U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/14/96 - 05/15/96 ** EVENT NUMBERS ** 30462 30463 30464 30465 30466 30467 30468 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30462 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SUMMER REGION: 2 |NOTIFICATION DATE: 05/14/96 | |UNIT: [1] [ ] [ ] STATE: SC |NOTIFICATION TIME: 01:54 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 05/14/96 | +------------------------------------------------+EVENT TIME: 00:00[EDT]| |NRC NOTIFIED BY: SIMPSON |LAST UPDATE DATE: 05/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CRLENJAK 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | LEAKAGE PAST EMERGENCY FEEDWATER PUMP FLOW CONTROL VALVES COULD PLACE UNIT | | OUTSIDE OF DESIGN BASIS | | | | DURING RECENT INTEGRATED SAFEGUARDS TESTING, THE LICENSEE NOTICED | | INCREASING STEAM GENERATOR LEVELS AS A RESULT OF LEAKAGE PAST THE CLOSED | | MOTOR-DRIVEN EMERGENCY FEEDWATER (EFW) PUMP FLOW CONTROL VALVES. UPON | | FURTHER INVESTIGATION, THE LICENSEE DETERMINED THAT LEAKAGE PAST THESE | | VALVES COULD PLACE THE UNIT IN AN UNANALYZED CONDITION WITH RESPECT TO THE | | REACTOR BUILDING STEAM LINE BREAK ANALYSIS. THE LICENSEE IS ALSO CONCERNED | | WITH POTENTIAL LEAKAGE PAST THE TURBINE-DRIVEN EFW FLOW CONTROL VALVES. | | | | THE LICENSEE'S INITIAL EVALUATION INDICATES THAT FOLLOWING A FAULTED STEAM | | GENERATOR ISOLATION, SOME LEAKAGE IS INITIALLY ACCEPTABLE, BUT EFW FLOW TO | | THE FAULTED STEAM GENERATOR IS ASSUMED TO BE TERMINATED AFTER APPROXIMATELY | | 1,800 SECONDS. THE LICENSEE PLANS TO DETERMINE THE ACCEPTABLE LEVEL OF | | LEAKAGE PAST THE FLOW CONTROL VALVES AS WELL AS ANY REQUIRED CHANGES TO | | PLANT PROCEDURES. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30463 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 05/14/96 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 09:51 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/13/96 | +------------------------------------------------+EVENT TIME: 23:24[CDT]| |NRC NOTIFIED BY: TURNER/REED |LAST UPDATE DATE: 05/14/96 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HARRELL RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 OFF-DUTY CONTRACT JANITORIAL SUPERVISOR WAS DETERMINED TO BE UNDER THE | | INFLUENCE OF ALCOHOL DURING A FOR-CAUSE TEST. THE INDIVIDUAL'S SITE ACCESS | | HAS BEEN TERMINATED. SEE HOO LOG FOR DETAILS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30464 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LIMERICK REGION: 1 |NOTIFICATION DATE: 05/14/96 | |UNIT: [ ] [2] [ ] STATE: PA |NOTIFICATION TIME: 12:44 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 05/14/96 | +------------------------------------------------+EVENT TIME: 10:33[EDT]| |NRC NOTIFIED BY: WILLIAM MAGUIRE |LAST UPDATE DATE: 05/14/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANIELLO DELLA GRECA 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | A/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOMATIC TURBINE TRIP AND REACTOR SCRAM DUE TO A GENERATOR POWER-TO-LOAD | | UNBALANCE CONDITION WHICH RESULTED FROM A GRID PERTURBATION | | | | AT 1033, UNIT 2 RECEIVED AN AUTOMATIC SCRAM SIGNAL FROM AN AUTOMATIC | | TURBINE TRIP. THE TURBINE TRIP SIGNAL WAS GENERATED FROM A POWER-TO-LOAD | | UNBALANCE CONDITION. ALL RODS FULLY INSERTED. AS A NORMAL FEEDWATER | | RESPONSE FROM A 100% POWER TURBINE TRIP, A LOW LEVEL (12.5 INCHES) | | ISOLATION SIGNAL WAS ALSO RECEIVED FOR RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN | | COOLING VALVES, RHR HEAT EXCHANGER SAMPLE LINES, AND RHR EXCHANGER DRAINS | | TO RADWASTE. ALL OF THE APPLICABLE VALVES WERE ALREADY CLOSED PRIOR TO | | RECEIVING THE ISOLATION SIGNAL. THE '2E' SAFETY RELIEF VALVE OPENED | | FOLLOWING THE REACTOR SCRAM DUE TO REACTOR HIGH PRESSURE CAUSED BY THE | | TURBINE TRIP, AND IT SUBSEQUENTLY RECLOSED, AS EXPECTED. THERE WERE NO | | EMERGENCY CORE COOLING SYSTEMS SIGNALS OR INJECTIONS AS A RESULT OF THIS | | TRANSIENT. ALL SYSTEMS FUNCTIONED AS REQUIRED. | | | | THE LICENSEE BELIEVES THAT THE GENERATOR LOAD UNBALANCE CONDITION RESULTED | | FROM ELECTRICAL INSTABILITY ON THE GRID. APPARENTLY, THE DELMARVA | | (DELAWARE/MARYLAND/VIRGINIA) PENINSULA ON THE GRID HAD LOST POWER AND THERE | | WAS SOME ELECTRICAL INSTABILITY ON THE GRID WHEN THE LOAD DISPATCHER WAS | | TRYING TO REESTABLISH POWER TO THE DELMARVA PENINSULA. | | | | UNIT 2 IS CURRENTLY STABLE IN COND 3 (HOT SHUTDOWN). OPERATORS ARE | | CURRENTLY UTILIZING THE FEEDWATER SYSTEM AND CONTROL ROD DRIVE SYSTEM FOR | | REACTOR VESSEL LEVEL CONTROL, AND MAIN STEAM IS BEING BYPASSED TO THE | | CONDENSER FOR REACTOR VESSEL PRESSURE CONTROL. THERE ARE NO ABNORMAL | | CONTAINMENT PARAMETERS. | | | | THE LICENSEE NOTIFIED THE APPLICABLE STATE AND LOCAL AGENCIES OF THIS EVENT | | AS AN EVENT OF POTENTIAL PUBLIC INTEREST. THE LICENSEE ALSO NOTIFIED THE | | NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30465 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MAINE YANKEE REGION: 1 |NOTIFICATION DATE: 05/14/96 | |UNIT: [1] [ ] [ ] STATE: ME |NOTIFICATION TIME: 13:32 [ET]| |RX TYPE: [1] CE |EVENT DATE: 05/14/96 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: PETE EBERT |LAST UPDATE DATE: 05/14/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANIELLO DELLA GRECA 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 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY THAT INTERLOCKS WHICH PREVENT THE YARD CRANE FROM TRANSPORTING | | HEAVY LOADS OVER THE SPENT FUEL POOL MAY NOT BE FUNCTIONAL | | | | AT 1200, THE CONTROL ROOM WAS NOTIFIED BY THE ENGINEERING DEPARTMENT THAT | | THE INTERLOCKS WHICH PREVENT THE YARD CRANE FROM TRANSPORTING HEAVY LOADS | | OVER THE SPENT FUEL POOL DO NOT APPEAR TO BE FUNCTIONAL. THE YARD CRANE | | INTERLOCKS ARE DESIGNED TO ALLOW ACCESS TO THE SPENT FUEL CASK LAYDOWN AREA | | BUT PREVENT CARRYING HEAVY LOADS OVER SPENT FUEL POOL UNLESS A BYPASS KEY | | DISABLES THE INTERLOCK CIRCUIT. THE DESIGN DEFECT HAS BEEN IN EXISTENCE | | SINCE INITIAL PLANT OPERATION. | | | | A MAJOR OVERHAUL OF THE YARD CRANE IS JUST BEING COMPLETED, AND THE CRANE | | VENDOR WAS IN THE PROCESS OF PREPARING A POST-MAINTENANCE FUNCTIONAL TEST | | PLAN WHEN THE DESIGN DEFECT WAS DISCOVERED. AN ENGINEERING REVIEW OF THE | | WIRING SCHEMATICS CONFIRMED THE VENDOR'S INITIAL CONCLUSION. UPON FINAL | | REASSEMBLY OF THE CRANE, A TEST OF THE INTERLOCK CIRCUIT WILL BE CONDUCTED | | TO VERIFY THE EXISTENCE OF THE DEFECT. AT 1300, AFTER REVIEW OF THE | | APPLICABLE DESIGN DOCUMENTS AND ADMINISTRATIVE CONTROLS, THE EVENT WAS | | CONSIDERED TO BE REPORTABLE TO THE NRC. AS FAR AS IS KNOWN BY THE | | LICENSEE, AT NO TIME HAS A HEAVY LOAD BEEN PLACED OVER SPENT FUEL AS A | | RESULT OF THIS DESIGN DEFECT. | | | | THE LICENSEE WILL NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 30466 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NUCLEAR METALS, INC, CONCORD, MA |NOTIFICATION DATE: 05/14/96 | | CITY: CONCORD REGION: 1 |NOTIFICATION TIME: 15:26 [ET]| | COUNTY: MIDDLESEX STATE: MA |EVENT DATE: 05/14/96 | |LICENSE#: SMB-179 AGREEMENT: N |EVENT TIME: 08:50[EDT]| | DOCKET: |LAST UPDATE DATE: 05/14/96 | | +-----------------------------+ | |PERSON ORGANIZATION| | |ANIELLO DELLA GRECA RDO | | |DON COOL, NMSS EO | +------------------------------------------------+RICH BARRETT, ERB AEOD | |NRC NOTIFIED BY: ERIC ANDERSON |MOORE, NAT RES CTR EPA | |HQ OPS OFFICER: LEIGH TROCINE |DAVID TORDOFF EPA | +------------------------------------------------+TOM TANNER DOE | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |JBBE 40.60(b)(2)(i) ACCID MIT EQUIP FAILS | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RELEASE OF ABOUT 380 GRAMS OF DEPLETED URANIUM IN APPROXIMATELY 1,800 | | GALLONS OF WASTE WATER INTO THE SOIL VIA A BROKEN PIPE | | | | NUCLEAR METALS, INC., LOCATED IN CONCORD, MA., REPORTED THE FOLLOWING | | EVENT: | | | | AT APPROXIMATELY 1545 ON MAY 13, 1996, A BACK HOE OPERATOR UNKNOWINGLY | | BROKE A 3 INCH DIAMETER PVC PIPE DURING EXCAVATION ACTIVITIES. THIS PIPE | | BREAK WAS LOCATED APPROXIMATELY 100 FEET SOUTH OF THE LICENSEE'S TANK HOUSE | | IN A LINE THAT IS USED TO TRANSFER MISCELLANEOUS WASTE WATER FROM A STORAGE | | TANK LOCATED INSIDE THE TANK HOUSE TO A RESOURCE RECOVERY AREA LOCATED IN A | | PROCESS FACILITY IN BUILDING 'E'. THE PIPE BREAK WAS LOCATED ON THE | | LICENSEE'S PROPERTY WITHIN A FENCED IN AREA, BUT IT WAS NOT LOCATED WITHIN | | A RADIOLOGICALLY RESTRICTED AREA. | | | | AT 0835 ON MAY 14, 1996, THE LICENSEE ATTEMPTED TO TRANSFER WASTE WATER | | FROM THE STORAGE TANK TO THE RESOURCE RECOVERY AREA WITHOUT KNOWING THAT | | THE TRANSFER LINE HAD BEEN BROKEN THE DAY BEFORE. WHEN THE LICENSEE | | REALIZED THAT NO LIQUID WAS BEING TRANSFERRED, THE LICENSEE TERMINATED THE | | TRANSFER AT 0850. THE LICENSEE'S INVESTIGATION REVEALED THAT THE LIQUID | | HAD BEEN PUMPED INTO THE EXCAVATION HOLE THROUGH THE BROKEN PIPE. THE | | LIQUID SUBSIDED WHEN THE PUMP WAS TURNED OFF, AND A LOT OF THE LIQUID | | SUBSIDED BACK INTO THE ORIGINAL STORAGE TANK. | | | | BY COMPARING THE INITIAL AND FINAL VOLUMES PRESENT IN THE STORAGE TANK, THE | | LICENSEE ESTIMATED THAT THE QUANTITY OF MISCELLANEOUS WASTE WATER THAT WAS | | RELEASED INTO THE SOIL WAS APPROXIMATELY 1,800 GALLONS. THE WASTE WATER | | CONTAINED WASH WATER, RECOVERED SPLIT ACIDS OF AN AQUEOUS NATURE, A HOST OF | | TRAMP OILS, DEPLETED URANIUM-238 AND URANIUM-234, LESS THAN 0.2% | | URANIUM-235, AND THE IMMEDIATE PROGENY OF THE DEPLETED URANIUM (PRESUMED TO | | BE IN SECULAR EQUILIBRIUM WITH THE PARENTS). THE PROGENY INCLUDED | | THORIUM-234, PROTACTINIUM-234, AND PROTACTINIUM-234 METASTABLE. | | | | THE LICENSEE'S FOLLOWUP ANALYSIS INDICATED THAT ROUGHLY 20 PICOCURIES PER | | MILLILITER (2E-5 MICROCURIES PER MILLILITER) OF DEPLETED URANIUM WAS IN THE | | SAMPLE. THAT TRANSLATES TO A TOTAL RELEASE OF APPROXIMATELY 380 GRAMS OF | | DEPLETED URANIUM IN THE ESTIMATED 1,800-GALLON WASTE WATER RELEASE. THE | | PRELIMINARY CONCENTRATION ESTIMATES EXCEED THE REGULATORY EFFLUENT | | CONCENTRATION LIMIT BY A FACTOR OF 60. | | | | IN ORDER TO GAIN ACCESS TO THE PIPE FOR THE PERFORMANCE OF REPAIRS, THE | | LICENSEE PLANS TO EXCAVATE FURTHER, REMOVE THE SOIL FROM BENEATH THE BREAK | | AREA, AND PLACE THE SOIL TO THE SIDE. THE LICENSEE THEN PLANS TO REPLACE | | THE SECTION OF PIPE WITH THE BREAK, SEAL IT, AND PLACE THE PIPE BACK IN | | SERVICE. THE LICENSEE ALSO PLANS TO REMOVE ANY SOIL THAT HAS BEEN | | IDENTIFIED AS BEING AFFECTED AND APPROPRIATELY DISPOSE OF IT. IN ADDITION, | | THE LICENSEE PLANS TO ANALYZE SOIL SAMPLES FROM THE AFFECTED AREA FOR | | ACTIVITY CONCENTRATIONS. SOIL SAMPLES THUS FAR INDICATE THAT THERE ARE NO | | GROSS LEVELS OF CONTAMINATION THAT WOULD CAUSE AN EXPOSURE PROBLEM. | | HOWEVER, THE LICENSEE DOES EXPECT TO FIND SOME AREAS WITHIN THE FENCE THAT | | HAVE SOME LEVELS OF SURFACE CONTAMINATION. FOLLOWUP PERSONNEL WILL REMAIN | | BADGED AND MONITORED. THE AREA HAS NOT BEEN ROPED OFF OR LABELLED AT THIS | | TIME. THE LICENSEE STATED THAT NO WORKERS WERE IMPACTED BY THIS EVENT AND | | THAT THE WASTE WATER COULD HAVE GOTTEN INTO THE WATER TABLE THROUGH THE | | SOIL BENEATH THE PIPE BREAK. | | | | THE LICENSEE NOTIFIED NRC REGION 1 (STEVEN SHAFFER) AND THE STATE | | DEPARTMENT OF ENVIRONMENTAL PROTECTION'S EMERGENCY RESPONSE CENTER AND | | BUREAU OF WASTE SITE CLEANUP. (REFER TO THE HOO LOG FOR A SITE CONTACT | | ADDRESS AND TELEPHONE NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30467 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PERRY REGION: 3 |NOTIFICATION DATE: 05/14/96 | |UNIT: [1] [ ] [ ] STATE: OH |NOTIFICATION TIME: 16:19 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 05/14/96 | +------------------------------------------------+EVENT TIME: 15:24[EDT]| |NRC NOTIFIED BY: ALAN RABENOLD |LAST UPDATE DATE: 05/14/96 | |HQ OPS OFFICER: HENRY BAILEY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROY CANIANO 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 +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION OF A 0.5 GPM LEAK FROM THE CIRCULATING WATER SYSTEM | | | | THERE IS A 0.5-GPM LEAK FROM A CRACK IN THE CIRCULATING WATER BASIN WALL, | | AND THE CIRCULATING WATER IS TREATED WITH SODIUM HYPOCHLORITE. THIS | | LEAKAGE IS BEING CONTAINED IN A POOL AND IS BEING PUMPED BACK INTO THE | | BASIN. | | | | THE LICENSEE NOTIFIED THE ENVIRONMENTAL PROTECTION AGENCY AND PLANS TO | | NOTIFY THE NRC RESIDENT INSPECTOR. THE LICENSEE DOES NOT PLAN TO ISSUE A | | PRESS RELEASE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 30468 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 05/14/96 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 18:12 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 05/13/96 | +------------------------------------------------+EVENT TIME: 20:45[MST]| |NRC NOTIFIED BY: KATHLEEN ROBERSON |LAST UPDATE DATE: 05/14/96 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | DISCOVERY THAT INAPPROPRIATE CLOSURE OF A STEAM GENERATOR NORMAL BLOWDOWN | | ISOLATION VALVE TO THE BLOWDOWN FLASH TANK RESULTED IN ACTUAL REACTOR CORE | | POWER EXCEEDING INDICATED POWER BY APPROXIMATELY 0.28% | | | | AT APPROXIMATELY 1300 MST ON MAY 14, 1996, AN INITIAL INVESTIGATION BY | | LICENSEE ENGINEERING PERSONNEL DETERMINED THAT AN INAPPROPRIATE CLOSURE OF | | THE STEAM GENERATOR #1 NORMAL BLOWDOWN ISOLATION VALVE (BDIV) TO THE | | BLOWDOWN FLASH TANK RESULTED IN REACTOR CORE POWER EXCEEDING 3,800 MWt. THE | | CLOSED BDIV WAS DISCOVERED BY UNIT 2 OPERATIONS PERSONNEL AT APPROXIMATELY | | 2045 MST ON MAY 13, 1996. THE VALVE WAS ORIGINALLY CLOSED AT APPROXIMATELY | | 0052 MST ON MAY 11, 1996, PRIOR TO THE PERFORMANCE OF STEAM GENERATOR HIGH | | RATE BLOWDOWNS. FOLLOWING DISCOVERY ON MAY 13, 1996, THE BDIV WAS | | REOPENED, AND THE REMAINING UNIT 2 ISOLATION VALVES WERE VERIFIED TO BE IN | | THEIR PROPER POSITIONS. VALVE LINEUPS ON UNITS 1 AND 3 WERE ALSO VERIFIED. | | THE LICENSEE'S INITIAL INVESTIGATION DETERMINED THAT THE APPARENT CAUSE OF | | THE EVENT WAS PERSONNEL ERROR IN THAT THE BDIV WAS LEFT IN THE CLOSED | | POSITION CONTRARY TO AN APPROVED PROCEDURE. | | | | THE ACTUAL REACTOR POWER DURING THAT PERIOD OF TIME THAT THE BDIV WAS | | ISOLATED (APPROXIMATELY 68 HOURS) WAS HIGHER THAN INDICATED POWER BY | | APPROXIMATELY 0.28%. THE HIGHEST ROLLING SHIFTLY AVERAGE WAS DETERMINED TO | | BE APPROXIMATELY 100.27%. (THE LICENSEE UTILIZES 12 HOUR SHIFTS.) | | EVALUATION IS STILL IN PROGRESS, AND FURTHER TESTING WILL BE PERFORMED TO | | FINALIZE THE POWER LEVEL. THIS EVENT DID NOT ADVERSELY AFFECT THE SAFE | | OPERATION OF THE PLANT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+