U.S. Nuclear Regulatory Commission Operations Center Event Reports For 01/06/98 - 01/07/98 ** EVENT NUMBERS ** 33349 33390 33495 33496 33497 +----------------------------------+ +-----------------------+ |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. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33390 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DIABLO CANYON REGION: 4 |NOTIFICATION DATE: 12/11/97 | |UNIT: [ ] [2] [ ] STATE: CA |NOTIFICATION TIME: 14:34 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 12/11/97 | +------------------------------------------------+EVENT TIME: 11:15[PST]| |NRC NOTIFIED BY: BRUCE LEWIS |LAST UPDATE DATE: 01/06/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN PELLET 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 | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | WESTINGHOUSE IFBA FUEL DESIGN ISSUE FOLLOWUP. | | | | ON DECEMBER 11, 1997, WESTINGHOUSE INFORMED PG&E THAT PLANT SPECIFIC | | ANALYSIS HAD BEEN COMPLETED THAT PREDICTED FUEL ROD PELLET-TO-CLAD GAP | | REOPENING FOR UNIT 2 AT A BURNUP OF 18,000 MWD/METRIC TON. THIS BURNUP | | OCCURRED FOR UNIT 2 ON APPROXIMATELY SEPTEMBER 1, 1997. PG&E HAS COMPLETED | | AND APPROVED A PLANT SPECIFIC OPERABILITY EVALUATION BASED ON THE | | WESTINGHOUSE GENERIC SAFETY ASSESSMENT OF THE EFFECTS OF INCORPORATING | | REVISED MODELS FOR CLAD OXIDATION OF ZIRC-4 FUEL CLADDING AND HELIUM | | RELEASE IN INTEGRAL FUEL BURNABLE ABSORBER (IFBA) FUEL RODS. THE | | OPERABILITY EVALUATION CONCLUDED THAT THE WESTINGHOUSE GENERIC SAFETY | | ASSESSMENT BOUND DIABLO CANYON UNIT 2. | | | | UNIT 1 IS IN THE FIRST OF ITS FUEL CYCLES AND THIS ISSUE WILL NOT BE | | APPLICABLE UNTIL MAY 1998 UNDER THE BOUNDING ANALYSIS PREVIOUSLY PERFORMED | | BY WESTINGHOUSE. | | | | ADDITIONALLY, IN THE INFORMATION-ONLY REPORT MADE ON NOVEMBER 14, 1997 | | (EVENT #33185), PG&E INFORMED THE NRC THAT THE CORRECTED FUEL MODEL | | IDENTIFIED THE POTENTIAL FOR CLADDING OXIDATION TO EXCEED 12% PRE-ACCIDENT | | FUEL OXIDATION SCREENING CRITERIA ON JANUARY 9, 1998 FOR UNIT 2. THE 12% | | OXIDATION LIMIT ASSURES THAT THE SUM OF PRE-ACCIDENT AND POST-LOCA | | OXIDATION WILL NOT EXCEED THE 10CFR50.46 CRITERION OF 17%. WESTINGHOUSE | | HAS DETERMINED THAT THIS DATE HAS BEEN EXTENDED TO CORRESPOND TO A FUEL | | BURNUP OF 23,800 MWD/METRIC TON BY COMPLETING CYCLE SPECIFIC CORROSION | | ANALYSIS. THIS BURNUP WILL BE REACHED ON OR AFTER JANUARY 23, 1998. | | WESTINGHOUSE IS PERFORMING ADDITIONAL ANALYSIS TO DETERMINE THE AMOUNT OF | | TRANSIENT (i.e., LOCA) OXIDATION WHICH IS EXPECTED TO DEMONSTRATE THAT THE | | SUM OF THE PRE-TRANSIENT OXIDATION AND THE TRANSIENT OXIDATION WILL NOT | | EXCEED THE 17% CLAD OXIDATION CRITERIA FOR UNIT 2 CYCLE 8. | | | | THE NRC RESIDENT INSPECTOR WILL BE NOTIFIED BY THE LICENSEE OF THIS EVENT. | | | | * * * UPDATE AT 2031 ON 01/06/98 BY BRUCE LEWIS TAKEN BY WEAVER * * * | | | | ON 12/23/97, WESTINGHOUSE CONFIRMED THAT UNIT 2 CYCLE 8 WILL EXCEED THE | | 12% PRE-TRANSIENT OXIDATION SCREENING CRITERION ON OR AFTER 01/23/98. THE | | ANALYSIS RESULTS INDICATED A MAXIMUM TRANSIENT OXIDATION EQUIVALENT TO 3.3% | | OF THE INITIAL CLADDING THICKNESS. WHEN ADDED TO THE PRE-TRANSIENT | | OXIDATION OF 12.5% FOR THE LEAD ROD PREDICTED AT THE END OF CYCLE, THE | | TOTAL CLADDING OXIDATION OF 15.8% REMAINS BELOW THE 17% LIMIT. THEREFORE, | | COMPLIANCE WITH THE 10CFR50.46 LOCA LIMIT ON TOTAL LOCALIZED OXIDATION WAS | | DEMONSTRATED. | | | | THE DCPP BEST ESTIMATE LOCA ANALYSIS IS CURRENTLY UNDER NRC REVIEW. | | THEREFORE, THE WESTINGHOUSE ASSESSMENT WAS PERFORMED USING TWO SEPARATE | | APPROACHES - APPENDIX K AND BEST ESTIMATE. BOTH METHODS YIELDED ACCEPTABLE | | RESULTS. THE METHODS ARE DESCRIBED IN A WESTINGHOUSE OWNERS GROUP LETTER | | TO THE NRC, "TRANSMITTAL OF RESPONSE TO NRC REQUEST FOR ADDITIONAL | | INFORMATION ON THE FUEL ROD INTERNAL PRESSURE ISSUE," DATED 11/12/97. THE | | WCOBRA/TRAC TRANSIENT USED TO CALCULATE THE MAXIMUM LOCAL OXIDATION AT THE | | BEGINNING OF LIFE FOR THE DCPP BEST ESTIMATE LOCA ANALYSIS WAS SELECTED AS | | THE STARTING POINT FOR THE ASSESSMENT. THIS IS CONSISTENT WITH "BEST | | ESTIMATE APPROACH," PROVIDED IN "TRANSMITTAL OF RESPONSE TO NRC REQUEST FOR | | ADDITIONAL INFORMATION ON THE FUEL ROD INTERNAL PRESSURE ISSUE," DATED | | 11/12/97. THE SAME TRANSIENT ALSO BOUNDS THE DCPP APPENDIX K ANALYSIS, | | PLUS ADDITIONAL PCT ASSESSMENTS, AND IS ALSO APPROPRIATE FOR USE WITH THE | | APPENDIX K APPROACH. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR OF THIS UPDATE. | | | | THE OPERATIONS OFFICER NOTIFIED THE R4DO BLAIR SPITZBERG. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 33495 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 01/06/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 00:23 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 01/05/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 23:20[EST]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 01/06/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N | | | DOCKET: 0707002 | | +------------------------------------------------+JIM CREED, R3 IAT | |NRC NOTIFIED BY: RON CRABTREE | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NCFR NON CFR REPORT REQMNT | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | A CLASSIFIED STORAGE REPOSITORY IN AN OFFICE AREA OF THE X-100 BUILDING WAS | | DISCOVERED UNSECURED BY A ROUTINE SECURITY PATROL. IMMEDIATE COMPENSATORY | | ACTIONS WERE TAKEN UPON DISCOVERY. THE CUSTODIAN OF THE REPOSITORY HAS | | BEEN NOTIFIED AND AN INVENTORY OF CONTENTS IS UNDERWAY. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33496 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 01/06/98 | |UNIT: [1] [ ] [ ] STATE: CT |NOTIFICATION TIME: 09:46 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 01/06/98 | +------------------------------------------------+EVENT TIME: 09:00[EST]| |NRC NOTIFIED BY: DAN MEEKHOFF |LAST UPDATE DATE: 01/06/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAURIE PELUSO 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 | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | OFFSITE NOTIFICATION REGARDING SMALL OIL SPILL INTO STORM DRAIN. | | | | THE LICENSEE NOTIFIED THE STATE OF CONNECTICUT REGARDING A SMALL OIL SPILL | | (LESS THAN 1 QUART) ONTO A PARKING LOT ONSITE. THE LICENSEE DETECTED AN | | OIL SHEEN ON THE PARKING LOT, AND IN A STORM DRAIN. THE STORM DRAIN | | DISCHARGES INTO THE LONG ISLAND SOUND. THE LICENSEE HAS NOT DETECTED ANY | | OIL SHEEN ON THE WATER OF THE SOUND. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 33497 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: LASALLE REGION: 3 |NOTIFICATION DATE: 01/06/98 | |UNIT: [ ] [2] [ ] STATE: IL |NOTIFICATION TIME: 13:26 [ET]| |RX TYPE: [1] GE-5,[2] GE-5 |EVENT DATE: 01/06/98 | +------------------------------------------------+EVENT TIME: 08:52[CST]| |NRC NOTIFIED BY: JOHN HOPMAN |LAST UPDATE DATE: 01/06/98 | |HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN JACOBSON RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 REFUELING | 0 REFUELING | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | ONE REACTOR PROTECTION SYSTEM (RPS) MOTOR GENERATOR (M-G) SET "B" BREAKER | | OPENED AND THE OTHER IN-SERIES RPS BREAKER FAILED TO OPEN. | | | | AT 0852 CST, UNIT 2 EXPERIENCED A DEENERGIZATION OF RPS BUS "B". THE "B" | | RPS M-G SET ELECTRICAL POWER MONITORING ASSEMBLY (EPMA) BREAKER #2C71-S003B | | OPENED AND EPMA BREAKER #2C71-S003D FAILED TO OPEN. BREAKER #2C71-S003D | | FAILING TO OPEN IS AN ABNORMAL RESPONSE. THE EPMAs ARE INSTALLED IN SERIES | | WITH THE "B" RPS M-G SET. | | | | IMMEDIATE CONTROL ROOM RESPONSE WAS TO PERFORM THE ABNORMAL PROCEDURE FOR | | THE LOSS OF RPS BUS "B" AND TO REENERGIZE RPS BUS "B" UTILIZING ITS | | ALTERNATE FEED USING DIFFERENT BREAKERS. | | | | THE FOLLOWING PRIMARY CONTAINMENT ISOLATION VALVES CLOSED AS A RESULT OF | | THE LOSS OF RPS BUS "B": DRYWELL PNEUMATICS 100 PSIG HEADER ISOLATION | | VALVE #2IN017 AND TRAVERSING INCORE PROBE INDEXER PURGE ISOLATION VALVE | | #2IN031. ALSO, POST LOCA CONTAINMENT MONITORING VALVES REPOSITIONED IN | | RESPONSE TO A LOSS OF RPS BUS "B". | | | | THE LICENSEE IS INVESTIGATING THE LOSS OF THE RPS BUS "B" AND WHY EPMA | | BREAKER # 2C71-S003D DID NOT OPEN. | | | | UNIT 1 WAS UNAFFECTED BY THIS EVENT. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+