U.S. Nuclear Regulatory Commission Operations Center Event Reports For 06/15/98 - 06/16/98 ** EVENT NUMBERS ** 34243 34256 34397 34398 34399 34400 34401 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34243 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 05/15/98 | |UNIT: [ ] [ ] [3] STATE: CT |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 05/15/98 | +------------------------------------------------+EVENT TIME: 15:15[EDT]| |NRC NOTIFIED BY: ROBERT SMITH |LAST UPDATE DATE: 06/15/98 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOHN WHITE RDO | |AINC 50.72(b)(2)(iii)(C) POT UNCNTRL RAD REL | | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | COMPLIANCE WITH GENERAL DESIGN CRITERIA 19 NOT DEMONSTRATED. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "IN THE PROCESS OF REVISING THE RADIATION SHIELDING SECTION OF CHAPTER 12 | | OF THE [FINAL SAFETY ANALYSIS REPORT], IT WAS DETERMINED THAT THE DOSES | | BEING CALCULATED BY NORTHEAST UTILITIES RADIOLOGICAL ASSESSMENT BRANCH TO | | DEMONSTRATE COMPLIANCE FOR CERTAIN POST-ACCIDENT ACTIVITIES [DID] NOT MEET | | THE GENERAL DESIGN CRITERIA [(GDC)]-19 LIMIT OF 5 REM WHOLE BODY. TWO | | ACTIVITIES WERE IDENTIFIED IN THE EMERGENCY OPERATING PROCEDURES (EOP) THAT | | CANNOT BE PERFORMED DUE TO THE RADIATION FIELDS INVOLVED. THESE ARE:" | | | | "1. REFUELING WATER STORAGE TANK [(RWST)]/CHARGING PUMP SUCTION VALVE | | BREAKERS MUST BE LOCALLY OPENED AT APPROXIMATELY 30 MINUTES POST-[LOSS | | OF COOLANT ACCIDENT (LOCA)]. THIS OPERATION INVOLVES MANIPULATING A | | VALVE ON THE OTHER SIDE OF A WALL FROM THE PERSONNEL HATCH WITH A | | PROJECTED RADIATION FIELD (BASED UPON PRELIMINARY CALCULATIONS) OF | | GREATER THAN 50,000 R/Hr." | | | | "2. AT APPROXIMATELY 4 DAYS AFTER A LOCA, THE HYDROGEN PURGE SYSTEM MUST | | BE ALIGNED FOR OPERATION. THIS OPERATION INVOLVES OPERATOR ACTIONS AT | | LOCATIONS WITHIN THE AUXILIARY BUILDING. AT THE 23-FOOT ELEVATION, | | RADIATION FIELDS ARE PROJECTED TO BE GREATER THAN 500 R/Hr. AT THE | | 4-FOOT ELEVATION, RADIATION FIELDS ARE PROJECTED TO BE GREATER THAN | | 1,000 R/Hr. (BOTH ESTIMATES [WERE] BASED UPON PRELIMINARY | | CALCULATIONS.)" | | | | "THE VERY HIGH RADIATION CONDITIONS DESCRIBED COULD PREVENT AN OPERATOR | | FROM PERFORMING NECESSARY ACTIONS REQUIRED BY THE EOPs. THEREFORE, THESE | | CONDITIONS ARE REPORTABLE PURSUANT TO 10CFR50.72(b)(2)(iii) AND | | 10CFR50.73(A)(2)(v) AS ANY EVENT OR CONDITION THAT ALONE COULD HAVE | | PREVENTED THE FULFILLMENT OF A SAFETY FUNCTION OF STRUCTURES OR SYSTEMS | | THAT ARE NEEDED TO CONTROL THE RELEASE OF RADIOACTIVE MATERIAL AND/OR | | MITIGATE THE CONSEQUENCES OF AN ACCIDENT." | | | | "CORRECTIVE ACTIONS FOR THIS EVENT HAVE NOT YET BEEN IDENTIFIED." | | | | THE LICENSEE NOTIFIED STATE AND LOCAL GOVERNMENTS AND PLANS TO NOTIFY THE | | NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1819 EDT ON 06/15/98 FROM ROBERT SMITH TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "ON 05/15/98, IT WAS IDENTIFIED THAT THE PROJECTED DOSE (BASED ON | | PRELIMINARY CALCULATIONS) FOR PERFORMING TWO EOP-RELATED ACTIVITIES, POST | | ACCIDENT, IN VITAL AREAS WITHIN THE PLANT, WOULD EXCEED THE GDC-19 GUIDANCE | | OF 5 REM WHOLE BODY. A 4-HOUR REPORT WAS MADE PURSUANT TO | | 10CFR50.72(b)(2)(iii) AS A LOSS OF SAFETY FUNCTION ON 05/15/98. FURTHER | | REFINEMENT OF THE CALCULATIONS AND REVIEW OF THE APPLICABLE LICENSING AND | | DESIGN BASIS HAS RESULTED IN A REVISED REPORTABILITY DETERMINATION. THE | | TWO ACTIVITIES ARE:" | | | | "1. OPENING THE RWST/CHARGING PUMP SUCTION VALVE BREAKERS TO PROVIDE A | | BACKUP MEANS TO PREVENT CONTAINMENT BACK LEAKAGE TO THE RWST. THE | | REVISED CALCULATION IS LESS THAN THE 5-REM GUIDANCE OF GDC 19." | | | | "2. THE BEYOND-THE-DESIGN-BASIS OPERATION OF THE CONTAINMENT VACUUM | | (HYDROGEN PURGE) SYSTEM POST-LOCA. ORIGINALLY THE 5-REM GDC-19 | | GUIDANCE WAS THOUGHT TO APPLY. A SUBSEQUENT REVIEW OF THE LICENSING | | BASIS DETERMINED THAT UTILIZATION OF THIS METHOD OF COMBUSTIBLE GAS | | CONTROL WAS FOR BEYOND DESIGN BASIS EVENTS (DBE). THE DOSE CRITERIA | | FOR BEYOND DBEs IS SPECIFIED IN THE EMERGENCY PLAN AS 25 REM." | | | | "BASED UPON THE DOSE FOR EACH OF THESE ACTIVITIES BEING WITHIN THE DESIGN | | CRITERIA FOR THE RESPECTIVE SITUATION, THESE CONDITIONS ARE NOT REPORTABLE | | PURSUANT TO 10CFR50.72(b)(2)(iii) AS 'ANY EVENT OR CONDITION THAT ALONE | | COULD HAVE PREVENTED THE FULFILLMENT OF THE SAFETY FUNCTION OF STRUCTURES | | OR SYSTEMS THAT ARE NEEDED TO: (c) CONTROL THE RELEASE OF RADIOACTIVE | | MATERIAL AND (d) MITIGATE THE CONSEQUENCES OF AN ACCIDENT.' ALSO, BASED | | UPON FURTHER REVIEW, THESE CONDITIONS WERE DETERMINED TO BE NOT REPORTABLE | | PURSUANT TO 10CFR50.73(a)(2)(ii)(B) AS CONDITIONS OUTSIDE THE DESIGN BASIS. | | THEREFORE, THESE CONDITIONS ARE NOT REPORTABLE, AND THE IMMEDIATE | | NOTIFICATION FOR THIS EVENT IS RETRACTED." | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. THE NRC | | OPERATIONS OFFICER NOTIFIED THE R1DO (WILLIAMS). | +------------------------------------------------------------------------------+ !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34256 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: OCONEE REGION: 2 |NOTIFICATION DATE: 05/18/98 | |UNIT: [1] [2] [3] STATE: SC |NOTIFICATION TIME: 17:56 [ET]| |RX TYPE: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP |EVENT DATE: 05/18/98 | +------------------------------------------------+EVENT TIME: 17:30[EDT]| |NRC NOTIFIED BY: DAVID NIX |LAST UPDATE DATE: 06/15/98 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |ANN BOLAND 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 | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 3 | N Y 100 POWER OPERATION | 100 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 10 CFR PART 50, APPENDIX 'R,' ISSUE - TWO INDEPENDENT MEANS OF SAFE | | SHUTDOWN MAY NOT BE AVAILABLE FOLLOWING A FIRE. | | | | RECENT INSPECTIONS OF THE FIRE WALL BETWEEN THE EAST AND WEST PENETRATION | | ROOMS HAVE IDENTIFIED NONCONFORMING CONDITIONS IN THE FIRE WALL STRUCTURE | | AND IN SOME OF THE PENETRATION SEALS THAT MAINTAIN THE FIRE BOUNDARY | | CHARACTERISTICS OF THE WALL. ITEMS FOUND WERE MINOR TO SIGNIFICANT VOIDS | | IN THE PENETRATION SEALS AND CRACKING AND SPALLING OF THE WALL MATERIAL. | | THESE WALLS WERE EVALUATED TO ASSESS THE SIGNIFICANCE OF THE FINDINGS, AND | | THE LICENSEE'S PRELIMINARY CONCLUSION IS THAT THE WALLS MAY NOT HAVE BEEN | | CAPABLE OF PERFORMING THEIR INTENDED FUNCTION FOLLOWING AN APPENDIX 'R' | | FIRE. | | | | THERE ARE NINE DIFFERENT FIRE ZONES AT OCONEE, OF WHICH TWO HAVE BEEN | | IDENTIFIED AS CRITICAL FIRE ZONES. ONE OF THE CRITICAL FIRE ZONES IS THE | | SAFE SHUTDOWN FACILITY AND ITS EQUIPMENT THAT IS ROUTED THROUGH EACH OF THE | | UNITS' WEST PENETRATION ROOMS. THE SECOND ZONE IS THE AREA EAST OF THE | | EAST/WEST PENETRATION ROOM DIVIDING WALL, AND IT ENCOMPASSES THE PLANT | | EQUIPMENT NORMALLY RELIED UPON TO SAFELY SHUT DOWN THE REACTOR. THE 3-HOUR | | RATED FIRE WALL BETWEEN THE EAST AND WEST PENETRATION ROOMS ASSURES THAT | | THESE TWO CRITICAL FIRE AREAS, WHICH SEPARATE THE TWO SAFE SHUTDOWN PATHS, | | ARE INDEPENDENT. | | | | THE LICENSEE HAS DETERMINED THAT THIS CONDITION IS OUTSIDE OF THE DESIGN | | BASIS OF THE PLANT IN THAT TWO INDEPENDENT MEANS OF ACHIEVING SAFE SHUTDOWN | | FOLLOWING AN APPENDIX 'R' FIRE MAY NOT HAVE BEEN AVAILABLE. AN ENGINEERING | | ANALYSIS OF THE IDENTIFIED CONDITIONS IS CONTINUING. EFFORTS ARE BEING | | INITIATED TO REPAIR THE WALLS, AND FIRE WATCHES HAVE BEEN POSTED IN | | ACCORDANCE WITH LICENSE COMMITMENTS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | | | | * * * UPDATE AT 1638 EDT ON 06/15/98 FROM DAVID NIX TO S.SANDIN * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AFTER FURTHER REVIEW, DUKE POWER COMPANY FEELS THAT THIS EVENT DOES NOT | | MEET THE REPORTABILITY REQUIREMENTS OF 10 CFR 50.72." | | | | "AN ENGINEERING ANALYSIS WAS PERFORMED CONSIDERING THE IDENTIFIED | | CONDITIONS OF THE 3-HOUR RATED FIRE WALL. THE CALCULATION WAS BASED ON OUR | | EXAMINATION OF THE AVAILABLE ELEMENTS OF THE DEFENSE IN DEPTH FIRE | | PROTECTION PROGRAM AND BASED ON THE PHYSICAL ARRANGEMENT OF EQUIPMENT WITH | | RESPECT TO AVAILABLE IGNITION SOURCES, CABLE TRAYS, AND COMBUSTIBLE | | MATERIALS IN THE EAST AND WEST PENETRATION ROOMS." | | | | "THE ANALYSIS CONCLUDED THE FOLLOWING:" | | | | "* THERE IS A LOW POTENTIAL FOR FIRE INITIATION IN THE EAST AND WEST | | PENETRATION ROOMS. THIS IS DUE TO THE CABLING IN TRAYS CONSTITUTING A | | LOW TO MODERATE FIRE LOADING; THE CABLE IS GROUNDED, ARMORED, SHEATHED | | CONSTRUCTION WHICH IS MORE RESISTANT TO FIRE; AND THERE IS NOT A | | SIGNIFICANT AMOUNT OF CREDIBLE IGNITION SOURCES IN THE AREA." | | | | "* THERE IS A LACK OF CONTINUITY OF COMBUSTIBLE MATERIAL BETWEEN CREDIBLE | | IGNITION SOURCES AND CABLE TRAYS TO PROPAGATE A FIRE THAT COULD OCCUR. | | THE EAST/WEST PENETRATION ROOM BARRIER IS OVER 90 FEET FROM THE | | CREDIBLE IGNITION SOURCES IN THE EAST PENETRATION ROOM. IN ADDITION, | | THE STANDBY SHUTDOWN FACILITY CABLING IS OVER 25 FEET AWAY FROM THE | | BARRIER IN THE WEST PENETRATION ROOM." | | | | "* A FIRE THAT COULD INITIATE WOULD BE DETECTED PRIOR TO REACHING THE | | DEGRADED BARRIER." | | | | "* THE FIRE BRIGADE IS CAPABLE OF RESPONDING TO CONTROL AND EXTINGUISH ANY | | FIRE IN A TIMELY MANNER." | | | | "* SINCE IT IS UNLIKELY THERE WOULD HAVE BEEN DIRECT FLAME IMPINGEMENT ON | | THE DEGRADED BARRIER, THE BARRIER COULD HAVE PROVIDED SOME LEVEL OF | | FIRE PROPAGATION PROTECTION." | | | | "THEREFORE, EVEN IN THE UNLIKELY EVENT THAT A FIRE OCCURRED IN ONE OF THE | | TWO CRITICAL AREAS, THE FIRE WOULD NOT HAVE PROPAGATED TO AN EXTENT THAT | | WOULD HAVE RENDERED THE SECOND CRITICAL AREA UNABLE TO SAFELY SHUTDOWN THE | | AFFECTED REACTOR." | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. THE NRC OPERATIONS | | OFFICER NOTIFIED THE R2DO (LANDIS). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 34397 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 06/15/98 | | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 02:12 [ET]| |COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 06/15/98 | | 6903 ROCKLEDGE DRIVE |EVENT TIME: 01:25[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 06/15/98 | | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION| |LICENSE#: GDP-2 AGREEMENT: N |THOMAS KOZAK RDO | | DOCKET: 0707002 |JOE HOLONICH/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: ERIC SPAETH | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |PAAA 95.57(b) LOSS OF CLASSIFIED INFO | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL COMPROMISE OF CLASSIFIED INFORMATION DUE THE DISCOVERY OF AN | | UNSECURED CLASSIFIED REPOSITORY (1-HOUR REPORT) (REFER TO EVENT #34340 FOR | | A SIMILAR EVENT.) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM PORTSMOUTH: | | | | "WHILE CONDUCTING ROUTINE SECURITY CHECKS IN THE X-710 FACILITY, PROTECTIVE | | FORCES PERSONNEL DISCOVERED AN UNSECURED CLASSIFIED REPOSITORY IN THE | | OFFICE AREA. THE DISCOVERY WAS MADE AT 0125 HOURS ON MONDAY, JUNE 15th, | | 1998, AND [IT] WAS IMMEDIATELY REPORTED TO THE PROTECTIVE FORCES SHIFT | | COMMANDER WHO THEN REPORTED THE INCIDENT TO THE ON-DUTY PLANT SHIFT | | SUPERINTENDENT. THE CUSTODIAN OF THE CLASSIFIED REPOSITORY WAS NOTIFIED, | | AND THE CONTENTS OF THE REPOSITORY WILL BE INVENTORIED. LEAVING A | | CLASSIFIED REPOSITORY UNSECURED CONSTITUTES A SECURITY INFRACTION AT | | PORTSMOUTH GASEOUS DIFFUSION PLANT." | | | | PORTSMOUTH PERSONNEL NOTIFIED THE NRC RESIDENT INSPECTOR AND PLAN TO | | NOTIFIED THE DEPARTMENT OF ENERGY SITE REPRESENTATIVE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34398 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: WASHINGTON NUCLEAR REGION: 4 |NOTIFICATION DATE: 06/15/98 | |UNIT: [2] [ ] [ ] STATE: WA |NOTIFICATION TIME: 05:28 [ET]| |RX TYPE: [2] GE-5 |EVENT DATE: 06/15/98 | +------------------------------------------------+EVENT TIME: 02:22[PDT]| |NRC NOTIFIED BY: SHAWN JARROW |LAST UPDATE DATE: 06/15/98 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |WILLIAM JOHNSON 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 36 POWER OPERATION | 35 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO THE INABILITY TO ISOLATE A | | CONTAINMENT PENETRATION AS A RESULT OF A STUCK TRAVERSING INCORE PROBE | | (TIP) DRIVE CABLE | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "A 1-HOUR NON-EMERGENCY REPORT IS BEING MADE DUE TO INITIATION OF A PLANT | | SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS. THE PLANT SHUTDOWN [FROM | | 36% POWER] WAS INITIATED AT 0222 PDT." | | | | "DURING TIP MOVEMENTS, A TIP DRIVE CABLE BECAME STUCK. THE CAUSE OF THE | | STUCK CABLE IS NOT KNOWN AT THIS TIME. THIS DISABLED THE [FACILITY'S] | | ABILITY TO CLOSE [GATE VALVE] TIP-V-2 WHICH IS A PRIMARY CONTAINMENT | | ISOLATION VALVE. THE PENETRATION IS CAPABLE OF BEING ISOLATED VIA THE | | IN-LINE SHEAR VALVE WHICH IS STILL OPERABLE." THE IN-LINE SHEAR VALVE IS A | | KEY-LOCK, EXPLOSIVE, SQUIB-TYPE VALVE WHICH WOULD CRIMP THE LINE IF IT WAS | | CLOSED. THIS WOULD NECESSITATE REPLACEMENT OF BOTH THE IN-LINE SHEAR VALVE | | AND THE TIP DETECTOR DRIVE CABLE. | | | | "TECHNICAL SPECIFICATIONS DIRECT THE PLANT TO GO TO HOT SHUTDOWN WITHIN 12 | | HOURS AND BE IN COLD SHUTDOWN WITHIN 36 HOURS IF THE INOPERABLE PRIMARY | | CONTAINMENT ISOLATION VALVE IS NOT ISOLATED WITHIN 4 [HOURS]. SINCE THE | | IN-LINE VALVE IS A SHEAR VALVE [WHICH WOULD CRIMP THE LINE IF CLOSED], THE | | FACILITY HAS CHOSEN TO SHUT [THE UNIT] DOWN. THE PLANT IS CURRENTLY AT 35% | | POWER IN MODE 1 WITH A SHUTDOWN IN PROGRESS." | | | | "WHEN PERMITTED, A PRIMARY CONTAINMENT ENTRY WILL BE PERFORMED FOR | | INSPECTION AND RECOVERY OF THE TIP DRIVE CABLE." | | | | THE LICENSEE STATED THAT DRYWELL INSTRUMENTATION HAS NOT INDICATED AN | | INCREASE IN RADIATION LEVELS. HOWEVER, THE LICENSEE PLANS TO TAKE | | PRECAUTIONS DURING THE UPCOMING PRIMARY CONTAINMENT ENTRY DUE TO THE | | POTENTIAL FOR ELEVATED RADIATION LEVELS. | | | | THE LICENSEE PLANS TO PLACE THE UNIT IN MODE 4 (COLD SHUTDOWN). THE | | CURRENT ESTIMATED RESTART DATE IS 06/16/98. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34399 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: GEOTECHNICAL CONSULTANTS |NOTIFICATION DATE: 06/15/98 | | CITY: COLUMBUS REGION: 3 |NOTIFICATION TIME: 12:45 [ET]| | COUNTY: FRANKLIN STATE: OH |EVENT DATE: 06/13/98 | |LICENSE#: 34-26022-01 AGREEMENT: N |EVENT TIME: 08:00[EDT]| | DOCKET: |LAST UPDATE DATE: 06/15/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |BRENT CLAYTON RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+FEMA, DOE, USDA, HHS FAX | |NRC NOTIFIED BY: TOM FREDA |EPA, DOT (VIA NRC) FAX | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | MOISTURE DENSITY GAUGE STOLEN AND RECOVERED. | | | | BETWEEN 0800 AND 0845 EDT ON 06/13/98, A MOISTURE DENSITY GAUGE WAS STOLEN | | FROM A PARKED VEHICLE IN A RESTAURANT PARKING LOT. THE VEHICLE DRIVEN BY A | | TECHNICIAN EMPLOYED BY GEOTECHNICAL CONSULTANTS OF WESTERVILLE, OHIO, WAS | | BROKEN INTO, AND ONLY THE ORANGE CASE CONTAINING THE DEVICE WAS REMOVED. | | THE MOISTURE DENSITY GAUGE IS A CAMPBELL PACIFIC NUCLEAR, MODEL #MC1DR-82, | | S/N #MD-9119206, CONSISTING OF TWO SOURCES (A 10-mCi Cs-137 SOURCE AND A | | 50-mCi AMERICIUM-241/BERYLLIUM SOURCE). THE COLUMBUS POLICE DEPARTMENT | | (PD) WAS NOTIFIED OF THE THEFT. | | | | APPROXIMATELY 3 HOURS LATER (AT 1100 EDT), AN INDIVIDUAL CONTACTED THE | | RADIATION SAFETY OFFICER (RSO) REPORTING THAT HE HAD FOUND THE DEVICE. THE | | GAUGE WAS PICKED UP BY THE RSO IN THE PRESENCE OF THE PD WHO FELT THAT | | THERE WAS INSUFFICIENT EVIDENCE TO DETAIN THE INDIVIDUAL. THE LICENSEE | | DETERMINED THAT THE SOURCE WAS STILL IN THE LOCKED/COVERED POSITION | | PRECLUDING ANY PERSONNEL EXPOSURE. | | | | THE LICENSEE CONTACTED NRC REGION III (KEVIN NULL). | | | | (REFER TO THE HOO LOG FOR CONTACT INFORMATION.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 34400 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: AMERICAN CYANIMID COMPANY |NOTIFICATION DATE: 06/15/98 | | CITY: W. WINDSOR TWP REGION: 1 |NOTIFICATION TIME: 14:15 [ET]| | COUNTY: MERCER STATE: NJ |EVENT DATE: 06/15/98 | |LICENSE#: 29-07694-01 AGREEMENT: N |EVENT TIME: : [EDT]| | DOCKET: |LAST UPDATE DATE: 06/15/98 | | +-----------------------------+ | |PERSON ORGANIZATION| | |RICHARD BARKLEY RDO | | |FRED COMBS, NMSS EO | +------------------------------------------------+FEMA, DOE, USDA, HHS FAX | |NRC NOTIFIED BY: GEORGE MacDURMON |EPA, DOT (VIA NRC) FAX | |HQ OPS OFFICER: STEVE SANDIN | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DETECTOR CONTAINING 15 mCi OF NI-63 WAS DETERMINED TO BE MISSING DURING | | INVENTORY IN WEST WINDSOR TOWNSHIP, NEW JERSEY. | | | | DURING A ROUTINE INVENTORY, THE LICENSEE DISCOVERED THAT A DETECTOR | | CONTAINING 15 mCi OF Ni-63 WAS MISSING. THE DETECTOR WAS REMOVED FROM AN | | HP GAS CHROMATOGRAPH DURING MAINTENANCE AND TRANSFERRED TO A SCIENTIST'S | | OFFICE ON 06/27/97. THE SCIENTIST NOTICED THAT IT WAS MISSING ON 06/30/97, | | HOWEVER, HE DID NOT REPORT THIS TO THE RADIATION SAFETY OFFICER (RSO) UNTIL | | LATER. WHEN THE RSO WAS NOTIFIED, A SEARCH OF THE FACILITY WAS PERFORMED | | INCLUDING A CALL TO THE SOURCE OWNER, HEWLETT-PACKARD, TO DETERMINE IF THE | | DETECTOR (WHICH WAS STORED IN A SHIPPING CONTAINER) HAD BEEN INADVERTENTLY | | RETURNED. ALL EFFORTS TO LOCATE THE DETECTOR WERE UNSUCCESSFUL. THE | | LICENSEE HAS IMPLEMENTED CORRECTIVE ACTIONS TO PREVENT A RECURRENCE OF THIS | | EVENT AND HAS DISCUSSED THIS EVENT WITH NRC REGION I (JOHN KINNEMAN). | | | | (REFER TO THE HOG LOG FOR CONTACT INFORMATION.) | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 34401 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 06/15/98 | |UNIT: [1] [2] [ ] STATE: WI |NOTIFICATION TIME: 15:17 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 06/15/98 | +------------------------------------------------+EVENT TIME: 13:16[CDT]| |NRC NOTIFIED BY: R.P. WOOD |LAST UPDATE DATE: 06/15/98 | |HQ OPS OFFICER: STEVE SANDIN +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |BRENT CLAYTON 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 N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HYDROGEN MONITORS WERE DECLARED INOPERABLE DUE TO WIRE TERMINATIONS NOT | | HAVING EPOXY COATINGS MAINTAINED AS SPECIFIED IN THE VENDOR MANUAL. | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "THE ENVIRONMENTAL QUALIFICATION FOR UNIT 1 AND UNIT 2 HYDROGEN MONITORS | | FOR CONTAINMENT ATMOSPHERE MAY [NOT HAVE] BEEN MAINTAINED. THE VENDOR | | [(EXOSENSOR)] REQUIRES AN EPOXY COATING ON ALL WIRE TERMINATIONS. THIS | | COATING MAY HAVE BEEN DISTURBED DURING SERVICE AND CALIBRATION. UNIT 1 IS | | IN REFUELING SHUTDOWN WITH THE [REACTOR COOLANT SYSTEM] TEMPERATURE [AT] | | 96øF. UNIT 2 ENTERED A 72-HOUR [LIMITING CONDITION FOR OPERATION (LCO)] | | BASED ON TECHNICAL SPECIFICATION 15.3.5-5 REQUIREMENTS. AFFECTED EQUIPMENT | | [IS THE UNIT] 1 AND 2 HA-964, -965, -966 AND -967." | | | | THE LICENSEE ANTICIPATES PROCURING AND APPLYING A QUALIFIED EPOXY TO THE | | AFFECTED TERMINATIONS BEFORE THE 72-HOUR LCO EXPIRES. | | | | THE LICENSEE INFORMED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+