U.S. Nuclear Regulatory Commission Operations Center Event Reports For 08/08/97 - 08/11/97 ** EVENT NUMBERS ** 32667 32713 32740 32741 32742 32743 32744 32745 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32667 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 07/23/97 | |UNIT: [1] [2] [ ] STATE: IL |NOTIFICATION TIME: 16:41 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 07/23/97 | +------------------------------------------------+EVENT TIME: 13:30[CDT]| |NRC NOTIFIED BY: DAVE SHELDON |LAST UPDATE DATE: 08/08/97 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM GAVULA 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MISCELLANEOUS EQUIPMENT IN THE CONTROL ROOM FOUND NOT TO BE SEISMICALLY | | MOUNTED | | | | ENGINEERING HAS IDENTIFIED THAT SOME MISCELLANEOUS EQUIPMENT (CABINETS, | | CONTROL ROOM EMERGENCY BREATHING PACKS, CONTROL ROOM GAS MONITOR, etc.) FOR | | UNITS 1 & 2 ARE NOT SEISMICALLY MOUNTED. IF A SEISMIC EVENT WERE TO OCCUR, | | IT WAS DETERMINED THAT THIS EQUIPMENT COULD DAMAGE VITAL EQUIPMENT | | IMPORTANT TO THE SAFETY OF THE PLANT. IN THE CURRENT PLANT CONDITION, THE | | EQUIPMENT THAT WOULD BE DAMAGED FROM A SEISMIC EVENT IS NOT REQUIRED FOR | | PLANT SAFETY. THE EQUIPMENT WILL BE RELOCATED TO ACCEPTABLE AREAS UNTIL | | PROPER INSTALLATION CAN BE ENGINEERED. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE ON 07/23/97 @ 2256 BY DANIELS TAKEN BY MACKINNON * * * | | | | ALL EQUIPMENT WHICH COULD DAMAGE VITAL EQUIPMENT IF A SEISMIC EVENT | | OCCURRED HAS BEEN RELOCATED OR STORED IN THEIR PROPER LOCATION TO PREVENT | | THEM FROM DAMAGING VITAL EQUIPMENT IN THE CONTROL ROOM FOR UNITS 1 & 2. | | R3DO (GAVULA) NOTIFIED. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED OF THIS EVENT BY THE LICENSEE. | | | | ***UPDATE ON 8/8/97 @ 2102 BY WIEGING TO GOULD*** THE INITIAL NOTIFICATION | | STATED THERE WAS MISCELLANEOUS EQUIPMENT STORED IN THE MAIN CONTROL ROOM | | THAT WAS NOT SEISMICALLY MOUNTED. THE ORIGINAL NOTIFICATION ERRONEOUSLY | | STATED THAT "THE EQUIPMENT THAT WOULD BE DAMAGED FROM SUCH AN EVENT IS NOT | | REQUIRED". THE ENGINEERING EVALUATION SUBSEQUENTLY IDENTIFIED EQUIPMENT | | PANELS THAT WERE WITHIN THE "ARC OF FALL" OF THE MISCELLANEOUS EQUIPMENT. | | THE EVALUATION DETERMINED THAT THERE WAS MINIMAL SAFETY SYSTEM | | SIGNIFICANCE. PROMPT ACTIONS WERE TAKEN TO HAVE THE EQUIPMENT IN QUESTION | | REMOVED. | | | | THE RESIDENT INSPECTOR WAS INFORMED. THE REG 3 RDO(PHILLIPS) WAS NOTIFIED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32713 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 08/02/97 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:09 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 08/01/97 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:25[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 08/08/97 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |WAYNE KROPP RDO | | DOCKET: 0707001 |JOHN HICKEY EO | +------------------------------------------------+ | |NRC NOTIFIED BY: MAURER | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |OCBB 76.120(c)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR REPORT | | | | "ON 8/1/97 AT 1625 HOURS, THE C-333-A FACILITY AUTOCLAVE POSITION 4 NORTH | | STEAM CONTROLLER WAS DISCOVERED TO BE INOPERABLE DURING CYLINDER HEELING | | OPERATIONS (MODE 5), TSR LCO 2.2.3.3 REQUIRES THE AUTOCLAVE STEAM PRESSURE | | CONTROL SYSTEM TO BE OPERABLE WHEN THE AUTOCLAVE IS IN MODE 5. THE | | AUTOCLAVE WAS DECLARED INOPERABLE AND REMOVED FROM SERVICE AT 1631 HOURS. | | TROUBLESHOOTING AND A SYSTEM ENGINEERING EVALUATION OF THE FAILURE HAVE | | BEEN INITIATED." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | | | | * * * UPDATE AT 0007 ON 08/08/97 BY MIKE UNDERWOOD TAKEN BY JOLLIFFE * * * | | | | A LICENSEE ENGINEERING EVALUATION DETERMINED THAT THE STEAM CONTROLLER IS | | NOT WITHIN THE SAFETY SYSTEM BOUNDARY AND WAS NOT REQUIRED TO BE OPERABLE | | BY THE TECHNICAL SAFETY REQUIREMENT. ADDITIONALLY, THE AUTOCLAVES SAFETY | | SYSTEMS TESTS WERE PERFORMED IN THE "AS-FOUND CONDITION" AND DEMONSTRATED | | THAT THE FAILED STEAM CONTROLLER HAD NO EFFECT ON THE SAFETY SYSTEM TO | | FUNCTION AS DESIGNED. | | | | THUS, THE LICENSEE DESIRES TO RETRACT THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | THE NRC OPERATIONS OFFICER NOTIFIED THE R3DO MONTE PHILLIPS AND THE NMSS EO | | JOHN GREEVES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32740 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 08/08/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 09:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/08/97 | +------------------------------------------------+EVENT TIME: 09:00[EDT]| |NRC NOTIFIED BY: MARY BETH DEPUYDT |LAST UPDATE DATE: 08/08/97 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |MONTE PHILLIPS 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 | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UNITS 1 & 2 OPERATED OUTSIDE THE DESIGN BASIS FOR SERVICE WATER INLET TEMP | | | | AS A RESULT OF QUESTIONS POSED BY MEMBERS OF THE ONGOING NRC AE DESIGN | | INSPECTION TEAM, THE LICENSEE HAS DETERMINED THAT UNITS 1 & 2 HAVE OPERATED | | OUTSIDE THE PLANT DESIGN BASIS FOR SERVICE WATER INLET TEMPERATURE. | | | | THE UFSAR, TABLE 9.5-3, LISTS SERVICE WATER INLET TEMPERATURE DESIGN VALUE | | AS 76øF. THIS VALUE IS USED AS INPUT TO ANALYSES SUCH AS CONTAINMENT PEAK | | PRESSURE AND CONTROL ROOM HABITABILITY. ALTHOUGH ENGINEERING ANALYSES WERE | | PERFORMED IN 1988 RAISING THE TEMPERATURE TO 87.5øF AS LISTED IN THE PLANT | | TECHNICAL SPECIFICATIONS, A 10CFR50.59 SAFETY EVALUATION WAS NEVER | | PERFORMED, NOR WAS THE UFSAR PROPERLY REVISED. | | | | PLANT SERVICE WATER INLET TEMPERATURE IS THE SAME AS LAKE MICHIGAN WATER | | TEMPERATURE. A REVIEW OF HISTORICAL DATA INDICATES THAT DURING JULY AND | | AUGUST OF ANY YEAR, LAKE MICHIGAN WATER TEMPERATURE IS LIKELY TO EXCEED | | THE 76øF VALUE. SPECIFIC DATA FOR 1997 SHOWS THAT LAKE MICHIGAN WATER | | TEMPERATURE, AND THEREFORE PLANT SERVICE WATER INLET TEMPERATURE, WAS | | GREATER THAN 76øF ON JULY 17, JULY 18, AND AUGUST 4, 1997. ALL PLANT | | SYSTEMS WHICH UTILIZE SERVICE WATER AS A COOLING MEDIUM HAVE BEEN | | DETERMINED TO BE OPERABLE. A 10CFR50.59 SAFETY EVALUATION WILL BE | | PERFORMED AND APPROPRIATE CHANGES WILL BE INCORPORATED INTO THE UFSAR. | | | | THIS REPORT IS INTENDED TO COVER ANY TEMPERATURE EXCLUSIONS ABOVE 76øF | | AND BELOW THE 87.5øF VALUE LISTED IN THE PLANT TECHNICAL SPECIFICATIONS | | THAT MAY OCCUR PRIOR TO THE COMPLETION OF THE 10CFR50.59 SAFETY EVALUATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 32741 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: U.S. AIR FORCE RADIOISOTOPE COMMIT. |NOTIFICATION DATE: 08/08/97 | | CITY: BROOKS AIR FORC REGION: 4 |NOTIFICATION TIME: 12:21 [ET]| | COUNTY: STATE: TX |EVENT DATE: 08/07/97 | |LICENSE#: 42-23539-01AF AGREEMENT: Y |EVENT TIME: 15:00[CDT]| | DOCKET: |LAST UPDATE DATE: 08/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PHIL HARRELL RDO | | |CAMPER EO | +------------------------------------------------+SCHNEIDER OSP | |NRC NOTIFIED BY: HICKS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE U.S. AIR FORCE RADIOISOTOPE COMMITTEE REPORTED A MISSING CESIUM-137 | | SOURCE. | | | | THIS MATERIAL WAS BEING TRANSPORTED VIA YELLOW FREIGHT FROM MCCORD AFB, | | WASHINGTON, TO WYLE LABS IN HEATH, OH. THE 85.6 MILLICURIES OF CESIUM-137 | | WAS SHIPPED FROM MCCORD AFB ON 6/26/97 AND SHOULD HAVE ARRIVED AT WYLE LABS | | WITHIN 3-4 WEEKS(APPROX 7/24/97). WYLE LABS WAS CONTACTED BY THE AIR FORCE | | ON 8/7/97 AND, AS OF THAT DATE, THE SOURCE HAD NOT BEEN RECEIVED. YELLOW | | FREIGHT HAS TRACED THE SOURCE TO PORTLAND, OR., AS OF 8/7/97. YELLOW | | FREIGHT HAS NOTIFIED THEIR HAZMAT TEAM FOR STANDBY AND IS CONTINUING THE | | TRACE FOR THE SOURCE. THE SOURCE MAY BE LOST, BUT YELLOW FREIGHT HAS NOT | | CONFIRMED THIS. THE SEALED SOURCE DEVICE REGISTRY NUMBER IS | | NR-0121-D-103-S. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |TRANSPORTATION EVENT | |EVENT NUMBER: 32742 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SYNCOR |NOTIFICATION DATE: 08/08/97 | | CITY: LOUISVILLE REGION: 2 |NOTIFICATION TIME: 12:54 [ET]| | COUNTY: JEFFERSON STATE: KY |EVENT DATE: 08/08/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 05:50[EDT]| | DOCKET: |LAST UPDATE DATE: 08/08/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PHIL HARRELL RDO | | |COMBS EO | +------------------------------------------------+CHRIS CHRISTENSEN RDO | |NRC NOTIFIED BY: BLANCHARD(NAT RES. CENTR) |SCHNEIDER OSP | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NTRA TRANSPORTATION EVENT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE NATIONAL RESPONSE CENTER NOTIFIED THE NUCLEAR REGULATORY COMMISSION OF | | AN ACCIDENT THAT OCCURRED IN JEFFERSON COUNTY, KY., ON THE DIXIE HIGHWAY | | INVOLVING A TRUCK CARRYING LOW LEVEL RADIOACTIVE MATERIALS. THIS INCIDENT | | WAS REPORTED TO THE NATIONAL RESPONSE CENTER BY SYNCOR WHO IS THE SUSPECTED | | RESPONSIBLE PARTY. THE DRIVER OF THE TRUCK WAS INJURED AND THE HIGHWAY WAS | | CLOSED FOR 3 HOURS. THERE WAS NO REPORTED RELEASE OF RADIOACTIVE | | MATERIALS. A SURVEY OF THE AREA WAS MADE. THE STATE WAS NOTIFIED BY | | SYNCOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32743 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 08/09/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 00:53 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 08/08/97 | +------------------------------------------------+EVENT TIME: 16:50[EDT]| |NRC NOTIFIED BY: ARCHIE FAULKNER |LAST UPDATE DATE: 08/09/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 86 POWER OPERATION | 86 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SOUTH PLANT VENT RADIATION MONITOR DECLARED INOPERABLE DUE TO EQUIPMENT | | FAILURE | | | | "AT 1650 ON 8/8/97, THE HOPE CREEK GENERATING STATION SOUTH PLANT VENT | | RADIATION MONITOR BECAME INOPERABLE DUE TO AN EQUIPMENT FAILURE. THE EXACT | | CAUSE OF THE FAILURE IS NOT YET KNOWN. THIS FAILURE DID NOT CAUSE ANY | | AUTOMATIC ACTIONS TO OCCUR, AND NONE SHOULD HAVE OCCURRED. COMPENSATORY | | MEASURES HAVE BEEN INITIATED IN ACCORDANCE WITH PLANT TECH SPECS (ALTERNATE | | SAMPLING). THE EFFECT OF THE FAILURE IS LOSS OF CONTROL ROOM INDICATION OF | | RADIOACTIVE EFFLUENT RELEASE DATA DURING NORMAL AND EMERGENCY PLANT | | OPERATIONS VIA THE SOUTH PLANT VENT. PLANT MAINTENANCE WORKERS ARE | | TROUBLESHOOTING THE PROBLEM. THIS REPORT IS BEING MADE DUE TO THE LOSS OF | | THIS MONITOR FOR >8 HOURS [WHICH] IS CONSIDERED A MAJOR LOSS OF ASSESSMENT | | CAPABILITY AT THE HOPE CREEK GENERATING STATION." | | | | THE UNIT IS CURRENTLY IN TECH SPEC LCOs 3.3.7.11 (ALTERNATE SAMPLING) AND | | 3.3.7.5 (POST ACCIDENT SAMPLING) AS A RESULT OF THE ABOVE RAD MONITOR | | FAILURE. THERE WAS NO INDICATION OF ANY ABNORMAL RAD LEVELS OR RELEASE | | DURING THE PERIOD OF TIME THIS MONITOR HAS BEEN INOPERABLE. THE LICENSEE | | SUSPECTS THAT THE PROBLEM IS RELATED TO A FAULTY HIGH VOLTAGE POWER SUPPLY | | AND EXPECTS TO COMPLETE REPAIRS WITHIN 24 HOURS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32744 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 08/09/97 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 10:02 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 08/09/97 | +------------------------------------------------+EVENT TIME: 07:02[EDT]| |NRC NOTIFIED BY: JERRY FREEMAN |LAST UPDATE DATE: 08/09/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPURIOUS SCRAM CAUSED BY OPERATOR JIGGLING MODE SWITCH TO REMOVE KEY AS | | PART OF SURVEILLANCE PROCEDURE | | | | "WHILE ATTEMPTING TO REMOVE THE KEY PER PROCEDURE FROM THE REACTOR MODE | | SWITCH WHILE IN THE REFUEL POSITION, A FULL SCRAM WAS PROCESSED DUE TO THE | | SHUTDOWN POSITION CONTACTS INADVERTENTLY MAKING UP. THE MODE SWITCH IS | | PRESENTLY LOCKED IN THE SHUTDOWN POSITION PENDING COMPLETION OF A SCRAM | | DISCHARGE VOLUME SURVEILLANCE. ALL RODS WERE AT POSITION '00' PRIOR TO AND | | FOLLOWING THIS EVENT." | | | | THE INADVERTENT SCRAM WAS CAUSED BY OPERATORS JIGGLING THE SWITCH TO REMOVE | | THE KEY. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32745 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HADDAM NECK REGION: 1 |NOTIFICATION DATE: 08/09/97 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 11:25 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 08/09/97 | +------------------------------------------------+EVENT TIME: 11:14[EDT]| |NRC NOTIFIED BY: PHILIP RAINHA |LAST UPDATE DATE: 08/09/97 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |RICHARD CONTE 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 DECOMMISSIONED | 0 DECOMMISSIONED | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED CONTAINMENT ISOLATION ACTUATION DUE TO PERSONNEL ERROR | | | | "AN UNPLANNED ACTUATION OF AN ENGINEERED SAFETY FUNCTION (CONTAINMENT | | ISOLATION), NOT REQUIRED FOR THE CURRENT PLANT CONDITION, OCCURRED ON | | 7/30/97." | | | | ON 7/30/97 AT 0313EDT, THE LICENSEE DEENERGIZED THE 'A1' AND 'A2' REACTOR | | PROTECTION SYSTEM (RPS) CABINETS. THIS RESULTED IN POSSIBLY 1 OR 2 | | CONTAINMENT ISOLATION VALVES REPOSITIONING CLOSED. OPERATORS DID NOT | | RECOGNIZE THAT THIS ACTUATION HAD OCCURRED UNTIL 1114EDT ON 8/9/97 WHEN | | THEY WERE UNABLE TO PUMP THE CONTAINMENT SUMPS. A REVIEW OF THE RECORDS | | CONCLUDED THAT DEENERGIZING THE 'A' TRAIN RPS BY DESIGN RESULTS IN AN | | ACTUATION OF THE CONTAINMENT ISOLATION LOGIC (HIGH CONTAINMENT PRESSURE | | ISOLATION). THE LICENSEE ATTRIBUTES THE CAUSE TO PERSONNEL ERROR AND WILL | | INFORM THE STATE OF CONNECTICUT, LOCAL TOWNSHIPS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+