U.S. Nuclear Regulatory Commission Operations Center Event Reports For 05/01/98 - 05/04/98 ** EVENT NUMBERS ** 34080 34131 34151 34161 34162 34163 34164 34165 34166 34167 34168 34169 34170 34171 34172 34173 34174 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34080 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 04/16/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 04:45 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 04/15/98 | +------------------------------------------------+EVENT TIME: 23:45[CDT]| |NRC NOTIFIED BY: MARSHALL FUNKHOUSER |LAST UPDATE DATE: 05/02/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AINA 50.72(b)(2)(iii)(A) POT UNABLE TO SAFE SD | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | ONE OF THE SUPPORT PINS THAT SUPPORTS THE NUCLEAR SAFETY PROTECTION SYSTEM | | (NSPS) BAY 'C' POWER SUPPLY DRAWER WAS FOUND MISSING. | | | | THIS NOTIFICATION WAS MADE BASED ON A POWER SUPPLY SUPPORT PIN FOUND | | MISSING. A PIN WAS FOUND MISSING TO THE NSPS BAY 'C' POWER SUPPLY DRAWER. | | THE INDIVIDUAL THAT REMOVED THE POWER SUPPLY DRAWER NOTED THAT THE PIN WAS | | NOT INSTALLED. IT IS NOT KNOWN HOW LONG THIS PIN HAS BEEN MISSING. | | | | THE PROPER OPERATION OF THE NSPS POWER SUPPLY DRAWER DURING A SEISMIC EVENT | | IS IN QUESTION. THERE IS NO PRESENT DATA KNOWN ON HOW THIS MISSING PIN | | WOULD IMPACT THIS TYPE OF EVENT; HOWEVER, THE RESIDUAL HEAT REMOVAL SYSTEM | | 'B' AND 'C' TRAINS AND THE AUTOMATIC DEPRESSURIZATION SYSTEM LOGIC REQUIRE | | POWER TO INITIATE. THUS, THE ABILITY OF THESE SYSTEMS TO OPERATE DURING A | | SEISMIC EVENT IS IN QUESTION. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED OF THIS EVENT BY THE LICENSEE. | | | | * * * UPDATE AT 0710 ON 05/02/98 FROM ROBERT POWERS TO MACKINNON * * * | | | | FURTHER EVALUATION OF THE MISSING SUPPORT PIN HAS DETERMINED THAT IT IS | | STRUCTURALLY ACCEPTABLE FOR ONE SUPPORT PIN TO BE MISSING. THE IDENTIFIED | | CONDITION HAS NO AFFECT ON THE SEISMIC QUALIFICATION OF THE POWER SUPPLY | | SUPPORT. THEREFORE, THE LICENSEE IS RETRACTING THIS EVENT REPORT. | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R3DO (ROGER LANKSBURY). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34131 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FT CALHOUN REGION: 4 |NOTIFICATION DATE: 04/26/98 | |UNIT: [1] [ ] [ ] STATE: NE |NOTIFICATION TIME: 02:41 [ET]| |RX TYPE: [1] CE |EVENT DATE: 04/25/98 | +------------------------------------------------+EVENT TIME: 23:22[CDT]| |NRC NOTIFIED BY: DAVE BANNISTER |LAST UPDATE DATE: 05/01/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ELMO COLLINS 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT EMERGENCY DIESEL GENERATOR START DURING SYSTEM LINEUP | | | | WHILE PERFORMING A SYSTEM ALIGNMENT IN ACCORDANCE WITH PLANT PROCEDURE | | OI-DG-1, CHECKLIST E, THE #2 EMERGENCY DIESEL GENERATOR (EDG) WAS | | INADVERTENTLY STARTED WHEN HAND SWITCH 43-1/D2 WAS TAKEN FROM "OFF AUTO" | | TO "EMERGENCY STANDBY." THE LICENSEE REPORTED THAT 4160 VAC BUS 1A4 HAD | | BEEN REMOVED FROM SERVICE FOR MAINTENANCE, AND IT WAS DEENERGIZED AT THE | | TIME OF THE EVENT. THE EDG STARTED (BUT DID NOT LOAD TO THE BUS) AS THE | | EDG OUTPUT BREAKER WAS OPEN AND RACKED DOWN. THE EDG WAS SUBSEQUENTLY SHUT | | DOWN, AND THE HAND SWITCH WAS TAKEN BACK TO THE "OFF AUTO" POSITION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1519 ON 05/01/98 FROM MATZKE TO GOULD * * * | | | | FURTHER REVIEW OF THE INCIDENT INDICATES THAT THE #2 EDG START WAS CAUSED | | BY A NON-EMERGENCY SAFEGUARDS FUNCTION SIGNAL AND THAT THE EDG WAS PROPERLY | | REMOVED FROM SERVICE AT THAT TIME. THEREFORE, THE LICENSEE IS RETRACTING | | THIS REPORT. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R4DO (PHIL HARRELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34151 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 04/29/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 17:38 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 04/29/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 14:30[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/02/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY/REG3 RDO | | DOCKET: 0707002 |FREDERICK COMBS/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: STEVE MAY | | |HQ OPS OFFICER: JOHN MacKINNON | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NRC BULLETIN 91-01 RESPONSE (4-HOUR REPORT) | | | | NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) DOES NOT DOCUMENT THAT THE | | DOUBLE CONTINGENCY IS MET FOR WET AIR IN LEAKAGE AND LUBE OIL IN LEAKAGE | | FOR THE EXTENDED RANGE PRODUCT (ERP) WITHDRAWAL STATION. NUCLEAR | | CRITICALITY SAFETY PERSONNEL DISCOVERED THAT THE ERP WITHDRAWAL STATION | | (WITHDRAWS LOW ASSAY LIQUID URANIUM HEXAFLUORIDE INTO CYLINDERS) NCSA DOES | | NOT DOCUMENT THAT THE DOUBLE CONTINGENCY IS MET FOR WET AIR IN LEAKAGE AND | | LUBE OIL IN LEAKAGE. NCSA-0326_015.A03 WAS WRITTEN TO ADDRESS THIS ISSUE, | | BUT IT WAS NEVER APPROVED BY THE PLANT OPERATIONS REVIEW COMMITTEE. | | CONTROLS (MODERATION AND GEOMETRY) WERE MAINTAINED THROUGHOUT THIS EVENT. | | THIS IS ALSO A VIOLATION OF THE PLANT TECHNICAL SAFETY REQUIREMENT. THE | | PLANT SUPERINTENDENT DIRECTED THE ERP STATION TO BE PLACED IN STANDBY. | | THERE WAS NO LOSS OF HAZARD/RADIOACTIVE MATERIAL, AND THERE WERE NO | | RADIOACTIVE/RADIOLOGICAL CONTAMINATION EXPOSURES AS A RESULT OF THIS EVENT. | | | | THIS IS A DOCUMENTATION PROBLEM. THE OPERATION DOES IN FACT MEET THE | | DOUBLE CONTINGENCY AS DEMONSTRATED IN THE ANALOGOUS NCSA FOR THE LOW ASSAY | | WITHDRAWAL STATION (0333_017.A01). | | | | PORTSMOUTH PERSONNEL INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1723 ON 05/02/98 FROM MAY TO GOULD * * * | | | | IN REFERENCE TO NOTICE OF VIOLATION 70-7002/97206-06 ON 07/24/97, SIMILAR | | CONDITIONS WERE IDENTIFIED AT THE SITE'S TAILS AND LOW ACTIVE WASTE (LAW) | | WITHDRAWAL STATIONS. HOWEVER, AN EVENT REPORT WAS NOT INITIATED AT THAT | | TIME. ON 08/04/97, NCSE-0333_017.E01 WAS REVISED TO REFLECT THE DOUBLE | | CONTINGENCY FOR THE LAW STATION; AND ON 10/20/97, NSCE-0330_007.E01 WAS | | ALSO REVISED TO REFLECT THE DOUBLE CONTINGENCY FOR THE TAILS WITHDRAWAL | | STATION. PROCEDURAL REQUIREMENTS DID NOT CHANGE AS A RESULT OF THE | | NCSA/NCSE REVISIONS, AND PRESENTLY ALL WITHDRAWAL STATIONS HAVE NCSA/NCSE | | IN PLACE WHICH REFLECT THE DOUBLE CONTINGENCY. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR. THE R3DO | | (LANKSBURY), NMSS EO (COMBS), AND AEOD IRD (BARRETT) WERE NOTIFIED BY THE | | NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34161 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALVERT CLIFFS REGION: 1 |NOTIFICATION DATE: 05/01/98 | |UNIT: [1] [2] [ ] STATE: MD |NOTIFICATION TIME: 07:39 [ET]| |RX TYPE: [1] CE,[2] CE |EVENT DATE: 04/30/98 | +------------------------------------------------+EVENT TIME: 10:00[EDT]| |NRC NOTIFIED BY: J. OSBORNE/J. HOLLEMAN |LAST UPDATE DATE: 05/01/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |HFIT 26.73 FITNESS FOR DUTY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - FITNESS FOR DUTY REPORT - | | | | A LICENSED EMPLOYEE WAS DETERMINED TO BE UNDER THE INFLUENCE OF ALCOHOL | | DURING A RANDOM TEST. THE EMPLOYEE'S PLANT ACCESS AUTHORIZATION HAS BEEN | | SUSPENDED. (REFER TO THE HOO LOG FOR ADDITIONAL DETAILS.) THE LICENSEE | | PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34162 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: SIEMENS POWER CORP/NUCLEAR DIVISION |NOTIFICATION DATE: 05/01/98 | | CITY: RICHLAND REGION: 4 |NOTIFICATION TIME: 11:20 [ET]| | COUNTY: BENTON STATE: WA |EVENT DATE: 04/29/98 | |LICENSE#: SNM-1227 AGREEMENT: Y |EVENT TIME: 17:00[PDT]| | DOCKET: |LAST UPDATE DATE: 05/01/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |NIEL DELLA GRECA RDO | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: JIM MALLAY | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT - DEVIATION IN THE RELAP4 PORTION OF THE LARGE BREAK | | LOSS OF COOLANT ACCIDENT (LBLOCA) EVALUATION MODEL (REFER TO EVENT #34165 | | FOR ADDITIONAL INFORMATION.) | | | | SIEMENS POWER CORPORATION (SPC) HAS IDENTIFIED A DEVIATION IN THE RELAP4 | | PORTION OF THE LBLOCA EVALUATION MODEL. SMALL CHANGES IN THE INPUT TO | | RELAP4 (PART OF THE EXEM/PWR LBLOCA EVALUATION MODEL) CAN RESULT IN LARGE | | CHANGES IN THE CALCULATED PEAK CLADDING TEMPERATURE DURING A LBLOCA. THESE | | RESULTS ARE CONSIDERED EXCESSIVE GIVEN THE SIZE OF THE INPUT CHANGES. THE | | PLANTS FOR WHICH SPC PROVIDES LBLOCA ANALYSES HAVE ALL BEEN EVALUATED WITH | | THIS DEVIATION CORRECTED IN THE LBLOCA EVALUATION MODEL. THE RESULTS OF | | THESE ANALYSES FOR FOUR OF THESE PLANTS INDICATE THAT THE EARLIER ANALYSES | | WITH THE DEVIATION ARE CONSERVATIVE [i.e., RESULT IN HIGHER PEAK CLADDING | | TEMPERATURES (PCT)] RELATIVE TO THE RESULTS FROM THE CORRECTED MODEL. THE | | PCTs ARE LOWER USING THE CORRECTED MODEL FOR THESE FOUR PLANTS BY | | APPROXIMATELY 30øF TO 130øF. | | | | THE RESULTS OF THE ANALYSES FOR A FIFTH PLANT, MILLSTONE UNIT 2, INCREASE | | THE PCT BY MORE THAN 50øF, AND THE PCTs EXCEED THE 2,200øF CRITERION IN | | 10 CFR 50.46. MILLSTONE UNIT 2 IS CURRENTLY SHUTDOWN AND DEFUELED. A | | REVISED LBLOCA ANALYSIS TO SUPPORT THE RESTART OF MILLSTONE UNIT 2 WILL BE | | PROVIDED BY SPC TO NORTHEAST UTILITIES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34163 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 05/01/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 13:12 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 05/01/98 | +------------------------------------------------+EVENT TIME: 12:32[EDT]| |NRC NOTIFIED BY: ABBOTT |LAST UPDATE DATE: 05/01/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |ACCS 50.72(b)(1)(iv) ECCS INJECTION | | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | M/R Y 100 POWER OPERATION | 0 HOT SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MANUAL SCRAM FROM 100% DUE TO CONTROL ROD DRIFT ALARMS; Rx VESSEL INJECTION | | | | THIS MANUAL SCRAM WAS INITIATED DUE TO INDICATION OF MULTIPLE CONTROL ROD | | DRIFT ALARMS IN THE CONTROL ROOM. THE CAUSE OF THE ALARMS IS UNKNOWN AT | | THIS TIME AND IS BEING INVESTIGATED. ALL CONTROL RODS WERE DETERMINED TO | | BE FULLY INSERTED INTO THE CORE AFTER VERIFICATION WAS MADE ON THREE RODS | | WHICH INITIALLY APPEARED NOT TO HAVE BEEN FULLY INSERTED. NONE OF THE | | SAFETY/RELIEF VALVES LIFTED, BUT THE HPCI AND RCIC SYSTEMS INJECTED TO THE | | REACTOR VESSEL. THE AMOUNT AND DURATION OF THE INJECTIONS HAVE NOT BEEN | | DETERMINED AT THIS TIME, BUT THESE SYSTEMS HAVE BEEN SECURED. THE NORMAL | | FEED SYSTEM IS CURRENTLY IN USE, AND THE MAIN CONDENSER IS BEING USED AS | | THE HEAT SINK. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34164 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DEPT OF THE ARMY, ROCK ISLAND, IL |NOTIFICATION DATE: 05/01/98 | | CITY: FORT CAMPBELL REGION: 2 |NOTIFICATION TIME: 13:50 [ET]| | COUNTY: STATE: KY |EVENT DATE: 05/01/98 | |LICENSE#: 12-00722-13 AGREEMENT: Y |EVENT TIME: 13:40[EDT]| | DOCKET: |LAST UPDATE DATE: 05/01/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MIKE JORDAN/REG 3 RDO | | |SCOTT MOORE/NMSS EO | +------------------------------------------------+PIERCE SKINNER/REG 2 RDO | |NRC NOTIFIED BY: HAVENNER |RICHARD BARRETT/AEOD IRD | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | THE DEPARTMENT OF THE ARMY IN ROCK ISLAND, ILLINOIS, REPORTED THAT A M43A1 | | CHEMICAL AGENT DETECTOR CONTAINING 250 MICROCURIES OF AMERICIUM-241 WAS | | MISSING IN THE FIELD AT FORT CAMPBELL, KENTUCKY. ARMY PERSONNEL ARE | | CURRENTLY SEARCHING FOR THE DETECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34165 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/01/98 | |UNIT: [ ] [2] [ ] STATE: CT |NOTIFICATION TIME: 15:27 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/01/98 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: TRUESDALE |LAST UPDATE DATE: 05/01/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POSSIBILITY OF THE REACTOR EXCEEDING ITS PEAK CLAD TEMPERATURE LIMIT (REFER | | TO EVENT #34162 FOR ADDITIONAL INFORMATION.) | | | | THE LICENSEE WAS INFORMED BY THE FUEL VENDOR (SIEMENS POWER CORPORATION) | | THAT A PRELIMINARY REANALYSIS FOR THE LARGE BREAK LOCA INDICATES THAT | | UNIT 2 WOULD EXCEED A PEAK CLAD TEMPERATURE OF 2,200øF DURING THE WORST | | CASE ANALYZED LARGE BREAK LOCA. THIS IS IN VIOLATION OF THE CRITERIA | | CONTAINED IN 10 CFR 50.46 AND GENERAL DESIGN CRITERION 35. THE REVISED | | ANALYSIS INDICATES THAT PEAK CLAD TEMPERATURE WOULD ONLY EXCEED 2,200øF IF | | THE LINEAR HEAT RATE IS GREATER THAN 14.6 KW/FT AT THE START OF THE LARGE | | BREAK LOCA EVENT. UNIT 2 TECHNICAL SPECIFICATIONS ALLOW OPERATION WITH A | | LINEAR HEAT RATE AS HIGH AS 15.1 KW/FT. THE LARGE BREAK LOCA EVENT IS IN | | THE PROCESS OF BEING REANALYZED. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34166 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NAMCO CONTROLS |NOTIFICATION DATE: 05/01/98 | | CITY: HIGHLAND HEIGHT REGION: 3 |NOTIFICATION TIME: 15:55 [ET]| | COUNTY: STATE: OH |EVENT DATE: 05/01/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 00:01[EDT]| | DOCKET: |LAST UPDATE DATE: 05/01/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |MIKE JORDAN, R3 RDO | | | | +------------------------------------------------+VERN HODGE NRR | |NRC NOTIFIED BY: JOSEPH |NIEL DELLA GRECA, R1 RDO | |HQ OPS OFFICER: CHAUNCEY GOULD |AL BELISLE, R2 RDO | +------------------------------------------------+PHIL HARRELL, R4 RDO | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CCCC 21.21 UNSPECIFIED PARAGRAPH | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 21 REPORT - NAMCO CONTROLS' LIMIT SWITCHES HAVE AN IMPREGNATION | | SEALANT ANOMALY. | | | | DURING A REVIEW OF A RECEIPT INSPECTION CLOSED PURCHASE ORDER, IT WAS | | DISCOVERED THAT THE SUPPLIER WHO IMPREGNATED THE EA180 HOUSING DID NOT USE | | THE QUALIFIED SEALANT. THE LIMIT SWITCHES AFFECTED WERE MANUFACTURED FROM | | 12/18/97 THROUGH 03/27/98. THE IMPREGNATION SUPPLIER USED IMPREX 95-1000A | | WHICH WAS NOT PREVIOUSLY QUALIFIED BY NAMCO CONTROLS. NAMCO USES IMPREX | | 95-500, BUT IT IS BEING DISCONTINUED DUE TO ENVIRONMENTAL BENEFITS. IT HAS | | BEEN DETERMINED THAT APPROXIMATELY 112 IMPROPERLY IMPREGNATED HOUSINGS WERE | | SHIPPED TO NUCLEAR CUSTOMERS. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 34167 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 05/01/98 | | CITY: BALDWIN REGION: 2 |NOTIFICATION TIME: 16:22 [ET]| | COUNTY: STATE: FL |EVENT DATE: 05/01/98 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 15:00[EDT]| | DOCKET: |LAST UPDATE DATE: 05/01/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |PIERCE SKINNER/REG 2 RDO | | |FREDERICK COMBS/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: DAKINS | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A NUCLEAR GAUGE WAS DISCOVERED IN A SCRAP METAL YARD IN BALDWIN, FLORIDA. | | A STATE INSPECTOR WAS SENT TO BALDWIN FROM JACKSONVILLE TO SURVEY THE | | DEVICE. THE DEVICE MEASURED 1 MR/HR ON CONTACT. ITS PHYSICAL DIMENSIONS | | ARE 4 INCHES X 4 INCHES X 4 INCHES WITH A PLACE FOR ELECTRICAL CONNECTIONS | | ON ITS SIDE. THE STATE OF FLORIDA HAS THE DEVICE IN ITS POSSESSION AND | | PLANS TO TAKE IT TO ORLANDO ON 05/04/98. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34168 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 05/01/98 | |UNIT: [1] [ ] [ ] STATE: NJ |NOTIFICATION TIME: 19:57 [ET]| |RX TYPE: [1] GE-2 |EVENT DATE: 05/01/98 | +------------------------------------------------+EVENT TIME: 19:00[EDT]| |NRC NOTIFIED BY: CIGANIK |LAST UPDATE DATE: 05/01/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | FAILURE TO TEST A FIRE DETECTION SYSTEM DETECTOR IN THE HEATING VENTILATION | | AND AIR CONDITIONING (HVAC) SYSTEM SUPPLY DUCT | | | | WHILE REVIEWING THE RESPONSE OF THE CONTROL ROOM HVAC SYSTEM TO VARIOUS | | ACTUATION SIGNALS FROM THE FIRE DETECTION SYSTEM, IT WAS DETERMINED THAT | | THE SUPPLY DUCT DETECTOR IN ONE OF THE SYSTEMS HAD NOT BEEN TESTED AS | | REQUIRED BY THE PLANT'S FIRE PROTECTION PROGRAM. THE TESTING OF THIS | | DETECTOR WAS NOT INCLUDED IN THE ROUTINE TESTING PROGRAM. ALTHOUGH THIS | | DETECTOR HAS NOT BEEN TESTED, OTHER DETECTORS WHICH WOULD PERFORM A SIMILAR | | FUNCTION HAVE BEEN ROUTINELY TESTED. APPROPRIATE COMPENSATORY ACTIONS | | HAVE BEEN IMPLEMENTED. A PLAN IS BEING WRITTEN TO TEST THE DETECTOR IN | | QUESTION. A FIRE WATCH WILL BE REQUIRED IF THIS SYSTEM IS PLACED IN | | OPERATION. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34169 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BYRON REGION: 3 |NOTIFICATION DATE: 05/02/98 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 10:07 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/02/98 | +------------------------------------------------+EVENT TIME: 05:48[CDT]| |NRC NOTIFIED BY: MORRIS |LAST UPDATE DATE: 05/02/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ROGER LANKSBURY 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 N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BREACH OF THE CHEMICAL AND VOLUME CONTROL SYSTEM (CVCS) | | | | WHILE IN MODE 6 IN A REFUELING OUTAGE AND DURING PERFORMANCE OF SCHEDULED | | OUTAGE ACTIVITIES, THE COMMON SUCTION LINE TO THE CENTRIFUGAL CHARGING | | PUMPS WAS BREACHED WITH A 1/4-INCH DIAMETER HOLE IN THE PIPE. THE ACTIVITY | | WAS A PLANNED MODIFICATION TO INSTALL A 3/4-INCH VENT LINE, BUT IT WAS | | OUTSIDE OF AN EXISTING OUT-OF-SERVICE BOUNDARY. THIS BREACH POTENTIALLY | | RENDERED THE CVCS INCAPABLE OF PROVIDING AN EMERGENCY BORATION FLOW PATH | | TO MITIGATE THE CONSEQUENCES OF A DILUTION ACCIDENT. THE CVCS HAS BEEN | | DECLARED INOPERABLE DUE TO THE INOPERABLE BORATION FLOW PATH AND THE STATE | | OF THE SYSTEM'S STRUCTURAL INTEGRITY. ENGINEERING PERSONNEL ARE PERFORMING | | AN EVALUATION. THE LICENSEE CAN INSTALL A FREEZE SEAL OR ISOLATE THE DRAIN | | SYSTEM TO ISOLATE THE BREACH AND REPAIR IT. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34170 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: SOUTH TEXAS REGION: 4 |NOTIFICATION DATE: 05/02/98 | |UNIT: [1] [ ] [ ] STATE: TX |NOTIFICATION TIME: 15:38 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 05/01/98 | +------------------------------------------------+EVENT TIME: 22:34[CDT]| |NRC NOTIFIED BY: HARRISON |LAST UPDATE DATE: 05/03/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PHIL HARRELL RDO | |ADEV 50.72(b)(1)(i)(B) DEVIATION FROM T SPEC | | |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 +------------------------------------------------------------------------------+ | UNIT 1 ENTERED TECHNICAL SPECIFICATION 3.0.3 WHEN TWO EXHAUST BOOSTER FANS | | WERE MADE INOPERABLE BECAUSE THE THIRD FAN NEEDED TO BE REPLACED. | | | | ON 04/29/98, THE FUEL HANDLING BUILDING (FHB) #11B EXHAUST BOOSTER FAN | | FAILED AND NEEDS TO BE REPLACED. THE FAILED FAN CAN BE REPLACED WITHIN ITS | | 7-DAY ALLOWED OUTAGE TIME. HOWEVER, REPLACEMENT OF THE FAN WILL REQUIRE | | MAKING THE OTHER TWO EXHAUST BOOSTER FANS THAT SHARE THE COMMON SUPPLY AND | | THE EXHAUST PLENUMS INOPERABLE FOR THE BRIEF TIME NEEDED TO INSTALL AND | | SUBSEQUENTLY REMOVE A TEMPORARY MODIFICATION. THE LICENSEE REQUESTED AND | | WAS GRANTED ENFORCEMENT DISCRETION FROM THE REQUIREMENT TO APPLY TECHNICAL | | SPECIFICATION 3.0.3 FOR THE 8 HOURS REQUIRED TO INSTALL THE TEMPORARY | | MODIFICATION AND THE 6 HOURS REQUIRED TO REMOVE THE TEMPORARY MODIFICATION | | SO THAT REPAIRS OF THE #11B FHB EXHAUST BOOSTER FAN CAN BE COMPLETED. | | | | THE INITIAL ENTRY WAS MADE AT 2234 CDT ON 05/01/98 UNTIL 0222 CDT ON | | 05/02/98 TO FACILITATE INSTALLATION OF A TEMPORARY MODIFICATION REQUIRED TO | | REMOVE THE FHB #11B EXHAUST BOOSTER FAN. ACCORDING TO THE DISCRETION, THE | | LICENSEE EXPECTS TO ENTER TECHNICAL SPECIFICATION 3.0.3 AGAIN FROM | | APPROXIMATELY 1830 CDT ON 05/03/98 UNTIL 2300 CDT ON 05/03/98 IN ORDER TO | | FACILITATE REMOVAL OF THE TEMPORARY MODIFICATION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 0842 EDT ON 05/03/98 FROM BROWN RECEIVED BY TROCINE * * * | | | | THE FINAL TECHNICAL SPECIFICATION 3.0.3 ENTRY (FOR REMOVAL OF THE TEMPORARY | | MODIFICATION AFTER COMPLETION OF THE FAN REPLACEMENT) WAS MADE AT 2237 CDT | | ON 05/02/98. THIS TECHNICAL SPECIFICATION WAS EXITED AT 0224 CDT ON | | 05/03/98. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. THE R4DO | | (HARRELL) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34171 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/02/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 16:00 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/02/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:22[CDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/02/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY/REG3 RDO | | DOCKET: 0707001 |FREDERICK COMBS/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: BOSHELL | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SAFETY SYSTEM ACTUATION IN THE C-337A BUILDING (24-HOUR REPORT) | | | | IT WAS DETERMINED THAT A SAFETY SYSTEM ACTUATION HAD OCCURRED IN THE C-337A | | BUILDING ON AUTOCLAVE POSITION 2 WEST. THE AUTOCLAVE WAS APPROXIMATELY 1 | | TO 2 HOURS FROM COMPLETING THE FEED CYCLE FOR UF6 CYLINDER EM-1119 TO THE | | ENRICHMENT CASCADE. THE STEAM CONTROLLER SYSTEM MALFUNCTIONED. THIS | | CAUSED THE PRESSURE INSIDE THE AUTOCLAVE TO RISE TO THE ALARM SETPOINT, AND | | IT ACTUATED THE STEAM PRESSURE CONTROL SAFETY SYSTEM. THE SAFETY SYSTEM | | PERFORMED AS DESIGNED, AND THE AUTOCLAVE WAS PLACED IN A SAFE CONDITION. | | | | THE EVENT NOTIFICATION WAS MADE IN ACCORDANCE WITH SAFETY ANALYSIS REPORT | | TABLE 6.9-1, CRITERION J.2, AS AN ACTUATION OF A 'Q' SYSTEM IN RESPONSE TO | | A VALID SIGNAL. THIS EVENT REQUIRES A 24-HOUR NOTIFICATION TO THE NRC. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY PADUCAH PERSONNEL. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34172 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 05/03/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:08 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 05/02/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 03:44[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 05/03/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY RDO | | DOCKET: 0707002 |FREDERICK COMBS/NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: KEITH VANDERPOOL | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AUTOCLAVE STEAM SHUTDOWN ALARM DUE TO A HIGH CONDENSATE LEVEL CONDITION | | (24-HOUR REPORT) | | | | AT 0344 ON 05/02/98, OPERATIONS PERSONNEL RECEIVED A STEAM SHUTDOWN ALARM | | ON AUTOCLAVE #6 DURING A CYLINDER HEATING CYCLE (MODE II). THE STEAM | | SHUTDOWN WAS CAUSED BY AN ACTUATION OF THE 'B' PROBE IN THE HIGH CONDENSATE | | LEVEL SHUTOFF SYSTEM (A 'Q' SYSTEM). INVESTIGATION OF THE ALARM REVEALED | | THAT IT WAS CAUSED BY AN ACTUAL HIGH CONDENSATE LEVEL CONDITION WHICH | | CLEARED 2 MINUTES AFTER THE STEAM SHUTDOWN OCCURRED. THE CYLINDER IN THIS | | AUTOCLAVE WAS DISCONNECTED, AND THE AUTOCLAVE WAS DECLARED INOPERABLE FOR | | TESTING OF THE HIGH CONDENSATE LEVEL SHUTOFF SYSTEM BY MAINTENANCE | | PERSONNEL. | | | | THE CAUSE FOR THE HIGH LEVEL IN THE CONDENSATE DRAIN LINE IS BEING | | EVALUATED. SUBSEQUENT FLUSH SAMPLES TAKEN IN ACCORDANCE WITH OFF-NORMAL | | OPERATING PROCEDURES SHOWED DISCOLORATION IN THE CONDENSATE WATER. HIGH | | CONDENSATE LEVEL PROBES 'A' AND 'B' WERE FUNCTIONALLY TESTED AND PASSED. | | AUTOCLAVE #6 WILL REMAIN OUT OF SERVICE PENDING AN ENGINEERING EVALUATION | | AND RESOLUTION OF THE CONDENSATE STRAINER ISSUE. THERE WAS NOTHING UNUSUAL | | OR MISUNDERSTOOD, AND ALL SYSTEMS FUNCTION AS REQUIRED. THERE WAS NO | | RELEASE OF HAZARDOUS OR RADIOACTIVE MATERIAL, AND THERE WERE NO RADIOACTIVE | | OR RADIOLOGICAL CONTAMINATION EXPOSURES AS A RESULT OF THIS EVENT. | | | | THIS EVENT IS REPORTABLE PER SAFETY ANALYSIS REPORT SECTION 6.9. | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND PLAN TO NOTIFY | | THE SITE DEPARTMENT OF ENERGY REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34173 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/03/98 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 14:23 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/03/98 | +------------------------------------------------+EVENT TIME: 12:46[EDT]| |NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 05/03/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA RDO | |AMED 50.72(b)(2)(v) OFFSITE MEDICAL | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - POTENTIALLY CONTAMINATED CONTRACTOR TRANSPORTED TO LOCAL HOSPITAL - | | | | LICENSEE HEALTH PHYSICS TECHNICIANS ACCOMPANIED A POTENTIALLY CONTAMINATED | | TEMPORARY CONTRACTOR MECHANIC TO OSWEGO HOSPITAL FOR MEDICAL EVALUATION. | | THE MECHANIC HAD EXPERIENCED HEAT STRESS WHILE PERFORMING DECONTAMINATION | | WORK IN THE UNIT 2 DRYWELL (PRIMARY CONTAINMENT). | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34174 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 05/03/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:57 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 05/03/98 | +------------------------------------------------+EVENT TIME: 15:00[EDT]| |NRC NOTIFIED BY: FRANK SIENCZAK |LAST UPDATE DATE: 05/03/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |NIEL DELLA GRECA 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 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - SHUTDOWN COOLING SYSTEM ISOLATED DURING TESTING DUE TO HUMAN ERROR - | | | | WHILE ELECTRICIANS WERE REPAIRING AND 'VOTES' TESTING SHUTDOWN COOLING | | VALVE #IV-38-02, AN INADVERTENT AND INVALID SHUTDOWN COOLING SYSTEM | | ISOLATION OCCURRED. THE LICENSEE'S INVESTIGATION REVEALED THAT AN | | ELECTRICIAN PERFORMING THE MAINTENANCE TESTING ON THE VALVE CAUSED REACTOR | | PROTECTION SYSTEM FUSE 'UC' TO BLOW WHICH CAUSED THE SHUTDOWN COOLING | | SYSTEM ISOLATION. THE ELECTRICIANS STOPPED THE TESTING, REPLACED THE FUSE, | | UNISOLATED THE SYSTEM, AND RETURNED IT TO SERVICE. | | | | THE LICENSEE IS INVESTIGATING THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+