U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/07/98 - 01/08/98 ** EVENT NUMBERS ** 33349 33364 33430 33498 33499 33500 33501 33502 33503 33504 33505 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33349 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 12/04/97 | |UNIT: [ ] [2] [ ] STATE: NC |NOTIFICATION TIME: 18:48 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/04/97 | +------------------------------------------------+EVENT TIME: 18:40[EST]| |NRC NOTIFIED BY: KATHLEEN BRESLIN |LAST UPDATE DATE: 01/07/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |CHARLES CASTO IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY REPORT | | | | DISCOVERY OF POTENTIAL EQUIPMENT TAMPERING. REFER TO THE HOO LOG FOR | | ADDITIONAL DETAILS. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33364 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 12/08/97 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 14:14 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 12/08/97 | +------------------------------------------------+EVENT TIME: 10:53[EST]| |NRC NOTIFIED BY: CONWAY |LAST UPDATE DATE: 01/07/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JIM TRAPP 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 95 POWER OPERATION | 95 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL PRIMARY CONTAINMENT PRESSURE SUPPRESSION FUNCTION BYPASS PATHWAY. | | | | "A GENERAL ELECTRIC PART 21.21(b) NOTIFICATION (SC07-04) WAS MADE FOR | | POTENTIAL PRIMARY CONTAINMENT PRESSURE SUPPRESSION FUNCTION BYPASS | | PATHWAYS. A POSTULATED SINGLE FAILURE OF A CABLE RACEWAY/WIREWAY WHICH | | CONTAINS THE ISOLATION VALVE CONTROL WIRING FOR THE INBOARD CONTAINMENT | | PURGE SYSTEM VALVES COULD LEAD TO EXCESSIVE PRIMARY CONTAINMENT PRESSURE | | POST ACCIDENT. IN-DEPTH CALCULATIONS AND ANALYSIS STILL NEED TO BE | | PERFORMED TO DETERMINE THE MAXIMUM PRESSURE RISE. ADDITIONAL QUESTIONS | | WERE RAISED CONCERNING WHETHER THE CREATION OF BYPASS PATHWAYS ALSO OCCUR | | DURING NORMAL OPERATION OR SURVEILLANCE TESTING. | | | | A REVIEW OF NINE MILE POINT UNIT 2 PROCEDURES FOUND THAT DURING PRIMARY | | CONTAINMENT PURGE FOLLOWING FORCED AND PLANNED UNIT OUTAGES, A BYPASS | | PATHWAY IS CREATED DURING THE HIGH-FLOW INERTING PROCEDURE WHEN BOTH THE | | SUPPRESSION CHAMBER AND THE DRYWELL AIR SPACES ARE PURGED IN ORDER TO | | REDUCE CONTAINMENT OXYGEN LEVELS. THE SAME BYPASS PATHWAY LINEUP IS | | UTILIZED FOR THE DEINERTING PROCESS WHICH PRECEEDS OUTAGES WHICH REQUIRE | | PRIMARY CONTAINMENT ACCESS. THE LAST TIME A BYPASS FLOWPATH EXISTED WAS ON | | 11/12/97, FOLLOWING PLANT STARTUP FROM FORCED OUTAGE 97-03. | | | | ALL CONTAINMENT PURGE VALVES ARE CLOSED. ADMINISTRATIVE CONTROLS WILL BE | | IMPLEMENTED TO PRECLUDE CREATION OF A BYPASS FLOWPATH UNTIL PROCEDURE | | CHANGES CAN BE COMPLETED." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1723 ON 01/07/98 BY PITTS TAKEN BY WEAVER * * * | | | | THE LICENSEE HAS RETRACTED THIS EVENT. CALCULATIONS AND EVALUATIONS HAVE | | BEEN PERFORMED BY ENGINEERING WHICH HAVE DETERMINED THAT THE POSTULATED | | FAILURE WOULD NOT CAUSE PRIMARY CONTAINMENT PRESSURE TO EXCEED MAXIMUM | | DESIGN PRESSURE. IN ADDITION, QUESTIONS WITH REGARD TO CREATION OF BYPASS | | PATHWAYS DURING NORMAL OPERATION WERE BOUNDED BY THE CALCULATIONS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED THE R1DO (LAURIE PELUSO). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33430 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: QUAD CITIES REGION: 3 |NOTIFICATION DATE: 12/19/97 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 00:25 [ET]| |RX TYPE: [1] GE-3,[2] GE-3 |EVENT DATE: 12/18/97 | +------------------------------------------------+EVENT TIME: 21:25[CST]| |NRC NOTIFIED BY: LECHMAIER |LAST UPDATE DATE: 01/07/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |PATRICK HILAND 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 99 POWER OPERATION | 99 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BOTH UNIT 1 AND UNIT 1/2 EMERGENCY DIESEL GENERATORS DECLARED INOPERABLE. | | | | WHILE PERFORMING PREVENTATIVE MAINTENANCE ON THE UNIT 1 EMERGENCY DIESEL | | GENERATOR (EDG), THE TIME DELAY RELAY FOR START FAILURE WAS FOUND TO BE OUT | | OF TOLERANCE. THIS WAS DISCOVERED AT 1400 CST ON 12/18/97 AND THE UNIT 1 | | EDG WAS DECLARED INOPERABLE AT THAT TIME. THE UNIT 1/2 EDG WAS THEN TESTED | | TO DETERMINE IF ITS TIME DELAY RELAY WAS WITHIN APPROPRIATE SPECIFICATIONS. | | THE TEST WAS COMPLETED AND THE RELAY WAS ALSO DETERMINED TO BE OUT OF | | TOLERANCE AT 2125 CST ON 12/18/97. THIS MEANS THAT BOTH THE UNIT 1 AND | | UNIT 1/2 EDGs WERE INOPERABLE AT THE SAME TIME. RELAY REPLACEMENT AND | | TESTING WAS IN PROGRESS AT THE TIME. THE CAUSE OF THE RELAY PROBLEM IS | | BEING INVESTIGATED. UNIT 1 IS IN AN LCO ACTION STATEMENT WHICH GIVES | | THEM TWO HOURS TO CORRECT THE PROBLEM OR BE IN HOT SHUTDOWN CONDITION | | IN 12 HOURS. | | | | THE NRC RESIDENT INSPECTOR WAS INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1943 ON 01/07/98 BY OSELAND TAKEN BY WEAVER * * * | | | | THE LICENSEE LATER DISCOVERED THAT THE UNIT 2 EDG WAS INOPERABLE FROM | | 12/10/97 TO 12/24/97. THE CAUSE OF THIS INOPERABILITY WAS A MISPOSITIONED | | THROTTLE VALVE IN THE COOLING WATER SUPPLY LINE. THIS WAS DISCOVERED | | DURING A SURVEILLANCE CONDUCTED ON 12/23/97. THIS MEANS THAT ALL THREE | | EDGs WERE INOPERABLE FOR ABOUT FIVE HOURS ON 12/18/97. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | | | | THE HOO NOTIFIED THE R3DO (JOHN JACOBSON). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33498 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 01/07/98 | |UNIT: [ ] [2] [ ] STATE: NY |NOTIFICATION TIME: 06:20 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 01/07/98 | +------------------------------------------------+EVENT TIME: 05:35[EST]| |NRC NOTIFIED BY: BRIAN WEAVER |LAST UPDATE DATE: 01/07/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 95 POWER OPERATION | 93 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | -UNIT 2 TS REQD S/D DUE TO BOTH CONTAINMENT MONITORING SYS DIVISIONS INOP- | | | | AT 0441 ON 01/07/98, THE LICENSEE DECLARED BOTH UNIT 2 DIVISION 2 PRIMARY | | CONTAINMENT AIRBORNE PARTICULATE AND GASEOUS RADIOACTIVITY MONITORING | | CHANNELS (#2CMS*CAB10B) INOPERABLE DUE TO ERRATIC FLOW INDICATION FOR | | UNKNOWN REASONS. | | | | BOTH UNIT 2 DIVISION 1 PRIMARY CONTAINMENT AIRBORNE PARTICULATE AND GASEOUS | | RADIOACTIVITY MONITORING CHANNELS (#2CMS*CAB10A) HAD PREVIOUSLY BEEN | | DECLARED INOPERABLE FOR PLANNED MAINTENANCE ACTIVITIES. TECH SPEC LCO | | ACTION STATEMENT 3.4.3.1, ACTION A, IS APPLICABLE WITH ONE CONTAINMENT | | MONITORING SYSTEM DIVISION INOPERABLE. | | | | WITH BOTH CONTAINMENT MONITORING SYSTEM DIVISIONS INOPERABLE, THE LICENSEE | | ENTERED TECH SPEC LCO ACTION STATEMENT 3.0.3 AND COMMENCED TO SHUT UNIT 2 | | DOWN AT 0535. NO CONTAINMENT PARAMETERS HAVE CHANGED AND NO COOLANT | | LEAKAGE INSIDE CONTAINMENT BEYOND NORMAL VALUES IS APPARENT. | | | | THE LICENSEE IS INVESTIGATING THE CAUSE OF THIS EVENT AND EXPECTS TO | | RESTORE ONE DIVISION CONTAINMENT MONITORING SYSTEM CONTAINMENT | | RADIOACTIVITY MONITORING CHANNEL TO OPERABLE STATUS PRIOR TO REACHING | | CONDITION 3. | | | | THIS EVENT HAS NO EFFECT ON UNIT 1. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 33499 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: FLORIDA BUREAU OF RADIATION CONTROL |NOTIFICATION DATE: 01/07/98 | | CITY: LARGO REGION: 2 |NOTIFICATION TIME: 09:48 [ET]| | COUNTY: PINELLAS STATE: FL |EVENT DATE: 01/07/98 | |LICENSE#: 22-12 (FL) AGREEMENT: Y |EVENT TIME: 00:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |KENNETH BARR RDO | | |DON COOL, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: CHARLES ADAMS | | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STOLEN TROXLER SOIL DENSITY GAUGE. | | | | A TROXLER SOIL DENSITY GAUGE (MODEL #3430, SERIAL #26271) OWNED BY: | | | | PROFESSIONAL SERVICE INDUSTRIES, INC. | | 5801 BENJAMIN CENTER DRIVE, SUITE 112 | | TAMPA, FL 33634 | | | | WAS STOLEN FROM A LOCKED PICKUP TRUCK PARKED OVERNIGHT AT THE EMPLOYEES | | RESIDENCE IN LARGO, FLORIDA. THE GAUGE CONTAINED AN 8 mCi Cs-137 AND 40 | | mCi Am-Be 241 SOURCE. THE LARGO POLICE DEPARTMENT WAS CONTACTED AND IS | | INVESTIGATING THE THEFT. IT IS NOT KNOWN WHETHER A PRESS RELEASE WILL BE | | ISSUED AT THIS TIME. SEE HOO LOG FOR CONTACT INFORMATION. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |OTHER NUCLEAR MATERIAL | |EVENT NUMBER: 33500 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: DUBOSE NATIONAL ENERGY SERVICES,INC |NOTIFICATION DATE: 01/07/98 | | CITY: CLINTON REGION: 2 |NOTIFICATION TIME: 10:00 [ET]| | COUNTY: STATE: NC |EVENT DATE: 01/07/98 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 10:00[EST]| | DOCKET: |LAST UPDATE DATE: 01/07/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |LAURIE PELUSO, R1 RDO | | | | +------------------------------------------------+KEN BARR R2DO | |NRC NOTIFIED BY: JAMES N. DAILEY |BLAIR SPITZBERG R4DO | |HQ OPS OFFICER: JOHN MacKINNON |VERN HODGE NRR | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |CDEG 21.21(c)(3)(i) DEFECTS/NONCOMPLIANCE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10CFR PART 21 REPORT - | | | | DUBOSE NATIONAL ENERGY SERVICES, INC, (DNES) SHIPPED A TOTAL OF 40 PIECES | | OF 4 INCH, 90 DEGREE ELBOWS WHICH DID NOT MEET ASME SEC II SA-234 | | REQUIREMENTS TO SEVERAL NUCLEAR POWER PLANTS. | | | | TUBE FORGINGS OF AMERICA (TFA), A VENDOR OF DNES, NOTIFIED DNES THAT | | MATERIAL SUPPLIED TO TFA BY US STEEL/KOBE STEEL WAS MIXED AT THE MILL. FROM | | ONE TO FIVE LENGTHS OF PIPE, OUT OF A SHIPMENT OF 1,614 LENGTHS, | | WERE MADE OF A DIFFERENT HEAT/GRADE MATERIAL. THIS SHIPMENT WAS USED TO | | MANUFACTURE A TOTAL OF 40 PIECES OF 4 INCH, 90 DEGREE ELBOWS WHICH WERE | | SHIPPED TO THE FOLLOWING NUCLEAR POWER PLANTS: | | | | CUSTOMER ORDER NUMBER QUANTITY | | | | WASHINGTON PUBLIC POWER 251756 20 PIECES | | NE NUCLEAR 02017957 16 PIECES | | TU ELECTRIC S02208826D2 3 PIECES | | SC ELECTRIC & GAS SR 700786 1 PIECE | | | | THE ABOVE CUSTOMERS WERE NOTIFIED OF THE PROBLEM. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33501 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 01/07/98 | |UNIT: [ ] [2] [3] STATE: IL |NOTIFICATION TIME: 13:28 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 01/07/98 | +------------------------------------------------+EVENT TIME: 12:15[CST]| |NRC NOTIFIED BY: CHRIS KENT |LAST UPDATE DATE: 01/07/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | REACTOR BLDG POST-LOCA TEMPS COULD EXCEED UFSAR ALLOWED VALUE OF 104øF. | | | | AS PART OF THE EFFORT TO RECONSTITUTE THE DRESDEN DESIGN BASIS, A | | CALCULATION WAS PREPARED TO DETERMINE THE POST-LOCA TEMPERATURES IN THE | | REACTOR BUILDING. THIS CALCULATION CONSERVATIVELY CONCLUDED THAT REACTOR | | BUILDING TEMPERATURES WILL BE SIGNIFICANTLY HIGHER THAN THE LIMITING VALUE | | STATED IN THE UFSAR (104øF). THE CALCULATED TEMPERATURES COULD HAVE | | ADVERSELY AFFECTED THE ABILITY OF CLASS 1E ELECTRICAL COMPONENTS IN THE | | REACTOR BUILDING TO PERFORM THEIR FUNCTION TO MITIGATE THE CONSEQUENCES OF | | AN ACCIDENT IF THEY ARE REQUIRED TO START AT SOME POINT DURING THE 30 DAYS | | IMMEDIATELY FOLLOWING THE LOCA. | | | | AN OPERABILITY EVALUATION HAS BEEN COMPLETED AND CONCLUDED THAT BASED ON | | LIMITED COMPENSATORY ACTIONS, THE EQUIPMENT NEEDED TO PERFORM SAFETY | | FUNCTIONS DURING AND AFTER A LOCA ARE CAPABLE OF PERFORMING AT TEMPERATURES | | ABOVE 104øF. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33502 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: VERMONT YANKEE REGION: 1 |NOTIFICATION DATE: 01/07/98 | |UNIT: [1] [ ] [ ] STATE: VT |NOTIFICATION TIME: 15:10 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 01/07/98 | +------------------------------------------------+EVENT TIME: 14:45[EST]| |NRC NOTIFIED BY: MICHAEL EMPEY |LAST UPDATE DATE: 01/07/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | PEAK TORUS TEMP POST-LOCA COULD EXCEED CONTAINMENT DESIGN TEMPERATURE. | | | | AS A RESULT OF THE ON-GOING LICENSEE CONTAINMENT ANALYSIS EFFORTS, IT WAS | | LEARNED THAT THE TORUS TEMPERATURE ANALYSIS OF RECORD DID NOT CONSIDER | | SEVERAL POTENTIAL SOURCES OF ENERGY AND MAY NOT HAVE DETERMINED THE | | LIMITING DBA LOCA SCENARIO. ALSO, THE COMPUTER CODE, FROSSTEY-2, WHICH | | WAS USED TO DETERMINE INPUT INTO THE ANALYSIS, CONTAINED AN ERROR WHICH | | RESULTED IN AN UNDER-ESTIMATION OF THE FUEL STORED ENERGY. THESE | | CONSIDERATIONS AND ERRORS HAVE THE POTENTIAL TO INCREASE THE PEAK POST-LOCA | | SUPPRESSION POOL TEMPERATURE ABOVE THE CURRENT ANALYZED PEAK OF 176øF. | | | | BESIDES THE FUEL STORED ENERGY, THE TWO HEAT SOURCES NOT ADDRESSED OR UNDER | | ESTIMATED ARE THE FEEDWATER ENERGY AND THE MECHANICAL ENERGY FROM THE ECCS | | PUMPS. | | | | THE LICENSEE HAS IMPLEMENTED THE FOLLOWING COMPENSATORY ACTIONS TO MAINTAIN | | TORUS TEMPERATURE WITHIN THE DESIGN LIMITS: TORUS TEMPERATURE WILL BE | | MAINTAINED LESS THAN 80øF (NORMALLY ALLOWED TO GO UP TO 90øF) AND | | OPERATIONS WILL CONTINUE ONLY IF RIVER WATER TEMPERATURE IS LESS THAN 50øF | | (ANALYZED UP TO 85øF). | | | | THE LICENSEE HAS INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33503 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/07/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 15:55 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/07/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 08:00[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/07/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |JOHN JACOBSON RDO | | DOCKET: 0707002 |LARRY CAMPER, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: LARSON | | |HQ OPS OFFICER: DOUG WEAVER | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | |NLTR LICENSEE 24 HR REPORT | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | BULLETIN 91-01, 24 HOUR REPORT. | | | | AT 0800 ON 01/07/98, IT WAS DISCOVERED THAT A NUCLEAR CRITICALITY SAFETY | | APPROVAL (NCSA) REQUIREMENT WAS NOT BEING MET. IN THE DOUBLE CONTINGENCY | | CONTROL MATRIX OF NCSA_PLANT 045.A01, CONTROL "A" REQUIREMENT #5 WAS NOT | | MAINTAINED. A SMALL VACUUM PUMP WAS NOT PROPERLY STORED TWO FEET AWAY | | EDGE-TO-EDGE FROM OTHER URANIUM BEARING EQUIPMENT OR CONTAINERS. UPON | | DISCOVERY, THE PUMP WAS CORRECTLY SPACED. CONTROL B REQUIREMENTS WERE | | MAINTAINED THROUGHOUT THE EVENT. THIS LOSS OF SPACING VIOLATED ONE CONTROL | | OF THE DOUBLE CONTINGENCY CONTROL REQUIREMENTS. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33504 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CLINTON REGION: 3 |NOTIFICATION DATE: 01/07/98 | |UNIT: [1] [ ] [ ] STATE: IL |NOTIFICATION TIME: 23:54 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 01/07/98 | +------------------------------------------------+EVENT TIME: 22:25[CST]| |NRC NOTIFIED BY: MIKE HUDSON |LAST UPDATE DATE: 01/07/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AARC 50.72(b)(1)(v) OTHER ASMT/COMM INOP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | - SAFETY PARAMETER DISPLAY SYSTEM INOPERABLE FOR LONGER THAN 8 HOURS - | | | | AT 1601 CST, THE LICENSEE DECLARED THE PLANT SAFETY PARAMETER DISPLAY | | (SPD) SYSTEM INOPERABLE FOLLOWING THE LOSS OF A PLANT COMPUTER SYSTEM | | INPUT/OUTPUT CABINET THAT RESULTED IN THE LOSS OF COMPUTER POINTS UTILIZED | | IN THE SPD SYSTEM FOR DETERMINING EMERGENCY OPERATING PROCEDURE ENTRY | | CONDITIONS FOR RADIOACTIVE RELEASE RATES. | | | | THE LICENSEE IS REPAIRING THE SPD SYSTEM. | | | | AT 2225 CST, THE LICENSEE DETERMINED THAT IT WOULD TAKE LONGER THAN EIGHT | | HOURS TO RESTORE THE SPD SYSTEM TO OPERABLE STATUS. | | | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33505 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 01/08/98 | |UNIT: [1] [ ] [ ] STATE: MI |NOTIFICATION TIME: 02:35 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 01/07/98 | +------------------------------------------------+EVENT TIME: 21:28[EST]| |NRC NOTIFIED BY: BRIAN MUTZ |LAST UPDATE DATE: 01/08/98 | |HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | - REACTOR TRIP SIGNAL DUE TO A MISSED TEST PROCEDURE STEP DURING A TEST - | | | | UNIT 1 IS IN MODE 5 (COLD SHUTDOWN) IN A MAINTENANCE OUTAGE WITH ALL | | CONTROL RODS COMPLETELY INSERTED, THE REACTOR TRIP BREAKERS (RTBs) OPEN, | | THE MAIN STEAM ISOLATION VALVES (MSIVs) CLOSED, AND THE RESIDUAL HEAT | | REMOVAL SYSTEM IN SERVICE. | | | | AT 2128 ON 01/07/98, DURING TESTING OF THE SOLID STATE PROTECTION (SSP) | | SYSTEM, THE TRAIN 'A' RTB UNDERVOLTAGE TRIP ANNUNCIATOR ACTUATED AND THE | | TRAIN 'A' MSIV DUMP VALVES OPENED DUE TO A REACTOR TRIP SIGNAL. | | | | THE LICENSEE DETERMINED THAT TECHNICIANS MISSED A TEST PROCEDURE STEP TO | | RESET THE SSP SYSTEM MEMORY WHICH RESULTED IN THE REACTOR TRIP SIGNAL WHEN | | THE SSP SYSTEM WAS REMOVED FROM THE "INHIBIT" TEST POSITION. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+