT, AN IMMEDIATE NOTIFICATION WAS MADE TO THE OHIO ENVIRONMENTAL | | PROTECTION AGENCY. THE LICENSEE ALSO NOTIFIED THE DEPARTMENT OF ENERGY AND | | THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31900 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 03/06/97 | |UNIT: [ ] [2] [ ] STATE: MI |NOTIFICATION TIME: 04:52 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 04:10[EST]| |NRC NOTIFIED BY: CHA |LAST UPDATE DATE: 03/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WRIGHT RDO | |ADEV 50.72(b)(1)(i)(B) DEVIATION FROM T SPEC | | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH CONTROL ROOM PRESSURIZATION FANS INOPERABLE | | | | "UNIT 2 ENTERED TECH SPEC 3.0.3 ACTION STATEMENT WHEN IT WAS DISCOVERED | | THAT BOTH CONTROL ROOM PRESSURIZATION FANS WERE INOPERABLE DUE TO THEIR | | INABILITY TO DELIVER THE DESIGN AIR FLOW. THE CONDITION WAS DISCOVERED WHEN | | A PLEXIGLAS BASIN, PLACED UNDER CONTROL ROOM PRESSURIZATION FAN INLET | | LOUVER FROM CONTROL ROOM, WOULD BLOCK THE DUCT LOUVER AREA WHEN CONTROL | | ROOM PRESSURIZATION FANS WERE PLACED IN SERVICE. NOT THE ENTIRE DUCT LOUVER | | INLET AREA WAS BLOCKED. HOWEVER, THE ABILITY FOR BOTH FANS TO DELIVER | | DESIGN FLOW WAS JEOPARDIZED DUE TO OBSTRUCTION." | | | | THE T.S. ACTION STATEMENT WAS EXITED WHEN THE BASIN WAS REMOVED. THE NRC | | RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31901 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/06/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 07:44 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 05:17[EST]| |NRC NOTIFIED BY: TOM WALLACE |LAST UPDATE DATE: 03/06/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE REACTOR TRIPPED FROM 67% POWER DUE TO A LOW LOW LEVEL IN A STREAM | | GENERATOR AND ALL AUXILIARY FEED PUMPS STARTED. | | | | AN INSTANTANEOUS BEARING FAILURE CAUSED THE LOSS OF THE "1B" MAIN FEED | | PUMP. THIS INITIATED AN AUTOMATIC PLANT RUNBACK TO LESS THAN 80% POWER. | | THE STANDBY FEED PUMP WAS UNAVAILABLE DUE TO MAINTENANCE, THEREFORE, THE | | OPERATORS CONTINUED TO RUN BACK MANUALLY TO 67% POWER. DESPITE THESE | | ACTIONS THE LEVEL IN THE NUMBER 4 STEAM GENERATOR CONTINUED TO DECREASE. | | WHEN TO LOW LOW LEVEL SETPOINT WAS REACHED AN AUTOMATIC REACTOR TRIP | | OCCURRED. AUX FEEDWATER STARTED AUTOMATICALLY FOLLOWING THE TRIP AND | | RETURNED STEAM GENERATOR LEVELS TO NORMAL. ALL CONTROL RODS INSERTED FULLY | | FOLLOWING THE TRIP. DECAY HEAT REMOVAL IS VIA THE MAIN CONDENSER. THE | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31902 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 03/06/97 | |UNIT: [ ] [ ] [3] STATE: AZ |NOTIFICATION TIME: 10:03 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 07:15[MST]| |NRC NOTIFIED BY: K. ROBERSON |LAST UPDATE DATE: 03/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |BARNES RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |DENNIG EO | | |WRIGHT FEMA | | |CONGEL IRD AEOD | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 REFUELING | 0 REFUELING | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO PARTIAL DRAINDOWN OF SPENT FUEL POOL | | | | AT 0625 MST, THE LICENSEE RECEIVED AN ALARM THAT THE WATER LEVEL IN THE | | SPENT FUEL POOL WAS DECREASING, AND WORKERS WERE DISPATCHED TO INVESTIGATE | | AND CORRECT THE PROBLEM. THE LICENSEE DETERMINED THAT AN INFLATABLE SEAL | | ASSOCIATED WITH THE GATE BETWEEN THE SPENT FUEL POOL AND THE TRANSFER CANAL | | HAD LOW AIR PRESSURE. THE INITIAL POOL WATER LEVEL WAS 24' ABOVE THE TOP OF | | FUEL (138' ELEVATION), AND DECREASED BY ONE FOOT BEFORE THE LEAKAGE WAS | | TERMINATED AT APPROXIMATELY 0715 MST. NO INCREASED RADIATION LEVELS WERE | | DETECTED AS A RESULT OF THE LEVEL DECREASE. | | | | CONTROL ROOM PERSONNEL ENTERED AND EXITED THE UNUSUAL EVENT AT 0715 MST, | | AFTER DETERMINING THAT THE EVENT HAD MET AN ENTRY CONDITION (EMERGENCY | | CLASSIFICATION RAD-3). THE LICENSEE STATED THAT THE TECHNICAL SPECIFICATION | | SPENT FUEL POOL MINIMUM WATER LEVEL (137' ELEVATION) WAS NOT VIOLATED | | DURING THE EVENT. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE | | LICENSEE. | | | | ***UPDATE ON 3/6/97 @ 1244 BY ROBERSON TO GOULD*** THE LICENSEE ORIGINALLY | | STATED THAT "NO ESF ACTUATIONS OCCURRED AND NONE WERE REQUIRED", BUT PER | | ABNORMAL OPERATING PROCEDURE RELATED TO DECREASE IN SPENT FUEL POOL LEVEL, | | A MANUAL FUEL BUILDING ESSENTIAL VENTILATION ACTUATION SYSTEM WAS ACTUATED | | AT 0643 MST. ONE DAMPER HAD TO BE MANUALLY OPENED TO ITS ACTUATED | | POSITION. THE RESIDENT INSPECTOR WAS NOTIFIED. REG 4 RDO(BARNES) WAS | | NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31903 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CRYSTAL RIVER REGION: 2 |NOTIFICATION DATE: 03/06/97 | |UNIT: [3] [ ] [ ] STATE: FL |NOTIFICATION TIME: 11:41 [ET]| |RX TYPE: [3] B&W-L-LP |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 10:35[EST]| |NRC NOTIFIED BY: LARRY MOFFATT |LAST UPDATE DATE: 03/06/97 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE HAS DISCOVERED THAT TEMPERATURES INSIDE THE REACTOR BUILDING | | AND THE AUXILIARY BUILDING CAN FALL BELOW THE RANGE OF TEMPERATURES USED IN | | THE INSTRUMENTATION UNCERTAINTY CALCULATIONS. UNTIL THE IMPACT ON | | ENGINEERED SAFEGUARDS SYSTEMS IS ANALYZED, THE LICENSEE CONSIDERS ALL | | INSTRUMENTATION LOCATED IN THESE BUILDINGS DEGRADED. | | | | THE INSTRUMENTATION LOCATED IN THE REACTOR BUILDING AND AUX BUILDING ARE | | CALIBRATED TO BE ACCURATE OVER AN ENVIRONMENTAL TEMPERATURE RANGE OF 70øF | | TO 119øF. THE LICENSEE OBSERVED AN AMBIENT TEMPERATURE INSIDE THE REACTOR | | BUILDING OF 41øF. THIS COULD RESULT IN INSTRUMENT UNCERTAINTIES THAT WOULD | | BE NONCONSERVATIVE FOR ACTUAL ENVIRONMENTAL CONDITIONS. THIS CONCERN | | INCLUDES THE ENGINEERED SAFEGUARDS SYSTEM. THE LICENSEE IS EVALUATING THE | | EFFECTS OF ACTUAL TEMPERATURE VARIATIONS ON INSTRUMENT UNCERTAINTY | | CALCULATIONS. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 31904 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: RADIOLOGY MEDICAL GROUP |NOTIFICATION DATE: 03/06/97 | | CITY: SAN DIEGO REGION: 4 |NOTIFICATION TIME: 13:00 [ET]| | COUNTY: STATE: CA |EVENT DATE: 02/27/97 | |LICENSE#: 0389-80 AGREEMENT: Y |EVENT TIME: 11:30[PST]| | DOCKET: |LAST UPDATE DATE: 03/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |IAN BARNES RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: CANTADA | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |LADM 35.33(a) MED MISADMINISTRATION | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED A MEDICAL MISADMINISTRATION OCCURRED WHEN THE | | TECHNICIAN GAVE A PATIENT A BONE IMAGING AGENT (20 mCi OF TECHNETIUM 99m | | DP) INSTEAD OF THE PRESCRIBED LUNG IMAGING AGENT(4 mCi OF TECHNETIUM 99m | | AA). THERE WILL BE NO ADVERSE AFFECTS TO THE PATIENT AND BOTH THE PATIENT | | AND PRESCRIBING PHYSICIAN WERE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31905 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SALEM REGION: 1 |NOTIFICATION DATE: 03/06/97 | |UNIT: [1] [2] [ ] STATE: NJ |NOTIFICATION TIME: 13:25 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 10:15[EST]| |NRC NOTIFIED BY: ROBERTSON |LAST UPDATE DATE: 03/06/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DANIEL HOLODY 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE WILL NOTIFIED THE STATES OF NEW JERSEY AND DELAWARE THAT A | | LICENSEE EMPLOYEE CAME TO WORK AND SET OFF THE CONTAMINATION MONITOR ALARM. | | | | THE EMPLOYEE ENTERED THE SECURITY CENTER ON HIS WAY TO WORK AND SET OFF A | | CONTAMINATION MONITOR ALARM, MEASURING APPROXIMATELY 100 COUNTS ABOVE | | BACKGROUND. THE INDIVIDUAL WAS NOT ALLOWED INTO THE FACILITY, BUT HE WAS | | ESCORTED TO THE PROCESSING CENTER FOR AN EVALUATION AND FOLLOW-UP SURVEY. | | AT THIS POINT AND TIME, WHETHER OR NOT THE RADIOACTIVE CONTAMINATION IS | | NATURAL OCCURRING OR FROM ANOTHER SOURCE, HAS NOT BEEN DETERMINED. THE | | INDIVIDUAL HAS NOT BEEN IN THE RADIOLOGICALLY CONTROLLED AREA SINCE 2/7/97. | | THE INDIVIDUAL WAS AT WORK THE PREVIOUS DAY AND HAD NO PROBLEMS ENTERING OR | | EXITING THE FACILITY. HIS WORK AREAS HAVE BEEN SURVEYED AND THERE IS NO | | DETECTABLE CONTAMINATION. THE RESIDENT INSPECTOR HAS BEEN INFORMED AND | | LOWER ALLOWAYS CREEK TOWNSHIP WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31906 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 03/06/97 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 16:17 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 15:10[EST]| |NRC NOTIFIED BY: MAY |LAST UPDATE DATE: 03/06/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DANIEL HOLODY RDO | |AINB 50.72(b)(2)(iii)(B) POT RHR INOP | | |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 +------------------------------------------------------------------------------+ | THE LICENSEE IDENTIFIED A CONDITION THAT COULD COMPROMISE THE RHR | | OPERABILITY AND ACCIDENT MITIGATION CAPABILITY. | | | | DURING A REVIEW OF FSAR SECTION 24 AND AN ASSOCIATED REVIEW OF THE RHR | | SYSTEM PROCEDURE (OP 2124), IT WAS DISCOVERED THAT THE PROCEDURE ALLOWED A | | CONDITION CONTRARY TO THE FSAR. SPECIFICALLY, THE PROCEDURE ALLOWS FOR THE | | USE OF AN ALTERNATE KEEP-FILL LINEUP WHICH DOES NOT CONTAIN ANY CHECK | | VALVES OR AUTOMATIC VALVES, NOR IS IT SEISMICALLY QUALIFIED. THIS LINEUP | | VIOLATES REQUIREMENTS FOR AUTOMATIC POSITIONING OF SYSTEM VALVES TO SUPPORT | | THE LPCI MODE OF OPERATION. SHOULD A SEISMIC EVENT OCCUR WHILE IN THIS | | ALTERNATE LINEUP, A SIGNIFICANT LOSS OF LPCI FLOW COULD RESULT. | | | | CORRECTIVE ACTION TAKEN WAS TO INFORM OPERATIONS PERSONNEL NOT USE THE | | CONDENSATE TRANSFER SYSTEM TO MAINTAIN THE RHR SYSTEM PRESSURIZED. | | | | THE RESIDENT INSPECTOR WILL BE NOTIFIED ALONG THE VERMONT DEPT OF PUBLIC | | SERVICE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31907 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WATTS BAR REGION: 2 |NOTIFICATION DATE: 03/06/97 | |UNIT: [1] [ ] [ ] STATE: TN |NOTIFICATION TIME: 18:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 03/06/97 | +------------------------------------------------+EVENT TIME: 17:43[EST]| |NRC NOTIFIED BY: WALLACE |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |THOMAS PEEBLES RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |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 HOT STANDBY | 0 HOT STANDBY | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE PLANT REPORTED THAT THEY HAD AN ECCS INJECTION WHILE COOLING DOWN FROM | | MODE 3 TO MODE 4. | | | | DURING PLANT COOLDOWN TO MODE 4 FROM MODE 3, THEY EXPERIENCED A SAFETY | | INJECTION SIGNAL DUE TO LOW STEAM LINE PRESSURE(<675 PSIG). THE INITIATION | | SIGNAL OCCURRED BEFORE THEY COULD BLOCK IT. ECCS DID INJECT TO THE RCS | | THROUGH THE HIGH HEAD INJECTION PATH, BUT THE VOLUME OF WATER INJECTED IS | | UNKNOWN AT THIS TIME. THE SAFETY INJECTION SIGNAL WAS TERMINATED WITHIN | | ELEVEN MINUTES. ALL OTHER ESF EQUIPMENT ACTUATED, FUNCTIONED AS DESIGNED, | | AND WAS SECURED WITHIN ELEVEN MINUTES. THE PLANT WILL CONTINUE TO COOLDOWN | | TO MODE 5 AFTER ESF EQUIPMENT IS REALIGNED. THE RESIDENT INSPECTOR WILL BE | | NOTIFIED. | | | | * * * UPDATE ON 3/6/97 @ 2338 BY EARLES TO GOULD * * * | | | | WHILE RECOVERING FROM THE INITIAL EVENT, THE SAFETY INJECTION (SI) FUNCTION | | WAS BLOCKED IN ACCORDANCE WITH PLANT PROCEDURES. HOWEVER, AT APPROXIMATELY | | 2022, AN INVALID 'B' TRAIN SI SIGNAL WAS INITIATED. DUE TO THIS SIGNAL ECCS | | EQUIPMENT INCREASED RCS PRESSURE ABOVE 1970 PSIG, RESETTING THE SI BLOCK | | FUNCTION. CONCURRENT WITH THIS, STEAM GENERATOR PRESSURE HAD DROPPED BELOW | | 675 PSIG DUE TO PLANT COOLDOWN. THIS GENERATED A SIGNAL WHICH INITIATED AN | | 'A' TRAIN SI. TROUBLESHOOTING OF THE SOLID STATE PROTECTION SYSTEM HAS | | BEGUN TO IDENTIFY THE SOURCE OF THE INVALID SIGNAL. CURRENT PLANT | | CONDITIONS ARE SUCH THAT AUTOMATIC INITIATION ON AN SI HAS BEEN REINSTATED | | AND THE PLANT WILL BE MAINTAINED IN ITS PRESENT CONDITION UNTIL THE SOURCE | | OF THE INVALID SIGNAL IS IDENTIFIED. | | | | THE RESIDENT INSPECTOR AND REG 2 RDO (PEEBLES) WERE NOTIFIED. | | | | * * * UPDATE 0530 3/7/97 FROM BUSHNELL TAKEN BY STRANSKY * * * | | | | AT 0419, WHILE TROUBLESHOOTING THE SSPS TO DETERMINE THE CAUSE OF THE | | SECOND SI MENTIONED ABOVE, AN 'A' TRAIN SI OCCURRED. AT THE TIME OF THE | | EVENT, THE 'B' TRAIN OF SI WAS OUT OF SERVICE FOR THE TEST, AND THE 'A' | | TRAIN LOGIC WAS BLOCKED. THE LICENSEE STATED THAT SOME QUANTITY OF WATER | | WAS INJECTED TO THE RCS, BUT DID NOT KNOW HOW MUCH. TROUBLESHOOTING | | ACTIVITIES ARE CONTINUING. THE NRC RESIDENT INSPECTOR WILL BE INFORMED BY | | THE LICENSEE. NOTIFIED R2DO (PEEBLES). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 31908 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 03/07/97 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 02:04 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 03/07/97 | +------------------------------------------------+EVENT TIME: 00:58[CST]| |NRC NOTIFIED BY: SOKOL |LAST UPDATE DATE: 03/07/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |McCORMICK-BARGER 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 HOT STANDBY | 0 HOT STANDBY | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNITS IN DEGRADED CONDITION WHILE TESTING EMERGENCY DIESEL GENERATORS | | | | THE LICENSEE HAS CONSERVATIVELY ENTERED TECHNICAL SPECIFICATION 15.3.0.b | | WHILE PERFORMING SURVEILLANCE TESTS ON THE G01 AND G02 EMERGENCY DIESEL | | GENERATORS (EDGs). EDG G04 HAS BEEN OUT OF SERVICE DUE TO A BEARING FAILURE | | IN THE GENERATOR. EDG G03 HAD BEEN PROVIDING STANDBY EMERGENCY POWER FOR | | BOTH UNITS. ON 2/28/97, THE EDG VENDOR INFORMED THE LICENSEE THAT THE | | BEARING FAILURE HAD BEEN CAUSED BY CIRCULATING CURRENTS IN THE GENERATOR | | SHAFT, AND THAT EDG G03 WAS SUSCEPTIBLE TO A SIMILAR FAILURE. (EDGs G01 AND | | G02 ARE NOT SUSCEPTIBLE TO THIS FAILURE MODE.) THE LICENSEE DECLARED EDG | | G03 INOPERABLE, AND PLANT TECHNICAL SPECIFICATIONS REQUIRE TESTING OF THE | | OPERABLE EDGs ON AN INCREASED FREQUENCY (EVERY 72 HOURS). | | | | SINCE EDGs G01 AND G02 ARE ASSOCIATED WITH THE 'A' TRAIN OF ESF EQUIPMENT | | ON THEIR RESPECTIVE UNITS, WHENEVER ONE OF THE EDGs IS BEING TESTED, NO | | STANDBY EMERGENCY POWER IS AVAILABLE TO THAT UNIT. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED OF THIS NOTIFICATION BY THE LICENSEE. | | | +------------------------------------------------------------------------------+