U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/12/98 - 01/13/98 ** EVENT NUMBERS ** 33378 33518 33519 33520 33521 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33378 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 12/10/97 | |UNIT: [ ] [ ] [3] STATE: SC |NOTIFICATION TIME: 14:11 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 12/10/97 | +------------------------------------------------+EVENT TIME: 13:10[EST]| |NRC NOTIFIED BY: NIX |LAST UPDATE DATE: 01/12/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PAUL FREDRICKSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 100 POWER OPERATION | 90 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF A POSSIBILITY OF THE ECCS BECOMING INOPERABLE DURING THE SUMP | | RECIRCULATING MODE | | | | ON 12/08/97, DURING A SELF-INITIATED TECHNICAL AUDIT OF THE PLANTS ECCS, IT | | WAS DETERMINED THAT A CERTAIN INPUT WAS NOT CONSIDERED IN AN ASSUMPTION IN | | THE CALCULATIONS ASSOCIATED WITH TRANSPORTATION OF DEBRIS TO THE REACTOR | | BUILDING EMERGENCY SUMP DURING THE RECIRCULATION MODE. INCLUSION OF THIS | | INPUT RESULTED IN A REDUCTION IN THE MINIMUM AVAILABLE SUMP WATER LEVEL, | | WHICH CAUSED INCREASED FLOW VELOCITIES AND CONSEQUENTLY INCREASED | | TRANSPORTABILITY OF DEBRIS SUCH AS INSULATION. INCREASED TRANSPORTABILITY | | OF DEBRIS COULD RESULT IN INCREASED SUMP BLOCKAGE AND REDUCED AVAILABLE | | ECCS NET PUMP SUCTION HEAD (NPSH). AS A RESULT, THIS CONDITION IS BEING | | FURTHER INVESTIGATED. | | | | THERE ARE CERTAIN MEASURES THAT CAN BE TAKEN TO INCREASE THE AVAILABLE ECCS | | NPSH. THESE MEASURES INCLUDE REMOVAL OF THE STRAINERS FROM THE FUEL | | TRANSFER CANAL, REMOVAL OF A FLANGE FROM THE REACTOR VESSEL ANNULUS DRAIN, | | AND REMOVAL OF INSULATION SUSCEPTIBLE TO TRANSPORTABILITY. | | | | SINCE UNIT 1 IS SHUTDOWN, THESE ECCS REQUIREMENTS ARE NOT CURRENTLY | | APPLICABLE, BUT THEY WILL BE ADDRESSED PRIOR TO RESTART. UNIT 2 HAS NO | | INSULATION SUSCEPTIBLE TO TRANSPORT; THEREFORE, THERE IS GREATER CONFIDENCE | | IN THE PRELIMINARY ENGINEERING ASSESSMENT THAT ADEQUATE ECCS NPSH EXISTS ON | | UNIT 2 THAN ON UNIT 3, EVEN WITH REDUCED WATER LEVELS. | | | | UNIT 3 IS REDUCING POWER TO FACILITATE THE REMOVAL OF INSULATION, | | STRAINERS, AND FLANGES SO THAT THE AVAILABLE ECCS MARGIN WILL INCREASE. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. | | | | * * * UPDATE ON 12/12/97 AT 1200 FROM ED BURCHFIELD TAKEN BY MACKINNON * * | | | | AT THIS TIME, RELEVANT INSULATION HAS BEEN REMOVED FROM UNIT 3 AND IS NOT | | PRESENT ON UNIT 2. THE REACTOR VESSEL DRAIN FLANGE WAS REMOVED ON UNIT 2 | | AND VERIFIED TO NOT BE PRESENT ON UNIT 3. THE FUEL TRANSFER CANAL | | STRAINERS HAVE BEEN REMOVED FROM UNITS 2 AND 3. THE RELEVANT INSULATION, | | REACTOR VESSEL DRAIN FLANGE, AND FUEL TRANSFER CANAL STRAINERS WILL ALSO BE | | REMOVED FROM UNIT 1 PRIOR TO EXCEEDING COLD SHUTDOWN CONDITIONS. UNIT 1 IS | | IN COLD SHUTDOWN, AND UNITS 2 AND 3 ARE OPERATING AT 100% FULL POWER. | | | | THE OPERABILITY EVALUATION HAS BEEN COMPLETED AND CONCLUDES THAT THE ECCS | | ON ALL THREE UNITS IS OPERABLE. THEREFORE, NO ENTRY INTO TECHNICAL | | SPECIFICATIONS IS REQUIRED. OCONEE CONSERVATIVELY REPORTED THIS EVENT ON | | UNIT 3 AS A 1-HOUR NON-EMERGENCY NOTIFICATION UNDER 10CFR50.72(b)(1)(ii)(B) | | AS A CONDITION THAT MAY BE OUTSIDE THE DESIGN BASIS OF THE PLANT IN THAT | | THIS CONDITION COULD POTENTIALLY RESULT IN THE INOPERABILITY OF THE ECCS | | DURING THE SUMP RECIRCULATION MODE OF A LOCA. ALTHOUGH NO OPERABILITY | | CONCERNS EXIST REGARDING THE CURRENT CONFIGURATION OF THE THREE OCONEE | | UNITS, ANALYSES ARE UNDERWAY TO EVALUATE OPERABILITY OF THE ECCS IN THE | | PAST. THESE ANALYSES WILL CONSIDER THE IMPACT OF REMOVED INSULATION AND | | FUEL TRANSFER CANAL/REACTOR VESSEL CAVITY FLOW RESTRICTIONS ON OPERABILITY | | OF THE EMERGENCY SUMP FOR ALL THREE OCONEE UNITS IN THE PAST. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS UPDATE. THE R2DO | | (PAUL FREDRICKSON) WAS NOTIFIED OF THIS UPDATE BY THE OPERATIONS OFFICER. | | | | * * * UPDATE ON 01/12/98 AT 1608 FROM HENRY LOWERY TAKEN BY JOLLIFFE * * * | | | | UPON FURTHER EVALUATION OF DEBRIS TRANSPORTABILITY AND ECCS NPSH ANALYSES, | | LICENSEE ENGINEERING PERSONNEL DETERMINED (ON 01/08/98) THAT THE PLANT | | ECCSs WERE NOT INOPERABLE AS A RESULT OF THE ABOVE CONDITION. THEREFORE, | | THE LICENSEE BELIEVES THAT THIS EVENT DOES NOT MEET THE REPORTING | | REQUIREMENTS OF 10CFR50.72(b)(1)(ii)(B). AS A RESULT, THE LICENSEE IS | | RETRACTING THIS EVENT NOTIFICATION. HOWEVER, THE LICENSEE HAS REPORTED | | THIS EVENT TO THE NRC VIA LICENSEE EVENT REPORT 50-269/97-10. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R2DO (KEN BARR). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33518 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/12/98 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 14:32 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/12/98 | +------------------------------------------------+EVENT TIME: 14:20[EST]| |NRC NOTIFIED BY: PAUL REED |LAST UPDATE DATE: 01/12/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |HAROLD GRAY 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 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - UNANALYZED CONDITION/NO BACKUP TO MAIN TURBINE BACKUP PRESSURE REGULATOR | | | | UNIT 1 IS DEFUELED IN CONDITION 5 AS PART OF A REFUELING OUTAGE. | | | | WHILE REVIEWING GENERAL ELECTRIC SERVICE INFORMATION LETTER #SIL-614, MAIN | | TURBINE BACKUP PRESSURE REGULATOR, DATED 11/05/97, THE LICENSEE DETERMINED | | THAT UNIT 1 DOES NOT HAVE A MAIN TURBINE BACKUP PRESSURE REGULATOR TO THE | | MAIN TURBINE BACKUP MECHANICAL PRESSURE REGULATOR WHICH IS THE BACKUP TO | | THE MAIN TURBINE ELECTRONIC PRESSURE REGULATOR. THE FAILURE OF THE UNIT 1 | | MAIN TURBINE BACKUP MECHANICAL PRESSURE REGULATOR WITHOUT A BACKUP PRESSURE | | REGULATOR IS AN UNANALYZED CONDITION IN THE UNIT 1 ACCIDENT ANALYSIS. | | | | DURING NORMAL PLANT OPERATION, AT LEAST TWO MAIN TURBINE PRESSURE | | REGULATORS ARE REQUIRED TO BE IN SERVICE. THE PURPOSE OF THE BACKUP | | PRESSURE REGULATOR IS TO TAKE OVER REACTOR PRESSURE CONTROL IF THE | | CONTROLLING PRESSURE REGULATOR FAILS DOWNSCALE (MAIN TURBINE CONTROL | | VALVES CLOSING). WHEN THE BACKUP PRESSURE REGULATOR TAKES OVER PRESSURE | | CONTROL, IT IS EXPECTED THAT THE DISTURBANCE WILL BE SMALL ENOUGH THAT A | | REACTOR SCRAM WILL BE AVOIDED. (THIS FEATURE IS DEMONSTRATED DURING | | INITIAL PLANT STARTUP TESTING.) | | | | THE LICENSEE PLANS TO RESOLVE THIS ISSUE PRIOR TO RESTART OF UNIT 1. | | | | THE LICENSEE NOTIFIED STATE AND LOCAL OFFICIALS AND THE NRC RESIDENT | | INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33519 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: BROWNS FERRY REGION: 2 |NOTIFICATION DATE: 01/12/98 | |UNIT: [1] [2] [3] STATE: AL |NOTIFICATION TIME: 15:51 [ET]| |RX TYPE: [1] GE-4,[2] GE-4,[3] GE-4 |EVENT DATE: 01/12/98 | +------------------------------------------------+EVENT TIME: 14:10[CST]| |NRC NOTIFIED BY: MIKE MORROW |LAST UPDATE DATE: 01/12/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |KENNETH BARR RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - STATE NOTIFIED OF THE DISCHARGE OF 1,200 GALLONS OF SEWAGE WASTE WATER - | | | | A MALFUNCTIONING SEWAGE LIFT PUMP CAUSED A BACKUP OF SEWAGE WASTE WATER | | UPSTREAM OF THE LIFT STATION WHICH CAUSED AN OVERFLOW THROUGH MANHOLES AND | | YARD DRAINAGE TO THE PLANT INTAKE FOREBAY. THIS IS AN UPSET OF THE | | NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM PERMIT LIMITS. | | | | THE LICENSEE NOTIFIED THE STATE OF ALABAMA DEPARTMENT OF ENVIRONMENTAL | | MANAGEMENT THAT APPROXIMATELY 1,200 GALLONS OF SEWAGE WASTE WATER WERE | | DISCHARGED TO THE PLANT INTAKE FOREBAY. THE LOCAL RAIN WATER HAS | | DISSIPATED THE SEWAGE WASTE WATER DISCHARGE. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33520 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NTH CONSULTANTS, EXTON, PA |NOTIFICATION DATE: 01/12/98 | | CITY: EXTON REGION: 1 |NOTIFICATION TIME: 16:09 [ET]| | COUNTY: STATE: PA |EVENT DATE: 01/12/98 | |LICENSE#: AGREEMENT: N |EVENT TIME: 13:25[EST]| | DOCKET: |LAST UPDATE DATE: 01/12/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |HAROLD GRAY RDO | | |MIKE BELL/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: CYNTHIA SATTIZAHN, RSO | | |HQ OPS OFFICER: DICK JOLLIFFE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NDAM DAMAGE MEASURE GAUGE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - DAMAGED TROXLER MOISTURE DENSITY GAUGE WITH A Cs-137/Am-241/Be SOURCE - | | | | A TROXLER MOISTURE DENSITY GAUGE WAS RUN OVER AND SEVERELY DAMAGED BY | | A BULLDOZER AT A CONSTRUCTION SITE LOCATED NEAR STATE ROUTE 100 AND SHOEN | | ROAD IN EXTON, PENNSYLVANIA. THE GAUGE SOURCE WAS 39.4 MILLICURIES OF | | Am-241/Be AND 6.4 MILLICURIES OF Cs-137 AS OF 10/15/97. THE RADIATION | | SAFETY OFFICER (RSO) CORDONED OFF THE IMMEDIATE AREA. THERE WERE NO | | PERSONNEL INJURIES OR CONTAMINATIONS. THE RSO HAS BEEN IN CONTACT WITH | | TROXLER AND NRC REGION 1, AND A REGION 1 REPRESENTATIVE IS EN ROUTE TO THE | | CONSTRUCTION SITE. | | | | (REFER TO THE OPERATIONS OFFICER LOG FOR AN RSO CALL BACK TELEPHONE | | NUMBER.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33521 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/13/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 04:25 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/12/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 19:30[CST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/13/98 | | CITY: PADUCAH REGION: 3 +-----------------------------+ | COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION| |LICENSE#: GDP-1 AGREEMENT: Y |JOHN MADERA RDO | | DOCKET: 0707001 |MIKE BELL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: W. G. HALICKS | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STEAM PRESSURE CONTROL SAFETY SYSTEM ACTUATION IN RESPONSE TO VALID SIGNAL | | | | WHILE C-337-A AUTOCLAVE POSITION 2 EAST WAS HEATING A URANIUM HEXAFLUORIDE | | CYLINDER IN PREPARATION FOR FEEDING IT TO THE ENRICHMENT CASCADE, A STEAM | | PRESSURE CONTROLLER MALFUNCTIONED. THIS MALFUNCTION RESULTED IN THE | | INCREASE OF THE STEAM PRESSURE IN THE AUTOCLAVE TO THE ALARM SET POINT, AND | | THIS CAUSED THE ACTUATION OF THE STEAM PRESSURE CONTROL SAFETY SYSTEM. THE | | SAFETY SYSTEM FUNCTIONED AS DESIGNED AND PLACED THE AUTOCLAVE IN A SAFE | | CONFIGURATION BY ISOLATING THE STEAM SUPPLY AND OPENING VENTS. | | | | PADUCAH REPORTED THIS EVENT IN ACCORDANCE WITH PROCEDURE UE2-RA-RE1030, | | REVISION 2, APPENDIX D, CRITERIA J.2, AS THE ACTUATION OF A 'Q' SAFETY | | SYSTEM IN RESPONSE TO A VALID SIGNAL. THIS WAS A 24-HOUR REPORT | | NOTIFICATION. | | | | PADUCAH NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+