U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/29/98 - 01/30/98 ** EVENT NUMBERS ** 33174 33623 33624 33625 33626 33627 +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33174 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: CALLAWAY REGION: 4 |NOTIFICATION DATE: 10/29/97 | |UNIT: [1] [ ] [ ] STATE: MO |NOTIFICATION TIME: 11:49 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 10/29/97 | +------------------------------------------------+EVENT TIME: 10:49[CST]| |NRC NOTIFIED BY: DAVE BONO |LAST UPDATE DATE: 01/29/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE YANDELL RDO | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 70 POWER OPERATION | 70 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FUEL DESIGN CRITERIA MAY NOT BE MET FOR WESTINGHOUSE TWICE BURNED IFBA | | FUEL. | | | | "THIS REPORT IS PROVIDED FOR INFORMATION. CALLAWAY WAS INFORMED BY | | WESTINGHOUSE THAT THE METHODOLOGY FOR DETERMINATION OF FUEL ROD INTERNAL | | PRESSURE AND CLADDING CORROSION WAS FOUND TO BE POTENTIALLY LESS | | CONSERVATIVE THAN PREVIOUSLY BELIEVED. AS A RESULT, CALCULATION OF | | 10CFR50.46 ECCS ACCEPTANCE CRITERIA MAY BE AFFECTED. THIS DETERMINATION IS | | BASED ON NEWER MODELS STILL UNDER DEVELOPMENT, WHICH ARE BELIEVED TO MORE | | ACCURATELY PREDICT FUEL-CLADDING BEHAVIOR. THE EFFECT OF THIS EVALUATION | | INDICATES THAT POTENTIALLY, FOR A POSTULATED LOCA, THE 17% CLAD OXIDATION | | LIMIT REQUIREMENT OF 10CFR50.46 MAY NOT BE MET. THE ANALYSIS PROVIDED BY | | WESTINGHOUSE IS GENERIC IN NATURE AND HAS NOT BEEN SPECIFICALLY APPLIED TO | | CALLAWAY. HOWEVER, THE GENERIC EVALUATION PROVIDED BY WESTINGHOUSE | | DETERMINED THAT THIS DOES NOT REPRESENT A CONDITION THAT SIGNIFICANTLY | | COMPROMISES PLANT SAFETY AND THAT IT DOES NOT REPRESENT A SUBSTANTIAL | | SAFETY CONCERN. THE BASIS FOR THIS JUDGMENT IS THAT IF THE POSTULATED | | EVENT OCCURRED; (a) A PLANT COULD BE SHUTDOWN SAFELY, AS THE CONTROL | | MECHANISMS WOULD FUNCTION PROPERLY, (b) A COOLABLE GEOMETRY IN THE SENSE | | REQUIRED FOR LOCA PROTECTION WOULD BE MAINTAINED, AND (c) 10CFR100 DOSE | | LIMITS WOULD NOT BE EXCEEDED IN ANY POSTULATED EVENT." | | | | "WESTINGHOUSE HAS NOTIFIED THE NRC AND THEIR CUSTOMERS OF THIS ISSUE THOUGH | | THEY HAVE CONCLUDED THAT EXCEEDING THE AFOREMENTIONED CRITERIA DOES NOT | | POSE A SUBSTANTIAL SAFETY HAZARD AND IS NOT REPORTABLE PER 10CFR21 | | REQUIREMENTS. ADDITIONALLY, THEY HAVE PROVIDED A PLAN FOR INCORPORATION OF | | THE NEW ZIRCALOY CORROSION MODEL INTO THEIR PAD CODE. CALLAWAY WILL | | MONITOR PROGRESS ON THIS PLAN FOR FURTHER DEVELOPMENTS." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE BY DAVID BONO TO FANGIE JONES AT 1205 ON 01/29/98 * * * | | | | THIS REPORT UPDATES PREVIOUS INFORMATION REPORT REGARDING FUEL DESIGN | | CRITERIA FOR WESTINGHOUSE TWICE BURNED IFBA FUEL. | | | | PLANT SPECIFIC ANALYSIS PERFORMED BY WESTINGHOUSE HAS DETERMINED THAT THEIR | | "NO GAP REOPENING CRITERION" MAY BE EXCEEDED FOR FUEL BURNUP IN EXCESS OF | | 15052 MWD/MTU. HOWEVER, THE ANALYSIS CONCLUDED THAT THE DESIGN BASIS FROM | | 10CFR50.46(b)(2) ACCEPTANCE CRITERIA REGARDING MAXIMUM CLADDING OXIDATION | | WOULD NOT BE EXCEEDED AS LONG AS CALLAWAY OPERATES WITHIN PRESCRIBED POWER | | LIMITS. THE ANALYSIS ALSO CONCLUDED THAT THE RELOAD SAFETY EVALUATION FOR | | THE CURRENT CYCLE REMAINS VALID. CALLAWAY HAS IMPLEMENTED APPROPRIATE | | ADMINISTRATIVE CONTROLS TO ENSURE OPERATION WITHIN THE POWER LIMITS | | PRESCRIBED AND WILL CONTINUE TO MONITOR EFFORTS TO RESOLVE THIS ISSUE. THIS | | PROBLEM WILL NO LONGER APPLY WITH THE NEXT REFUELING OUTAGE WHICH IS | | PRESENTLY SCHEDULED FOR APRIL 1998. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE HEADQUARTERS | | OPERATIONS OFFICER INFORMED THE R4DO (PHIL HARRELL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33623 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NORTH ANNA REGION: 2 |NOTIFICATION DATE: 01/29/98 | |UNIT: [1] [2] [ ] STATE: VA |NOTIFICATION TIME: 02:19 [ET]| |RX TYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 01/29/98 | +------------------------------------------------+EVENT TIME: 01:08[EST]| |NRC NOTIFIED BY: CROSSMAN |LAST UPDATE DATE: 01/29/98 | |HQ OPS OFFICER: CHAUNCEY GOULD +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SPDS COMPUTER SYSTEM FAILURE | | | | THE PLANT LOST ITS SPDS COMPUTER, AND IT COULD NOT BE RECOVERED WITHIN 1 | | HOUR. THE CAUSE OF FAILURE IS UNKNOWN AT THIS TIME, BUT MAINTENANCE | | PERSONNEL ARE STILL WORKING ON IT. | | | | THE NRC RESIDENT INSPECTOR WILL BE INFORMED. | | | | ***UPDATE AT 0513 ON 01/29/98 FROM CROSSMAN TO GOULD*** | | | | THE SPDS WAS RESTORED TO MINIMUM OPERATION AT 0500. THEY HAD PROBLEMS WITH | | SOME OF THE CRT DISPLAYS WHICH HAD TO BE DISCONNECTED TO RETURN SPDS TO | | MINIMUM OPERABILITY. THEY ARE CONTINUING WORK ON THE FAILED MONITORS. | | | | THE NRC RESIDENT INSPECTOR WAS NOTIFIED BY THE LICENSEE. THE R2DO | | (CHRISTENSEN) WAS NOTIFIED BY THE NRC OPERATIONS CENTER. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33624 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 01/29/98 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 10:05 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 01/28/98 | | LEU FABRICATION |EVENT TIME: 12:00[EST]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 01/29/98 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |CHRIS CHRISTENSEN RDO | | DOCKET: 07001113 |DON COOL/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: PAULSON | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR 91-01 BULLETIN RESPONSE | | | | THE LICENSEE HAS DETERMINED THAT AN ADMINISTRATIVE CONTROL ASSOCIATED WITH | | ADDITION OF A MATERIAL ADDITIVE TO A PRODUCTION UO-2 BLEND HAD BEEN | | DEGRADED. THE SITUATION OCCURRED IN THE DRY CONVERSION PROCESS (DCP) | | FACILITY. | | | | THE SITUATION WAS DISCOVERED DURING THE EVALUATION OF ROUTINE QUALITY | | SAMPLE RESULTS FOLLOWING COMPLETION OF A BLEND. NO UNSAFE CONDITION | | EXISTED. THE RESULTING TOTAL EQUIVALENT WATER MODERATION IN THE BLENDED | | MATERIAL (1.1 wt%) WAS LESS THAN THE ESTABLISHED LIMIT (1.9 wt%). OTHER | | BLENDS PERFORMED JUST BEFORE AND AFTER THE HIGH BLEND WERE FOUND TO HAVE NO | | OUT OF LIMIT CARBON RESULTS. | | | | CONTROLS WERE RE-ESTABLISHED WITHIN 4 HOURS. THIS IS REPORTED PURSUANT TO | | BULLETIN 91-01 DUE TO DEGRADATION OF ONE ASPECT OF CONTROL(S) ON | | MODERATION. DCP BLENDING ACTIVITIES HAVE BEEN SHUTDOWN PENDING | | INVESTIGATION AND IMPLEMENTATION OF CORRECTIVE MEASURES. | | | | THERE IS LOW SAFETY SIGNIFICANCE SINCE THE BLEND EQUIVALENT MOISTURE | | CONTENT (1.1%) IS BELOW THE 1.9% LIMIT. | | | | THERE WOULD HAVE TO BE MULTIPLE FAILURE MODES BEFORE A CRITICALITY ACCIDENT | | COULD OCCUR. | | | | MODERATION IS THE CONTROLLED PARAMETER. | | | | THERE WAS 712.5 kgs UO2 AT 4.90% U-235 ENRICHMENT WITH A MAXIMUM TOTAL | | ADDITIVE CONTENT OF 0.852% (LIMIT = 1.3%). THE FREE MOISTURE CONTENT OF | | THE BLEND WAS 0.26% (LIMIT = 0.60%). MAX ALLOWABLE TOTAL EQUIVALENT WATER | | MODERATION FOR 1,000 kg UO2 SPHERE LIMITED TO 1.9% wt% AT 5% U-235 | | ENRICHMENT. | | | | ADMINISTRATIVE CONTROL ON SEGREGATION OF ADDITIVES MATERIAL TYPE FAILED. | | FBS COMPUTER CONTROLS LIMIT TOTAL 'ADDITIVE' PER BLEND TO 1.3 wt% | | EQUIVALENT WATER MODERATION REMAINED INTACT. | | | | CORRECTIVE ACTIONS - IMMEDIATE SHUTDOWN OF BLENDING OPERATIONS, RESEGREGATE | | ADDITIVES IN DCP PROCESS STORAGE AREA AND INVESTIGATION OF CORRECTIVE | | ACTIONS ARE PENDING. | | | | THE RESIDENT INSPECTOR AND THE LOCAL AND STATE AGENCIES WILL BE NOTIFIED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33625 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: HARRIS REGION: 2 |NOTIFICATION DATE: 01/29/98 | |UNIT: [1] [ ] [ ] STATE: NC |NOTIFICATION TIME: 17:48 [ET]| |RX TYPE: [1] W-3-LP |EVENT DATE: 01/29/98 | +------------------------------------------------+EVENT TIME: 16:57[EST]| |NRC NOTIFIED BY: MARK PALMER |LAST UPDATE DATE: 01/29/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CHRIS CHRISTENSEN 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | SECURITY EVENT | | | | THE LICENSEE DISCOVERED THAT A CONTRACT WORKER RECEIVED UNESCORTED ACCESS | | BY OMITTING PERTINENT CRIMINAL HISTORY INFORMATION. THIS WAS DISCOVERED BY | | A ROUTINE CORPORATE REVIEW OF FEDERAL BUREAU OF INVESTIGATION PROVIDED | | BACKGROUND CHECKS. THE INDIVIDUAL WORKED ON SITE FROM 04/27/97 TO | | 05/20/97, AND THE ACCESS TERMINATED AT THAT TIME. ACCESS WILL BE DENIED IN | | THE FUTURE, AND AN INVESTIGATION IS ONGOING TO DETERMINE THE EXTENT OF THE | | INDIVIDUALS ACTUAL AREA OF WORK AND AREAS ACCESSED. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33626 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: NINE MILE POINT REGION: 1 |NOTIFICATION DATE: 01/29/98 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 17:55 [ET]| |RX TYPE: [1] GE-2,[2] GE-5 |EVENT DATE: 01/29/98 | +------------------------------------------------+EVENT TIME: 16:51[EST]| |NRC NOTIFIED BY: JIM KRONENBITTER |LAST UPDATE DATE: 01/29/98 | |HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |DAVID SILK 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL LOSS OF SERVICE WATER DURING MAINTENANCE COULD RESULT IN LOSS OF | | ACCIDENT MITIGATION. | | | | THE LICENSEE DISCOVERED, DURING PREPARATION FOR ROUTINE MAINTENANCE ON THE | | REACTOR BUILDING SERVICE WATER DRAG VALVE, THAT PREVIOUS MAINTENANCE COULD | | HAVE PREVENTED THE SECONDARY CONTAINMENT FROM MITIGATING THE CONSEQUENCES | | OF AN ACCIDENT. ON 12/11/97, WITH THE VALVE BONNET REMOVED, A PATHWAY | | COULD HAVE EXISTED THAT COULD PREVENT SECONDARY CONTAINMENT INTEGRITY FROM | | BEING ENSURED IN AN ACCIDENT SITUATION. IF SERVICE WATER WAS LOST DURING | | MAINTENANCE, A PATHWAY TO ATMOSPHERE COULD EXIST FROM INSIDE CONTAINMENT | | DIRECTLY TO ATMOSPHERE, BEYOND THE CAPACITY OF THE STANDBY GAS SYSTEM, | | BYPASSING SECONDARY CONTAINMENT INTEGRITY. ROUTINE MAINTENANCE IS ON HOLD | | WHILE THE CONSEQUENCES ARE BEING INVESTIGATED BY PLANT ENGINEERING AND | | MAINTENANCE PERSONNEL. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33627 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/29/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:25 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/29/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 16:30[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/29/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |BRUCE JORGENSEN RDO | | DOCKET: 0707002 |MARGARET FEDERLINE EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: KURT SISLER | | |HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 4-HOUR NRC BULLETIN 91-01 EVENT | | | | THE LICENSEE DISCOVERED THAT NO NUCLEAR CRITICALITY SAFETY APPROVAL (NCSA) | | EXISTED FOR VARIOUS OPERATION/CONTROLS IN THE X-236 PROCESS BUILDING. THESE | | INCLUDE THE FOLLOWING: 1. TOP/SIDE BOOSTERS, 2. ORIFICE STATION, 3. TRAPS, | | 4. JETS, 5. SPACE RECORDERS, 6. LINE RECORDERS, AND 7. MgFl AND SELECTIVE | | ABSORPTION TRAPS. THE UNANALYZED OPERATIONS ARE REPORTABLE PER NRC | | BULLETIN 91-01, NO NCSA IN PLACE. | | | | EACH OF THE ABOVE OPERATION/CONTROLS WERE EXAMINED FOR SAFETY SIGNIFICANCE, | | POTENTIAL CRITICALITY PATHWAYS, AND NCSA PARAMETERS. CORRECTIVE ACTIONS | | HAVE BEEN TAKEN TO VERIFY/RESTORE IDENTIFIED PROBLEMS TO ENSURE THAT ALL | | NCSA CONCERNS ARE PROPERLY IMPLEMENTED. | | | | THERE WAS NO LOSS OF HAZARDOUS OR RADIOACTIVE MATERIAL OR | | CONTAMINATION/EXPOSURE AS A RESULT OF THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR AND THE ONSITE DOE | | REPRESENTATIVE. | +------------------------------------------------------------------------------+