U.S. Nuclear Regulatory Commission Operations Center Event Reports For 11/17/1998 - 11/18/1998 ** EVENT NUMBERS ** 34820 35043 35044 35045 35046 35047 35048 35049 +------------------------------------------------------------------------------+ |Fuel Cycle Facility |Event Number: 34820 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 09/22/1998| | RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 13:16[EDT]| | COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 09/21/1998| | 6903 ROCKLEDGE DRIVE |EVENT TIME: 13:30[EDT]| | BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 11/17/1998| | CITY: PIKETON REGION: 3 +-----------------------------+ | COUNTY: PIKE STATE: OH |PERSON ORGANIZATION | |LICENSE#: GDP-2 AGREEMENT: N |JAMES CREED RDO | | DOCKET: 0707002 |FRED COMBS, NMSS EO | +------------------------------------------------+FRANK CONGEL, AEOD IRD | | NRC NOTIFIED BY: ERIC SPAETH | | | HQ OPS OFFICER: FANGIE JONES | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | 24-HOUR NRC BULLETIN 91-01 REPORT, LOSS OF CRITICALITY CONTROL | | | | PLANT PERSONNEL DETERMINED THAT A NUCLEAR CRITICALITY SAFETY APPROVAL | | (NCSA) WAS DEFICIENT IN THAT IT FAILED TO ANALYZE A CREDIBLE SCENARIO AND, | | THEREFORE, FAILED TO ESTABLISH THE CONTROLS NECESSARY TO MEET THE DOUBLE | | CONTINGENCY PRINCIPLE. CONTROL #2 REQUIRES THAT ONLY 'TRACE AMOUNTS' | | (UNDEFINED) OF URANIUM-BEARING MATERIAL MAY BE PRESENT IN THE PROCESS | | EQUIPMENT (CONVERTERS) MOVED INTO THE X-700 CONVERTER DISASSEMBLY/REPAIR | | AREA. THE EVALUATION FURTHER STATES THAT EQUIPMENT WITH SIGNIFICANT | | ACCUMULATIONS OF URANIUM MATERIAL WOULD BE CLEANED IN THE X-705 | | DECONTAMINATION FACILITY PRIOR TO TRANSFER. ESTIMATED ENRICHMENT CAN REACH | | 100 WEIGHT % UO2F2. ADDITIONALLY, NONDESTRUCTIVE EXAMINATION OF CONVERTERS | | IN THE X-700 CONVERTER AREA INDICATE THAT MORE THAN TRACE AMOUNTS OF | | URANIUM-BEARING MATERIALS ARE PRESENT IN THEM. THESE CONVERTERS WERE | | STAGED IN THE AREA PRIOR TO THE NCSA FOR THE AREA. | | | | THE NCSA PRESENTLY DOES NOT BOUND THE CONDITIONS PRESENT. THE NCSA IS | | BEING UPDATED TO INCLUDE MULTIPLE CONVERTERS AND MORE THAN TRACE AMOUNTS OF | | URANIUM-BEARING MATERIALS BEING PRESENT. THERE HAS BEEN AN ADMINISTRATIVE | | HOLD PLACED ON DISASSEMBLY AND REPAIR OF CONVERTERS IN THE X-700 AREA. | | CRITICALITY PERSONNEL HAVE DETERMINED THE PRESENT SAFETY OF THE CONDITION | | IN THE X-700 BUILDING AND NOTE THAT MODERATION CONTROLS HAVE ALWAYS BEEN | | MET. | | | | PORTSMOUTH PERSONNEL INFORMED THE NRC RESIDENT INSPECTOR AND PLAN TO INFORM | | THE ONSITE DEPARTMENT OF ENERGY REPRESENTATIVE. | | | | * * * RETRACTION 1042 11/12/98 FROM VANDERPOOL TAKEN BY STRANSKY * * * | | | | THIS REPORT IS BEING RETRACTED BECAUSE NON-DESTRUCTIVE ANALYSIS MONITORING | | INDICATED NO SIGNIFICANT DEPOSITS OF URANIUM; THEREFORE, NCSA COMPLIANCE WAS | | MAINTAINED. THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. NOTIFIED R3DO | | (GEOFFREY WRIGHT). | | | | * * * CANCELLATION OF RETRACTION 1246 11/17/98 FROM HALCOMB TAKEN BY | | STRANSKY * * * | | | | "AFTER FURTHER TECHNICAL REVIEW, THE ABOVE RETRACTION IS NO LONGER VALID AND | | IS HEREBY CANCELLED. | | | | "ON SEPTEMBER 21, 1998, PLANT PERSONNEL DETERMINED THAT A NUCLEAR | | CRITICALITY SAFETY APPROVAL (NCSA-0700904.AOO) WAS DEFICIENT IN THAT IT | | FAILED TO ANALYZE A CREDIBLE SCENARIO AND THEREFORE FAILED TO ESTABLISH THE | | CONTROLS NECESSARY TO MEET THE DOUBLE CONTINGENCY PRINCIPLE. CONTROL #2 | | REQUIRES THAT ONLY TRACE AMOUNTS OF URANIUM-BEARING MATERIAL MAY BE PRESENT | | IN PROCESS EQUIPMENT (CONVERTERS) MOVED INTO THE X-700 CONVERTER | | DISASSEMBLY/REPAIR AREA. THE NCSA/NCSE DOES NOT DEFINE WHAT 'TRACE AMOUNT' | | OF URANIUM BEARING MATERIAL IS. THE NCSE FURTHER STATES THAT EQUIPMENT WITH | | SIGNIFICANT ACCUMULATIONS OF URANIUM MATERIAL WOULD BE CLEANED IN THE X-705 | | DECONTAMINATION FACILITY PRIOR TO TRANSFER TO X-700. CONVERTERS WERE | | TRANSFERRED TO X-700 WITHOUT PRIOR DECONTAMINATION IN THE X-705 | | DECONTAMINATION FACILITY. ADDITIONALLY NONDESTRUCTIVE ANALYSIS (NDA) | | INDICATED THAT MORE THAN TRACE AMOUNTS OF URANIUM BEARING MATERIAL ARE | | PRESENT IN SOME OF THE CONVERTERS CURRENTLY STAGED IN X-700 BUILDING. | | | | "THE NCSE ALSO DID NOT CONSIDER MULTIPLE CONVERTERS IN THE | | DISASSEMBLY/REPAIR AREA CONTAINING MORE THAN A TRACE AMOUNT OF URANIUM | | BEARING MATERIAL." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED OF THIS UPDATE. NOTIFIED R3DO | | (PATRICK HILAND). | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35043 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/17/1998| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 10:14[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 11/17/1998| +------------------------------------------------+EVENT TIME: 09:15[EST]| | NRC NOTIFIED BY: J. D. KLEVORN |LAST UPDATE DATE: 11/17/1998| | HQ OPS OFFICER: JOHN MacKINNON +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |RONALD BELLAMY R1 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | Gross primary containment leakage | | | | The primary containment type "B" and "C" total as-found minimum pathway | | leakage rate has exceeded the minimum allowable limit specified in the | | facility technical specifications. Technical specification paragraph 6.20.B | | establishes the maximum allowable leakage limit at 0.5% air weight per day. | | This condition was discovered upon completing "D" main steam line isolation | | valve local leak rate testing. This problem will be corrected before plant | | startup. | | | | The NRC resident inspector was notified of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35044 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 11/17/1998| | UNIT: [1] [] [] STATE: NY |NOTIFICATION TIME: 13:11[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 11/17/1998| +------------------------------------------------+EVENT TIME: 10:38[EST]| | NRC NOTIFIED BY: SHAWN ALLEN |LAST UPDATE DATE: 11/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |RONALD BELLAMY R1 | |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ |1 N N 0 Refueling |0 Refueling | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DRYWELL FLOOR DRAIN ISOLATION DUE TO LOSS OF RPS BUS | | | | AT 1038, THE 'B' REACTOR PROTECTION SYSTEM (RPS) MOTOR/GENERATOR SET TRIPPED | | FOR UNKNOWN REASONS. LOSS OF POWER TO THE RPS BUS GENERATED NUMEROUS | | PRIMARY CONTAINMENT ISOLATION SYSTEM (PCIS) ISOLATION SIGNALS; HOWEVER, | | BECAUSE OF CURRENT PLANT CONDITIONS, MANY SYSTEMS ARE ALREADY OUT OF SERVICE | | FOR OUTAGE ACTIVITIES. THE LICENSEE REPORTED THAT THE DRYWELL FLOOR DRAIN | | OUTBOARD CONTAINMENT ISOLATION VALVE CLOSED AS A RESULT OF THE LOSS OF | | POWER, AND ITS CLOSURE IS REPORTABLE AS AN ESF ACTUATION. THE NRC RESIDENT | | INSPECTOR HAS BEEN INFORMED OF THIS EVENT BY THE LICENSEE. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35045 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: OYSTER CREEK REGION: 1 |NOTIFICATION DATE: 11/17/1998| | UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 14:01[EST]| | RXTYPE: [1] GE-2 |EVENT DATE: 11/17/1998| +------------------------------------------------+EVENT TIME: 14:00[EST]| | NRC NOTIFIED BY: ERIC DEMONCH |LAST UPDATE DATE: 11/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |RONALD BELLAMY R1 | |10 CFR SECTION: | | |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 +------------------------------------------------------------------------------+ | STATION BATTERY RACK OUTSIDE OF SEISMIC DESIGN BASIS | | | | THE LICENSEE REPORTED A CONDITION DISCOVERED DURING THE PAST REFUELING | | OUTAGE. AS A RESULT OF SEISMIC WALKDOWNS AND SUBSEQUENT ENGINEERING | | REVIEWS, THE LICENSEE DISCOVERED THAT THE 'B' STATION BATTERY COULD NOT BE | | SHOWN TO COMPLY WITH ITS SEISMIC DESIGN BASIS DUE TO A FIELD MODIFICATION | | PERFORMED TO THE BATTERY RACK. | | | | THE STATION BATTERIES WERE SEISMICALLY QUALIFIED BASED UPON RESULTS OF A | | SHAKE TABLE TEST PERFORMED IN ACCORDANCE WITH IEEE STANDARDS. THE TEST | | CONFIGURATION CONSISTED OF THE BATTERIES, BATTERY RACK AND RACK RETAINING | | PLATES. DURING THE INSTALLATION OF THE BATTERIES, THE RETAINING PLATES WERE | | RELOCATED BASED UPON A FIELD CHANGE NOTICE (FCN). THE LICENSEE HAS BEEN | | UNABLE TO LOCATE THE ENGINEERING CALCULATIONS THAT SUPPORT THE FCN. DUE TO | | THE INABILITY TO LOCATE THE CALCULATIONS, THE LICENSEE CANNOT DEMONSTRATE | | THAT THE FCN MAINTAINED THE DESIGN BASIS. | | | | THIS CONDITION WAS CORRECTED BEFORE THE UNIT STARTED UP FROM THE OUTAGE. | | THE LICENSEE HAS SINCE DETERMINED THAT THE STATION BATTERY WOULD HAVE | | PERFORMED ITS INTENDED FUNCTION IN THE EVENT OF A SAFE SHUTDOWN EARTHQUAKE. | | THE LICENSEE WILL INFORM THE NRC RESIDENT INSPECTOR OF THIS REPORT. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35046 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: MILLSTONE REGION: 1 |NOTIFICATION DATE: 11/17/1998| | UNIT: [1] [] [] STATE: CT |NOTIFICATION TIME: 14:36[EST]| | RXTYPE: [1] GE-3,[2] CE,[3] W-4-LP |EVENT DATE: 11/17/1998| +------------------------------------------------+EVENT TIME: 14:16[EST]| | NRC NOTIFIED BY: JOHN OLSON |LAST UPDATE DATE: 11/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |RONALD BELLAMY R1 | |10 CFR SECTION: | | |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 Cold Shutdown |0 Cold Shutdown | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | Licensee notified State of Connecticut regarding small oil spill onsite. | | | | The licensee contacted the Connecticut Department of Environmental | | Protection regarding a small spill of fuel oil onsite. A fuel oil truck | | entering the site to make a delivery leaked approximately 0.25 gallons of a | | water/oil mixture onto the parking lot, which dispersed into a large oil | | sheen. The licensee immediately placed a berm around the truck and all | | storm drains, and dispatched plant personnel to clean up the oil. The oil | | sheen extended to the vicinity of a storm drain near the vehicle access | | point, but no oil was detected at the drain outfall. The licensee reported | | that the spill has been contained and removed. The NRC resident inspector | | has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Hospital |Event Number: 35047 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | LICENSEE: CLEVELAND CLINIC FOUNDATION |NOTIFICATION DATE: 11/17/1998| | CITY: CLEVELAND REGION: 3 |NOTIFICATION TIME: 16:45[EST]| | COUNTY: STATE: OH |EVENT DATE: 11/17/1998| |LICENSE#: 34-00466-0 AGREEMENT: N |EVENT TIME: 12:45[EST]| | DOCKET: |LAST UPDATE DATE: 11/17/1998| | +-----------------------------+ | |PERSON ORGANIZATION | | |PATRICK HILAND R3 | | |CHARLEY HAUGHNEY NMSS | +------------------------------------------------+ | | NRC NOTIFIED BY: STUART KLINE | | | HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: N/A | | |10 CFR SECTION: | | |IBBF 30.50(b)(2)(ii) EQUIP DISABLED/FAILS | | | | | | | | | | | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | STUCK SOURCE DURING BRACHYTHERAPY TREATMENT | | | | During treatment of a patient using an IDE experimental afterloader | | manufactured by U.S. Surgical Corp, the source became stuck partway through | | the catheter when the drive cable jammed. The 500 mCi Ir-192 sealed source | | was exposed, but not located in the patient at the time of the event. The | | afterloader device was immediately moved to another room, where the source | | was located in the catheter, the cable was cut, and the source was placed | | into a shielded container. The licensee representative stated that the | | source was exposed for approximately 15 minutes before being paced into the | | shielded container. Dosimetry has been collected from individuals involved | | in this event. The licensee representative will contact NRC Region III | | regarding this event. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35048 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: PRAIRIE ISLAND REGION: 3 |NOTIFICATION DATE: 11/17/1998| | UNIT: [1] [2] [] STATE: MN |NOTIFICATION TIME: 16:58[EST]| | RXTYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 11/17/1998| +------------------------------------------------+EVENT TIME: 15:30[CST]| | NRC NOTIFIED BY: BRAD ELLISON |LAST UPDATE DATE: 11/17/1998| | HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |PATRICK HILAND R3 | |10 CFR SECTION: | | |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 N 0 Hot Standby |0 Hot Standby | |2 N N 0 Refueling |0 Refueling | | | | +------------------------------------------------------------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POTENTIAL FOR SINGLE FAILURE DURING TESTING | | | | "On November 17, 1998, Prairie Island personnel identified a condition | | potentially outside of the plant design basis. Prairie Island has performed | | Technical Specification required surveillance testing of Boric Acid Storage | | Tank Level channels by placing the respective channel in the tripped | | condition. When in this condition, a single failure of another channel | | could cause a premature transfer of the Safety Injection Pump suctions to | | the Refueling Water Storage Tank. This would bypass the injection of highly | | borated water required to mitigate a steam line break accident. At this | | time, all boric acid level channels are OPERABLE and surveillance tests are | | being quarantined until corrective actions can be implemented. Unit 1 is | | currently in Mode 3 and Unit 2 is currently in Mode 6. Prairie Island will | | likely request Technical Specification changes to allow this testing." | | | | The NRC resident inspector has been informed of this event by the licensee. | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ |Power Reactor |Event Number: 35049 | +------------------------------------------------------------------------------+ +------------------------------------------------------------------------------+ | FACILITY: COOPER REGION: 4 |NOTIFICATION DATE: 11/18/1998| | UNIT: [1] [] [] STATE: NE |NOTIFICATION TIME: 05:15[EST]| | RXTYPE: [1] GE-4 |EVENT DATE: 11/18/1998| +------------------------------------------------+EVENT TIME: 01:37[CST]| | NRC NOTIFIED BY: WILLIAM GREEN |LAST UPDATE DATE: 11/18/1998| | HQ OPS OFFICER: FANGIE JONES +-----------------------------+ +------------------------------------------------+PERSON ORGANIZATION | |EMERGENCY CLASS: N/A |GREGORY PICK R4 | |10 CFR SECTION: | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+-----------------+--------+-----------------+ |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 +------------------------------------------------------------------------------+ | Shutdown Cooling isolated and Standby Gas Treatment actuated | | | | The licensee reported that the B-3 Electrical Protection Assembly (EPA), | | powered from CDP 1A, for Division 2 Reactor Protection System (RPS) power | | tripped. This caused a loss of power to Division 2 RPS. A Division 2 half | | scram occurred along with a half group isolation of Group 2 and Group 6. | | The Group 2 isolation caused RHR Shutdown Cooling Supply Inboard and | | Outboard Isolation Valves, to close. This resulted in a loss of shutdown | | cooling (SDC). Standby Gas Treatment System B actuated as a result of the | | half Group 6 isolation. | | | | Abnormal Procedure 2.4.2.4.1, RHR Loss of Shutdown Cooling, was entered. | | The half group Isolations were verified to have operated correctly. At 0143 | | RPS power was transferred to the RPS Motor Generator set and the half group | | isolations were reset. At 0150 SDC was restored. The coolant temperature | | band at the time of the loss of SDC was 90 to 110 þF with a coolant | | temperature of 93 þF. Temperature rose 1 þF (to 94 þF) during the loss of | | SDC. The level band before the loss of SDC was 170" to 204" above | | instrument zero, level remained within the assigned band during the loss of | | SDC. At 0208 Abnormal Procedure 2.4.2.4.1 was exited. | | | | The licensee will inform the NRC Resident Inspector. | +------------------------------------------------------------------------------+