U.S. Nuclear Regulatory Commission Operations Center Event Reports For 07/21/94 - 07/22/94 ** EVENT NUMBERS ** 27295 27447 27557 27558 27559 27560 27561 27562 27563 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27295 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 05/25/94 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 14:55 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/25/94 | +------------------------------------------------+EVENT TIME: 13:14[CDT]| |NRC NOTIFIED BY: DAVE KUSER |LAST UPDATE DATE: 07/22/94 | |HQ OPS OFFICER: JOSEPH SEBROSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: UNUSUAL EVENT +-----------------------------+ |10 CFR SECTION: |DALE POWERS RDO | |AAEC 50.72(a)(1)(i) EMERGENCY DECLARED |ROBERT DENNING EO | |NLCO TECH SPEC LCO A/S |BOB CALDWELL FEMA | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 93 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNUSUAL EVENT DECLARED DUE TO BOTH EMERGENCY DIESEL GENERATORS BEING | | DECLARED INOPERABLE. | | | | THE FOLLOWING IS A TEXT OF A FACSIMILE FROM THE LICENSEE: | | | | "ON MAY 25, 1994 AT 1:14 PM A NOTIFICATION OF UNUSUAL EVENT WAS DECLARED | | WHEN BOTH DIESEL GENERATORS WERE DECLARED INOPERABLE DUE TO THE | | SURVEILLANCE TEST CONDUCTED EACH REFUELING OUTAGE NOT VERIFYING THE LOAD | | SHEDDING OF ALL LOADS ON THE CRITICAL 480 VOLT BUS. PROPER LOAD SHEDDING | | OF ALL 4160 VOLT LOADS IS VERIFIED DURING THE SEQUENTIAL LOADING TEST. THE | | PRINCIPAL 480 VOLT LOADS NOT VERIFIED TO BE SHED INCLUDE STATION AIR | | COMPRESSORS AND THE CRD PUMPS. THESE COMPONENTS ARE TRANSFERRED TO ANOTHER | | BUS DURING THE SURVEILLANCE TEST. INDIVIDUALLY, THE REMAINING LOADS ON THE | | CRITICAL 480 VOLT BUS ARE SMALL. | | | | IN ACCORDANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS IN SECTION 3.5.F.2, | | A LOAD REDUCTION TO 25 PERCENT POWER WAS INITIATED. AN ENGINEERING | | EVALUATION OF THE CONDITION IS ONGOING. A FOLLOW-UP NOTIFICATION WILL BE | | MADE WHEN SUCH INFORMATION IS AVAILABLE." END OF TEXT. | | | | THE LICENSEE IS REDUCING POWER AT 100 MW(e) PER HOUR. THE LICENSEE | | CONSIDERS THE EDGS AVAILABLE. ALL ECCS AND RCIC ARE OPERABLE. THE WEATHER | | IN THE AREA IS CALM WITH NO FORECAST OF RAIN. THE PROBLEM WAS DISCOVERED | | DURING REVIEW OF UNDERVOLTAGE TESTING. THE LAST REFUELING OUTAGE ENDED IN | | JULY OF 1993. THE LICENSEE IS INVESTIGATING CORRECTIVE ACTIONS AND IS | | PURSUING ENFORCEMENT DISCRETION WITH THE NRC TO STOP THE POWER DESCENSION. | | | | THE LICENSEE HAS INFORMED THE RESIDENT INSPECTOR AND HAS INFORMED LOCAL AND | | STATE OFFICIALS IN ACCORDANCE WITH THEIR EMERGENCY PLAN. | | | | * * * UPDATE 5/25/94 @ 22:40 FROM CAUL TAKEN BY SEBROSKY * * * | | THE REACTOR IS CURRENTLY AT 24% POWER AND THE LICENSEE PLANS TO SCRAM THE | | THE PLANT AT 22:00 CT PER THEIR NORMAL SHUTDOWN PROCEDURES. THE SHUTDOWN | | IS BEING DONE DUE TO BOTH EDGS BEING DECLARED INOPERABLE. THE LICENSEE | | WILL EXIT THE UNUSUAL EVENT WHEN THE PLANT REACHES COLD SHUTDOWN | | CONDITIONS. COLD SHUTDOWN IS EXPECTED TO BE REACHED SOMETIME TOMORROW | | MORNING. THE LICENSEE HAS BEEN IN CONTACT WITH REGION 4 OFFICIALS | | CONCERNING THE SHUTDOWN AND HAS INFORMED THE RESIDENT INSPECTOR. | | HOO NOTIFIED R4DO(POWERS) AND EO(VARGA). | | | | * * * UPDATE 5/27/94 @ 0106 FROM HITZEL TAKEN BY WEAVER * * * | | THE PLANT REACHED COLD SHUTDOWN AT 2357 CDT ON 5/26/94. THIS SATISFIES THE | | TECHNICAL SPECIFICATION ACTION STATEMENT FOR HAVING BOTH EMERGENCY DIESELS | | INOPERABLE. CONTRARY TO THE LAST UPDATE, THE UNUSUAL EVENT WILL NOT BE | | TERMINATED UNTIL AT LEAST ONE EDG IS MADE OPERABLE AS REQUIRED BY THEIR | | EMERGENCY PROCEDURES. NO TIME ESTIMATE WAS AVAILABLE. THE LICENSEE | | INFORMED THE NRC RESIDENT INSPECTOR AS WELL AS STATE AND LOCAL GOVERNMENTS. | | HOO NOTIFIED R4 RDO (POWERS) AND EO (CHAFFEE). | | | | * * * UPDATE 1400EDT 5/27/94 FROM KUSER TO S.SANDIN * * * | | THE CONTINUING INVESTIGATION HAS REVEALED THAT LOAD SHEDDING OF THE SERVICE | | WATER PUMPS, 4160 VOLT LOADS, IS NOT VERIFIED DURING THE SEQUENTIAL LOADING | | TEST. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. NOTIFIED | | R4DO(POWERS). | | | | * * * UPDATE AT 1734 EDT ON 6/11/94 FROM HITZEL TAKEN BY KARSCH * * * | | THE FOLLOWING NOTIFICATION WAS MADE PURSUANT TO 10CFR50.72(b)(2)iiiD: | | "AS AN ELEMENT OF THE INVESTIGATION INTO THIS CONDITION, AN EVALUATION OF | | CONTACT TEST REQUIREMENTS NECESSARY TO SATISFY LOGIC SYSTEM FUNCTIONAL | | TESTING REQUIREMENTS SPECIFIED IN TECHNICAL SPECIFICATIONS FOR SAFETY | | RELATED SYSTEMS WAS PERFORMED. THIS EVALUATION REVEALED A NUMBER OF | | CONTACTS NOT VERIFIED BY SURVEILLANCE PROCEDURES. EACH CONTACT NOT TESTED | | WAS EVALUATED TO DETERMINE IF FAILURE TO ASSURE ITS OPERABILITY JEOPARDIZED | | COMPLIANCE WITH THE LOGIC SYSTEM FUNCTIONAL TEST DEFINITION SPECIFIED IN | | SECTION 1.0 OF THE TECH SPECS. | | | | "AT 1430 TODAY (JUNE 11, 1994), THE SYSTEMS IDENTIFIED BELOW WERE DECLARED | | INOPERABLE DUE TO THE SURVEILLANCE TEST DEFICIENCY. | | SERVICE WATER REACTOR EQUIPMENT COOLING | | 4160 VAC BUS 1F 4160 VAC BUS 1G | | DIESEL GENERATOR 1 DIESEL GENERATOR 2 | | PROCEDURE CHANGES AND SPECIAL PROCEDURES ARE BEING DEVELOPED AND CONDUCTED | | TO ASSURE OPERABILITY OF THE LOGIC SYSTEMS. WHILE TECHNICALLY INOPERABLE, | | AND NOT REQUIRED TO BE OPERABLE UNDER THE PRESENT PLANT CONDITIONS, THE | | SYSTEMS ARE FUNCTIONAL AND AVAILABLE. THE ASSOCIATED SYSTEMS WILL NOT BE | | DECLARED OPERABLE UNTIL SATISFACTORY COMPLETION OF THE TESTS AND | | VERIFICATION OF THE RESULTS." | | | | THE LICENSEE HOPES TO COMPLETE TESTING ON ONE DIVISION'S EDG BY LATE | | MONDAY. AT THAT TIME THEY SHOULD BE ABLE TO EXIT THEIR UNUSUAL EVENT. | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. R4DO(SANBORN) NOTIFIED. | | | | **** UPDATE BY HITZEL AT 1555 EDT ON 06/14/94 TAKEN BY ANDREWS | | | | THE FOLLOWING INFORMATION WAS PROVIDED BY THE LICENSEE VIA FAX/PHONE: | | THIS IS THE SECOND FOLLOWUP NOTIFICATION TO THE NOTIFICATION MADE ON | | 5/25/94 @ 1314 CDT. AT THAT TIME, AN UNUSUAL EVENT HAD BEEN DECLARED WHEN | | BOTH DIESEL GENERATORS WERE DECLARED INOPERABLE DUE TO THE SURVEILLANCE | | TEST, CONDUCTED EACH REFUELING OUTAGE, NOT VERIFYING THE LOAD SHEDDING OF | | ALL LOADS ON THE CRITICAL 4160 AND 480 VOLT BUSES. INVESTIGATION REVEALED | | THAT LOAD SHEDDING OF THE SERVICE WATER BOOSTER PUMPS, 4160 LOADS, IS NOT | | VERIFIED DURING THE SEQUENTIAL LOADING TEST. LOAD SHEDDING OF ALL OTHER | | 4160 VOLT LOADS IS VERIFIED. THE PRINCIPLE 480 VOLT LOADS NOT VERIFIED TO | | BE SHED INCLUDE STATION AIR COMPRESSORS AND THE CRD PUMPS. THESE | | COMPONENTS HAD BEEN TRANSFERRED TO ANOTHER BUS DURING THE SURVEILLANCE | | TEST. INDIVIDUALLY, THE REMAINING LOADS ON THE CRITICAL 480 BUS ARE SMALL. | | | | ON 6/11/94, NPPD REPORTED IN A FOLLOWUP NOTIFICATION THAT AS AN ELEMENT OF | | THE INVESTIGATION INTO THIS CONDITION, AN EVALUATION OF CONTACT TEST | | REQUIREMENTS NECESSARY TO SATISFY LOGIC SYSTEM FUNCTIONAL TESTING | | REQUIREMENTS SPECIFIED IN THE TECHNICAL SPECIFICATIONS FOR SAFETY-RELATED | | SYSTEMS WAS PERFORMED. THIS EVALUATION REVEALED A NUMBER OF CONTACTS NOT | | VERIFIED BY SURVEILLANCE PROCEDURES. IN RESPONSE TO THIS DETERMINATION, | | SEVERAL SPECIAL TEST PROCEDURES WERE DEVELOPED & A NUMBER OF SURVEILLANCE | | TESTS WERE UPDATED TO TEST & VERIFY OPERABILITY OF THE CONTACTS & RELATED | | RELAYS. TESTING USING THESE PROCEDURES COMMENCED DURING THE WEEK OF 6/5/94. | | | | AT APPROXIMATELY 1100 CDT ON 6/14/94, DURING TESTING OF DIVISION 1 BREAKERS | | DESIGNED TO LOAD SHED ON A LOSS OF POWER, TWO 480 VAC BREAKERS FAILED TO | | TRIP AS REQUIRED. BOTH BREAKERS ARE DESIGNED TO TRIP IN LESS THAN 8.5 | | SECONDS. ONE BREAKER WHICH SUPPLIES POWER TO THE 1A SERVICE AIR COMPRESSOR | | TRIPPED APPROXIMATELY 100 SECONDS AFTER THE LOSS OF VOLTAGE CONDITION WAS | | IMPOSED. THE OTHER BREAKER WHICH SUPPLIES POWER TO VARIOUS LOADS | | ASSOCIATED WITH THE OFF-GAS SYSTEM NEVER TRIPPED. CALCULATIONS SHOW THAT | | THE ADDITIONAL LOADS WOULD HAVE RESULTED IN DIESEL GENERATOR LOADING | | OUTSIDE THE BOUNDARY OF THE CURRENTLY APPROVED DIESEL GENERATOR LOAD | | CALCULATIONS, RESULTING IN THE UNIT BEING OVERLOADED BY APPROXIMATELY 0.3%. | | THOUGH SLIGHTLY OVERLOADED, THROUGH THE USE OF ENGINEERING JUDGMENT, THE | | CONCLUSION HAS BEEN REACHED THAT THE DIESEL GENERATOR WOULD HAVE REMAINED | | FUNCTIONAL WITH NO IMPACT ON ITS DESIGN FUNCTION. | | | | TO ENSURE FUNCTIONALITY WITHIN THE CURRENT CALCULATED LOAD LIMITS, 480 VAC | | BREAKER 0G1 WAS OPENED AND TAGGED. TESTING OF THE REMAINING CONTACTS AND | | RELAYS ASSOCIATED WITH THE 4160 AND 480 VAC UNDERVOLTAGE CONTACTS IS | | CONTINUING. | | | | AT APPROXIMATELY 1430 CDT, DURING TESTING OF THE 480 VOLT "G" SWITCHGEAR | | (DIVISION 2), THE BREAKERS FOR MCC-V AND MCC-MR FAILED TO MEET TEST | | REQUIREMENTS. THE FUNCTIONALITY OF 480 VOLT "G" SWITCHGEAR AND DIESEL | | GENERATOR #2 HAS BEEN VERIFIED BY ADDING THE MCC LOADS TO THE CURRENT LOAD | | CALCULATIONS. THE DIESEL AND 480 VOLT "G" SWITCHGEAR ARE NOT OVERLOADED | | AND REMAIN FUNCTIONAL. | | | | THE LICENSEE HAS NOTIFIED THE NRC RESIDENT INSPECTOR. | | | | HOO NOTIFIED R4DO (YANDELL), EO (GRIMES). | | | | * * * UPDATE AT 0047 EDT ON 7/22/24 BY HAKENEWERTH TAKEN BY WEAVER * * * | | | | THE UNUSUAL EVENT WAS TERMINATED AT 2330 CDT ON 7/21/94 WHEN THE # 1 EDG | | WAS DECLARED OPERABLE. HOO NOTIFIED RDO (), EO (), FEMA (DAMICO) | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27447 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 06/24/94 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 20:38 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 06/24/94 | +------------------------------------------------+EVENT TIME: 20:20[EDT]| |NRC NOTIFIED BY: BATES |LAST UPDATE DATE: 07/21/94 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN ROGGE 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - POSSIBLE DEFECTIVE FUSES INSTALLED IN VITAL AC INVERTERS IN UNITS 1 & 2 - | | | | BUSSMANN COMPANY REPRESENTATIVES NOTIFIED LICENSEE THAT A POTENTIAL DEFECT | | EXISTS WITH BUSSMANN TYPE KTK, 120 VAC, 5 AMP FUSES WITH DATE CODE #V-303 | | DUE TO A POSSIBLE MANUFACTURING DEFECT. POSSIBLE COLD SOLDER JOINTS COULD | | ALLOW THESE FUSES TO OPEN UNEXPECTEDLY. | | | | THESE TYPE FUSES ARE PRESENTLY INSTALLED IN 6 VITAL AC INVERTERS IN UNIT 2, | | 7 VITAL AC INVERTERS IN UNIT 1 (PRESENTLY AT 100% POWER) AND NO EQUIPMENT | | IN UNIT 3 (PRESENTLY AT 100% POWER). LICENSEE HAS 7 OF THIS TYPE FUSES IN | | STOCK FOR UNITS 1 & 2. | | | | LICENSEE DESTRUCTIVELY TESTED THESE IN-STOCK FUSES AND FOUND NO COLD SOLDER | | JOINTS. | | | | LICENSEE HAS ADEQUATE QUANTITIES OF SUITABLE REPLACEMENT FUSES FROM OTHER | | MANUFACTURERS. | | | | LICENSEE WILL SUBMIT AN LER TO THE NRC ON THESE FUSES. | | | | THE CALLER DID NOT KNOW IF BUSSMANN COMPANY HAD SUBMITTED OR IF THE | | LICENSEE PLANS TO SUBMIT A 10CFR21 REPORT TO THE NRC ON THESE FUSES. | | | | LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | ***UPDATE AT 08:52 ON 07/21/94 BY BATES TO GOULD*** THE LICENSEE IS | | RETRACTING THIS EVENT DUE TO THE DISCOVERY THAT THE FUSES INSTALLED IN UNIT | | 2 INVERTERS DO NOT HAVE THE MANUFACTURES DEFECT FOUND IN THE FUSES | | INSTALLED IN THE UNIT 1 INVERTERS, THEREFORE THE FUSES IN UNIT 2 WERE | | ALWAYS FULLY OPERABLE MAKING THE EVENT NOT REPORTABLE. THE RI WILL BE | | INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |HOSPITAL | |EVENT NUMBER: 27557 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: UNIVERSITY OF PITTSBURGH HOSPITAL |NOTIFICATION DATE: 07/21/94 | | CITY: PITTSBURGH REGION: 1 |NOTIFICATION TIME: 11:42 [ET]| | COUNTY: ALLEGANEY STATE: PA |EVENT DATE: 07/20/94 | |LICENSE#: 37-00245-02 AGREEMENT: N |EVENT TIME: 14:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/21/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM LAZARUS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: JERRY ROSEN | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |IBCA 30.50(b)(3) MED TREAT INVOLV CONT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | UNPLANNED MEDICAL TREATMENT AT A MEDICAL FACILITY OF AN INDIVIDUAL WITH | | SPREADABLE CONTAMINATION AT THE UNIVERSITY OF PITTSBURGH HOSPITAL. | | | | AN INDIVIDUAL WAS CONTAMINATED WITH AN UNDETERMINED AMOUNT OF SN-113. | | (TOTAL AMOUNT SPILLED WAS 8 MICROCURIES). WHILE INJECTING AN ANIMAL WITH A | | SOLUTION CONTAINING 23 MICROCURIES OF SN-113, A LINE BROKE SPLASHING SOME | | OF THE SOLUTION ONTO THE INDIVIDUAL'S FACE AND NECK. | | | | THE CONTAMINATED PERSON WAS TRANSPORTED TO ANOTHER ROOM IN THE HOSPITAL TO | | HAVE HER EYES FLUSHED. THE SPILL WAS CLEANED UP WITHIN ONE HOUR. THE | | PERSON WAS DECONTAMINATED AND THERE WAS NO DAMAGE TO HER EYES. ALL AREAS | | INVOLVED HAVE BEEN DECONTAMINATED AND SURVEYED AND FOUND TO BE CLEAN. | | | | HOO NOTIFIED RDO (LAZARUS) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27558 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 07/21/94 | |UNIT: [ ] [2] [ ] STATE: MN |NOTIFICATION TIME: 12:33 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 07/21/94 | +------------------------------------------------+EVENT TIME: 10:19[CDT]| |NRC NOTIFIED BY: WAGENMANN |LAST UPDATE DATE: 07/21/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BJ HOLT 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 +------------------------------------------------------------------------------+ | THE LICENSEE REPORTED THAT THEY HAD A REACTOR TRIP FROM 100% DUE TO A | | TURBINE TRIP. | | | | THIS OCCURRED WHILE THEY WERE PERFORMING A HYDRO TEST ON THE FIRE | | PROTECTION SYSTEM AFTER A MODIFICATION HAD BEEN INSTALLED AND THE SPRINKLER | | HEAD ACTUATED. THIS ACTUATION SPRAYED WATER OVER THE THE MAIN GENERATOR | | LEADS CAUSING AN ELECTRIC GENERATOR 86 LOCKOUT WHICH RESULTED IN THE | | TURBINE TRIP. ALL RODS FULLY INSERTED DURING THE TRIP AND NO PORV'S OR | | SPRING ACTUATED RELIEF VALVES LIFTED. THEY ALSO EXPERIENCED AN AUX | | FEEDWATER PUMP AUTO START ON LOW S/G LEVEL AND A LETDOWN ISOLATION DUE TO | | LOW PZR LEVEL CAUSED BY RCS COOLDOWN. THE HEAT SINK IS THE AUX FEED AND | | S/G. THE RI WAS INFORMED | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27559 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PILGRIM REGION: 1 |NOTIFICATION DATE: 07/21/94 | |UNIT: [1] [ ] [ ] STATE: MA |NOTIFICATION TIME: 13:21 [ET]| |RX TYPE: [1] GE-3 |EVENT DATE: 07/21/94 | +------------------------------------------------+EVENT TIME: 13:00[EDT]| |NRC NOTIFIED BY: WALZ |LAST UPDATE DATE: 07/21/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 PLANT WILL ENTER A 7 DAY LCO ACTION STATEMENT DUE TO HPCI BEING | | DECLARED INOPERABLE BECAUSE OF A PLANNED SURVEILLANCE TEST. | | | | THIS SURVEILLANCE TEST WILL INVOLVE TESTING THE AUTO SWAP FUNCTION OF THE | | SUCTION PATH OF THE HPCI PUMP FROM THE CST TO THE SUPPRESSION POOL. DURING | | THIS PROPOSED 2-3HR TEST THE HPCI WILL BE DECLARED INOPERABLE BUT | | AVAILABLE. THE RI AND THE STATE HAVE BEEN NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27560 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: INDIAN POINT REGION: 1 |NOTIFICATION DATE: 07/21/94 | |UNIT: [2] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:30 [ET]| |RX TYPE: [2] W-4-LP,[3] W-4-LP |EVENT DATE: 07/19/94 | +------------------------------------------------+EVENT TIME: 13:05[EDT]| |NRC NOTIFIED BY: READY |LAST UPDATE DATE: 07/21/94 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS RDO | |NLTR LICENSEE 24 HR REPORT | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 2 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE LICENSEE ENTERED A 24 HR LCO ACTION STATEMENT DUE TO THE PERFORMANCE OF | | A TEST. | | | | THIS OCCURRED WHILE THEY WERE PERFORMING A TS REQUIRED SURVEILLANCE TEST ON | | THE FIRE MAIN PUMPS(PTM 34) WHICH REQUIRED THEM TO PLACE ALL FIRE PUMPS IN | | THE OFF POSITION. THE TEST AT FIRST WAS UNSATISFACTORY, BUT A RETEST OF THE | | SYSTEM WAS PROVEN SATISFACTORY AT 16:36 ON 7/19/94. THIS REPORT IS BEING | | MADE AT THIS TIME DUE TO THE NOTIFICATION NOT BEING PERFORMED AS PER THEIR | | PROCEDURE SAO124 WHICH REQUIRES A 24HR NOTIFICATION. THE RI WAS INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27561 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 07/21/94 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 13:44 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 07/21/94 | +------------------------------------------------+EVENT TIME: 12:00[EDT]| |NRC NOTIFIED BY: BRYAN CROKE |LAST UPDATE DATE: 07/21/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM LAZARUS 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 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SWAP OF VITAL POWER TO ALTERNATE SOURCE TRIGGERS SEVERAL ESF ACTUATIONS. | | | | WHILE RESTORING VITAL POWER TO THE NORMAL SUPPLY, A SWAP BACK TO THE | | ALTERNATE SOURCE OCCURRED FOR UNKNOWN REASONS. THIS CAUSED A PARTIAL | | ISOLATION OF GROUPS 2, 3, AND 5. THE GROUP 2 ISOLATION INVOLVED EQUIPMENT | | AND FLOOR SUMP OUTBOARD VALVES. THE GROUP 3 ISOLATION CONSISTED OF | | CONTAINMENT AND TORUS OUTBOARD MAKEUP, PURGE, AND VENT VALVES AND START OF | | STANDBY GAS TREATMENT SYSTEM DIVISION "A". THE GROUP 5 ISOLATION WAS THE | | CLOSURE OF THE REACTOR WATER CLEANUP SYSTEM OUTBOARD VALVES. | | | | THE MAIN FEEDWATER REGULATING VALVES LOCKED UP AND REQUIRED MANUAL/REMOTE | | RESET. THE RECIRCULATION PUMP SCOOP TUBES ALSO LOCKED UP. THE LICENSEE IS | | INVESTIGATING THE ROOT CAUSE OF THIS EVENT. | | | | THE LICENSEE INFORMED THE VERMONT DEPARTMENT OF PUBLIC SERVICE AND THE NRC | | RESIDENT INSPECTOR. | | | | HOO NOTE: SEE EVENT 27556. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 27562 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: PORTER CONSULTANTS |NOTIFICATION DATE: 07/21/94 | | CITY: PHILADELPHIA REGION: 1 |NOTIFICATION TIME: 16:26 [ET]| | COUNTY: STATE: PA |EVENT DATE: 07/21/94 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:00[EDT]| | DOCKET: |LAST UPDATE DATE: 07/21/94 | | +-----------------------------+ | |PERSON ORGANIZATION| | |WILLIAM LAZARUS RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: GREG WILHELM & JOHN SYKES | | |HQ OPS OFFICER: RUDY KARSCH | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PORTER CONSULTANTS (HPs) RESPONDED TO A REPORT OF A SOURCE UNCOVERED DURING | | EXCAVATION. THE SOURCE HAD A RADIOACTIVE MATERIAL PLACARD, BUT SPECIFIC | | INFORMATION HAD BEEN OBLITERATED. A SURVEY SHOWED TWICE BACKGROUND | | RADIATION LEVELS. THE SOURCE WAS PLACED INTO A LEAD PIG AND THE AREA | | CLEARED. REGION 1 WAS NOTIFIED AND WILL COORDINATE A RESPONSE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 27563 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 07/21/94 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 18:40 [ET]| |RX TYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 07/21/94 | +------------------------------------------------+EVENT TIME: 18:05[EDT]| |NRC NOTIFIED BY: GLENN LONG |LAST UPDATE DATE: 07/21/94 | |HQ OPS OFFICER: RUDY KARSCH +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |FLOYD CANTRELL RDO | |DDDD 73.71 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY PERSONNEL RECEIVED AND REVIEWED A BACKGROUND INVESTIGATION ON A | | CONTRACT PAINTER INDICATING A CRIMINAL HISTORY THAT WAS NOT IDENTIFIED WHEN | | THE INDIVIDUAL WAS INITIALLY EMPLOYED ON SITE. THE CONTRACTOR WAS GRANTED | | ACCESS BASED UPON A TEMPORARY CLEARANCE ON 5/31/94. THE INDIVIDUAL'S | | ACCESS TO THE PROTECTED AREA WAS TERMINATED ON 6/29/94, AT THE END OF THE | | OUTAGE. THE LICENSEE IS INVESTIGATING WHICH VITAL AREAS WERE ACCESSED AND | | WHETHER THAT WAS CONSISTENT WITH HIS ASSIGNED WORK ACTIVITIES. THERE HAS | | BEEN NO DETRIMENTAL IMPACT IDENTIFIED AS A RESULT OF HIS ACCESS TO THE | | PROTECTED AREA. THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+