Event Notification Report for March 8, 2000
U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
03/07/2000 - 03/08/2000
** EVENT NUMBERS **
36603 36676 36734 36745 36762 36763 36764 36765 36766 36767
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36603 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: UTAH DIVISION OF RADIATION CONTROL |NOTIFICATION DATE: 01/18/2000|
|LICENSEE: NUCLEAR TESTING SERVICES |NOTIFICATION TIME: 17:41[EST]|
| CITY: SALT LAKE CITY REGION: 4 |EVENT DATE: 01/18/2000|
| COUNTY: STATE: UT |EVENT TIME: 10:00[MST]|
|LICENSE#: UT 1800139 AGREEMENT: Y |LAST UPDATE DATE: 03/07/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LINDA SMITH R4 |
| |WAYNE HODGES NMSS |
+------------------------------------------------+JOSEPH GIITTER IRO |
| NRC NOTIFIED BY: JULIE FELICE | |
| HQ OPS OFFICER: LEIGH TROCINE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| AGREEMENT STATE REPORT INVOLVING TROXLER DENSITY GAUGE MISSING FROM NUCLEAR |
| TESTING SERVICES LOCATED IN SALT LAKE CITY, UTAH |
| |
| At 1000 MST on 01/18/00, Nuclear Testing Services located in Salt Lake City |
| notified the Utah Division of Radiation Control of a lost, missing, or |
| stolen gauge (Utah Incident Report UT-00-0002). The missing gauge was a |
| Troxler Electronic Laboratories, Inc. gauge (model number 3430, gauge |
| serial number 20882). The gauge contained two sealed sources: cesium-137 ( |
| source serial number 7-2293) and americium-241/beryllium (source serial |
| number 47-16381). Apparently, the licensee last had possession of the gauge |
| during April of 1999. This was also when the last leak test was performed. |
| The licensee believes that the gauge may have been leased out to another |
| company during August of 1999. However, there may have been problems with |
| the paperwork or accountability, and there were also changes in personnel. |
| |
| The Utah Division of Radiation Control instructed the licensee to contact |
| local Police Department because there is the possibility of theft. It was |
| also reported that the licensee had been in touch with Troxler. |
| |
| The Utah Division of Radiation Control stated that this event seemed to fit |
| the Abnormal Occurrence Criteria under any substantial breakdown of physical |
| security or material control. It was stated that one of those deals with |
| accountability systems. |
| |
| (Call the NRC operations center for a state contact telephone number.) |
| |
| * * * UPDATE AT 1608 ON 03/07/00 BY JULIE FELICE TO JOLLIFFE * * * |
| |
| Representatives from Geomatrix Consultants, Inc,, Costa Mesa, CA, notified |
| representatives of Nuclear Testing Services, Salt Lake City, UT that the |
| missing Troxler Moisture Density Gauge, Model #3430, Serial #20882, is in |
| Geomatrix's possession and had been all along. Geomatrix representatives |
| plan to return the undamaged gauge to Nuclear Testing Services. |
| |
| The NRC Operations Officer notified the R4DO Dave Loveless and NMSS EO Scott |
| Moore. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36676 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BEAVER VALLEY REGION: 1 |NOTIFICATION DATE: 02/09/2000|
| UNIT: [1] [] [] STATE: PA |NOTIFICATION TIME: 16:50[EST]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 02/08/2000|
+------------------------------------------------+EVENT TIME: 12:09[EST]|
| NRC NOTIFIED BY: CHRISTOPHER HYNES |LAST UPDATE DATE: 03/07/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |HAROLD GRAY R1 |
|10 CFR SECTION: | |
|NINF INFORMATION ONLY | |
|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 93 Power Operation |93 Power Operation |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| INFORMATION CALL REGARDING RIVER WATER PUMP PROBLEMS |
| |
| "This report is being made to provide preliminary notification of an event |
| that is currently under investigation at Beaver Valley Power Station Unit |
| No. 1 (BVPS Unit 1). |
| |
| "River Water Pump #WR-P-1B at BVPS Unit 1 tripped on overcurrent shortly |
| after it was attempted to be started at 1209 on 02/08/00. The Action |
| Statement for Technical Specification 3/4.7.4.1 was entered for less than |
| two River Water subsystems being operable. River Water Pump #WR-P-1C (swing |
| pump) was then aligned to the 'B' train header and it also tripped on |
| overcurrent shortly after it was started at 1716 on 02/08/00. |
| |
| "Preliminary information identified that the #1B and #1C River Water Pumps |
| would not operate due to the loss of gap between the pumps rotating assembly |
| and the pump bowl. Investigation into the cause of the loss of the pumps' |
| gap is ongoing. BVPS Unit 1 River Water Pump #1A on the 'A' train continues |
| to operate satisfactorily and is operable. The 'A' train is being treated |
| as protected equipment (i.e., no elective work is being done on or near 'A' |
| train components). The BVPS Unit 1 operating crews have reviewed the |
| procedures associated with operating the BVPS Unit 1 Auxiliary River Water |
| System in the Alternate Intake Structure and the use of the cross tie |
| connection with the diesel driven fire pump." |
| |
| The licensee stated that BVPS Unit 1 entered a 72 hour Technical |
| Specification Limiting Condition for Operation at 1209 on 02/08/00. The NRC |
| resident inspector has been informed of this notification by the licensee. |
| |
| * * * UPDATE AT 1827 ON 02/10/00 BY DAN MURRAY TO JOLLIFFE * * * |
| |
| The licensee has identified that the #1B and #1C River Water Pumps would not |
| operate due to the loss of gap between the pump's rotating assembly and the |
| pump bowl. This event is believed to have been initiated by a temporary |
| operating procedure that started on 02/05/00 for maintenance on the |
| non-safety related filtered water system. This procedure altered the |
| filtered water system configuration which was the normal supply to the River |
| Water Pumps' seal water system. One effect of this change was an increase |
| in the seal water temperature at times as much as 30 degrees above its |
| previous temperature which had been near the current river water |
| temperature. This temperature increase adversely affects a pump in the |
| standby configuration whereby thermal expansion of the pump's rotating |
| assembly causes a loss of clearance. River Water Pump #WR-P-1A has remained |
| operating satisfactorily throughout this event. The identified increased |
| seal water temperature condition would not adversely affect an operating |
| pump. Administrative controls have been implemented to require only the use |
| of seal water supply sources with temperatures at or near the current river |
| water temperature for the River Water Pumps. |
| |
| This condition is being reported to the NRC pursuant to |
| 10CFR50.72(b)(1)(ii)(B) as a condition that is outside the design basis of |
| the plant because of the potential for one train of the two-train safety |
| related River Water System (required to be operable per Technical |
| Specification 3/4.7.4.1) to have been incapable of performing its design |
| safety function for an extended period of time during operation. |
| |
| The licensee plans to revise the test procedure, perform the tech spec |
| surveillance test using the safety related seal water supply source, and |
| exit the tech spec action statement. |
| |
| The licensee notified the NRC Resident Inspector of this update. |
| |
| The NRC Operations Officer notified the R1DO Harold Gray of this update. |
| |
| * * * UPDATE AT 1816 ON 03/07/00 BY JOHN THOMAS TO JOLLIFFE * * * |
| |
| The following additional information is provided from a subsequent licensee |
| evaluation of the safety related seal water design for the River Water |
| System pumps at BVPS and the above event update: |
| |
| River Water Pump #WR-P-1C at BVPS Unit 1 was placed into service on 03/03/00 |
| with bearing and motor cooling water supplied by its own discharge via the |
| safety related "Y" strainer #RW-YS-42. Within 10-15 seconds of pump |
| startup, the seal water pressure dropped to approximately 5 psig from its |
| normal operating pressure of approximately 30 psig. The control room |
| operator then blew down the strainer and normal seal water operation ensued. |
| The normal non-safety related sources of seal water for the River Water |
| System pumps have only recently been removed from service as a result of the |
| above event update. A review of the adequacy of the current BVPS Unit 1 |
| seal water design for the River Water System was initiated as part of the |
| above event update. The partial plugging of the "Y" strainer on 03/03/00 |
| identifies that starting a River Water Pump which has been idle for a period |
| of time may initially ingest a slug of silt from the Intake Structure Bay |
| large enough to restrict the flow of seal water through this strainer. |
| Following an evaluation, the licensee has determined that a potential |
| inadequacy may exist in the BVPS Unit 1 seal water design for the River |
| Water System pumps that has been credited since initial operation of BVPS |
| Unit 1. Given that the strainer anomaly was quickly corrected, this seal |
| water design concern involves the operability of a non-operating pump during |
| startup. Seal water strainer plugging during pump operation is more gradual |
| and allows time for control room operator action. |
| |
| River Water System Pump #WR-P-1C remains in operation with seal water |
| supplied from its self-supplied strainer. An Auxiliary River Water Pump in |
| the Alternate Intake Structure is also available with its own separate seal |
| water supply. BVPS Unit 1 is currently in a refueling outage with all fuel |
| removed from the reactor vessel. |
| |
| The seal water design condition was previously reported pursuant to |
| 10CFR50.72(b)(1)(ii)(B) as a condition that was outside the design basis of |
| the plant because of the potential for one train of the two-train safety |
| related River Water System (required to be operable per Technical |
| Specification 3/4.7.4.1) to have been incapable of performing its design |
| safety function for an extended period of time during operation. This |
| additional information provides further basis that the seal water design for |
| the River Water System pumps was not sufficient to meet the design basis of |
| the plant. |
| |
| The licensee is continuing to investigate this event and plans to resolve |
| this issue prior to restarting Unit 1. |
| |
| The licensee plans to notify the NRC Resident Inspector of this update. |
| |
| The NRC Operations Officer notified the R1DO Greg Cranston of this update. |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36734 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: HOPE CREEK REGION: 1 |NOTIFICATION DATE: 02/28/2000|
| UNIT: [1] [] [] STATE: NJ |NOTIFICATION TIME: 06:34[EST]|
| RXTYPE: [1] GE-4 |EVENT DATE: 02/28/2000|
+------------------------------------------------+EVENT TIME: 05:45[EST]|
| NRC NOTIFIED BY: DAN BOYLE |LAST UPDATE DATE: 03/07/2000|
| HQ OPS OFFICER: BOB STRANSKY +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |JOHN WHITE R1 |
|10 CFR SECTION: |ROBERT SKELTON IAT |
|DDDD 73.71 UNSPECIFIED PARAGRAPH |JOHN DAVIDSON IAT |
|BAB1 20.2201(a)(1)(i) LOST/STOLEN LNM>1000X |WILLIAM BECKNER NRR |
| |WILLIAM BRACH NMSS |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| OVERDUE SHIPMENT OF NEW FUEL |
| |
| The licensee reported that a shipment of new fuel from ABB was due to arrive |
| onsite at 0530 2/28/00. At the time of the report, the shipment had not yet |
| arrived. The licensee is attempting to contact the shipper. The NRC resident |
| inspector will be informed of this event by the licensee. |
| |
| * * * UPDATE 0809 2/28/00 FROM PARKER TAKEN BY STRANSKY * * * |
| |
| The fuel shipment arrived onsite at 0735 2/28/00. The shipper (Roberts |
| Express) believed that the scheduled delivery time was 0700. The licensee |
| plans to investigate the discrepancy in the delivery schedule. The NRC |
| resident inspector will be informed of this update by the licensee. Notified |
| R1DO (White), NRR IAT (Skelton), NMSS IAT (Davidson), NRR EO (Beckner), and |
| NMSS IAT (Brach). |
| |
| * * * UPDATE 1012EST ON 3/7/00 FROM ERV PARKER TO S.SANDIN * * * |
| |
| "On 02/28/00, at 0634, Hope Creek made a one hour notification (NRC event |
| #36734). This notification stated 'Hope Creak Generating Station expected a |
| new fuel receipt to arrive on site at approximately 0530 this morning. As of |
| this time the shipment has not arrived. Station personnel are attempting to |
| contact the shipping vendor. Our information indicates that the truck was |
| dispatched at 1040 on Saturday and should have arrived by now.' The shipment |
| subsequently arrived on February 28, 2000, at 0735. This information was |
| provided to the NRC at 0805. |
| This notification was made in accordance with 10CFR73.71, Reporting Of |
| Safeguards Events, as a lost fuel shipment. The shipment was reported as |
| lost because the Control Room expected the shipment to arrive at 0530, and |
| it did not. The cause of the shipment not arriving at 0530 has been |
| determined to be miscommunication. Due to this miscommunication, the |
| trucking company believed that the shipment was expected at 0800. While |
| conducting the investigation, plant staff determined that the truck was |
| continually being tracked via satellite and the dispatcher was aware of its |
| location at all times. Therefore, the fuel truck was not lost and this event |
| is not reportable in accordance with 10CFR73.71. As a result, the |
| notification is being retracted." |
| |
| The licensee will inform the NRC resident inspector. Notified |
| R1DO(Cranston). |
+------------------------------------------------------------------------------+
!!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!!
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36745 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: ARKANSAS NUCLEAR REGION: 4 |NOTIFICATION DATE: 03/01/2000|
| UNIT: [] [2] [] STATE: AR |NOTIFICATION TIME: 13:56[EST]|
| RXTYPE: [1] B&W-L-LP,[2] CE |EVENT DATE: 03/01/2000|
+------------------------------------------------+EVENT TIME: 12:35[CST]|
| NRC NOTIFIED BY: LARRY MCLERRAN |LAST UPDATE DATE: 03/07/2000|
| HQ OPS OFFICER: DOUG WEAVER +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |CHARLES CAIN R4 |
|10 CFR SECTION: | |
|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 |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| UNANALYZED CONDITION - USING THE AUXILIARY FEEDWATER PUMP TO FEED THE STEAM |
| GENERATORS VIA THE MAIN FEEDWATER SYSTEM IS UNANALYZED. |
| |
| ANO engineering has determined that using the Auxiliary Feedwater (AFW) pump |
| to feed steam generators (S/Gs) via the Main Feedwater (MFW) System is |
| unanalyzed. The ability of the MFW block valves to shut and isolate the |
| affected S/G on a Main Steam Line Break (MSLB) has not been fully evaluated. |
| Preliminary evaluation indicates that the valves may not shut under worst |
| case conditions (low voltage supplied to the MOV and high D/P across the |
| valves). This condition is only applicable during low power operations with |
| AFW feeding via the MFW piping. |
| |
| AFW is not an Engineered Safety Feature at ANO Unit 2. The plant has a |
| separate Emergency Feedwater (EFW) System which is not affected by this |
| problem. |
| |
| The licensee will notify the NRC resident inspector. |
| |
| * * * UPDATE AT 1336 ON 03/07/00 BY TOM SCOTT TO JOLLIFFE * * * |
| |
| A licensee engineering review has determined that the consequences of the |
| above event would have had no safety significance. Review of the Hot Zero |
| Power (HZP) Containment Analysis for a MSLB showed that consequences of a |
| small amount of additional AFW would be bounded by the current limiting MSLB |
| containment analysis for Hot Full Power. A previous sensitivity analysis of |
| the effects of isolating EFW to the S/Gs indicated no significant impact due |
| to continued flow for the HZP Nuclear Steam Supply System MSLB analysis. |
| Since the consequences of having operated in an unanalyzed condition have |
| been determined not to have significantly compromised plant safety, |
| reporting to the NRC per 10CFR50.72(b)(1)(ii) is not applicable. |
| |
| Thus, the licensee desires to retract this event. |
| |
| The licensee notified the NRC Resident Inspector. |
| |
| The NRC Operations Officer notified the R4DO Dave Loveless. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|General Information or Other |Event Number: 36762 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 03/07/2000|
|LICENSEE: ROCKY MOUNTAIN CONSULTANTS |NOTIFICATION TIME: 12:39[EST]|
| CITY: REGION: 4 |EVENT DATE: 03/06/2000|
| COUNTY: STATE: CA |EVENT TIME: 12:00[PST]|
|LICENSE#: AGREEMENT: Y |LAST UPDATE DATE: 03/07/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |DAVID LOVELESS R4 |
| |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: DON BUNN | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
|BAB2 20.2201(a)(1)(ii) LOST/STOLEN LNM>10X | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - CESIUM-137 SOURCE LOCATED IN A LOAD OF SCRAP STEEL IN A SCRAP YARD IN UTAH |
| - |
| |
| On 03/06/00, Ed Johnson of Rocky Mountain Consultants notified California |
| Radiologic Health Branch (RHB) that he had discovered a 10 millicurie |
| Cs-137 source in a load of scrap steel that originated from California. The |
| |
| source was in a train car of scrap steel that set off the radiation monitor |
| at Nucor Steel Company, Utah. Mr Johnson searched the load and discovered a |
| Cs-137 source that had been removed from the body of a CPN portable gauge. |
| The source appeared to have been through a shredder but the serial number |
| was visible. The source manufacturer, Amersham, said it was delivered to |
| CPN who said they installed it in a MC-1 gauge, serial number M-19089075. |
| The gauge was sold to Petra Geotechnical Company, license #2933 in 1989. |
| This gauge was reported stolen on 12/12/94 and an investigation was |
| conducted at that time. Mr Johnson said the source will be shipped to CPN |
| who will dispose of it. |
| |
| The Am-241 neutron source was not located in the load of scrap steel. |
| RHB-LA plans to go to Williams Recycling Company, Los Angeles, where the |
| load originated, and survey their facility to try to locate it. The scrap |
| yard operator had installed a $30,000 Bicron gate monitor system three years |
| ago to keep unwanted radioactive material out of the scrap yard, but |
| apparently this did not work. A 5010 has been opened and assigned to RHB-LA |
| & Brea to investigate. |
| |
| RBH plans to notify NRC of this incident after results of the survey at |
| Williams Recycling Company are known. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36763 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/07/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 14:23[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/06/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 21:42[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/07/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY R3 |
| DOCKET: 0707002 |DON COOL NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: JEFF CASTLE | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - X-342 BUILDING EVACUATED DUE TO A VALID ACTUATION OF A "Q" SAFETY SYSTEM |
| - |
| |
| At 2142 on 03/06/00, X-342 building feed and sampling operations personnel |
| viewed smoke escaping from the pigtail (female) to manifold (male) fitting |
| for a cylinder in autoclave #2. The release started when the cylinder valve |
| was opened. The building personnel evacuated the building and remotely |
| placed the autoclave in containment shutdown. Placing the autoclave in |
| containment shutdown by design resulted in closure of the pigtail line |
| isolation/safety valve and a manual actuation of that particular safety |
| system. The safety system was actuated while the autoclave was in an |
| applicable TSR mode (TSR 2.1.3.13). The plant emergency response process |
| and procedures were implemented. Results of all surveys performed during |
| the emergency response were less than detectable. Plant personnel plan to |
| inspect the subject area and repair/replace damaged parts. |
| |
| This event is reportable to the NRC as a valid actuation of a "Q" Safety |
| System in accordance with Safety Analysis Report, Section 8.9 (24-Hour |
| Report). |
| |
| There was no loss of hazardous or radioactive material nor radioactive or |
| radiological contamination exposure as a result of this event. |
| |
| Plant personnel notified the NRC Resident Inspector and the Site DOE |
| Representative. |
| |
| PTS-2000-026, PR-PTS-00-01308. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36764 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: BRUNSWICK REGION: 2 |NOTIFICATION DATE: 03/07/2000|
| UNIT: [1] [2] [] STATE: NC |NOTIFICATION TIME: 15:45[EST]|
| RXTYPE: [1] GE-4,[2] GE-4 |EVENT DATE: 03/07/2000|
+------------------------------------------------+EVENT TIME: 15:04[EST]|
| NRC NOTIFIED BY: ANNETTE POPE |LAST UPDATE DATE: 03/07/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |EDWARD MCALPINE R2 |
|10 CFR SECTION: | |
|AESS 50.72(b)(1)(v) EMERGENCY SIREN INOP | |
|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 |
|2 N Y 100 Power Operation |100 Power Operation |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - TEN OFFSITE EMERGENCY SIRENS INOPERABLE FOR 19 MINUTES - |
| |
| At 1504 on 03/07/00, the licensee notified Brunswick County Officials that |
| ten offsite emergency sirens for Brunswick County were inoperable from 1444 |
| to 1503 on 03/07/00. Alternate offsite notification mechanisms were |
| available during this 19 minute period. |
| |
| The licensee notified the NRC Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Power Reactor |Event Number: 36765 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: WNP-2 REGION: 4 |NOTIFICATION DATE: 03/07/2000|
| UNIT: [2] [] [] STATE: WA |NOTIFICATION TIME: 19:47[EST]|
| RXTYPE: [2] GE-5 |EVENT DATE: 03/07/2000|
+------------------------------------------------+EVENT TIME: 14:22[PST]|
| NRC NOTIFIED BY: BOB BROWNLEE |LAST UPDATE DATE: 03/07/2000|
| HQ OPS OFFICER: DICK JOLLIFFE +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |DAVID LOVELESS R4 |
|10 CFR SECTION: |BRUCE BOGER NRR |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |THOMAS ESSIG NMSS |
| |JOSEPH GIITTER IRO |
| |BILL BEECHER PAO |
| | |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|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
+------------------------------------------------------------------------------+
| - NEWS RELEASE REGARDING THE RETRIEVAL OF BOXES OF RADIOACTIVE WASTE - |
| |
| The following news release was issued by the licensee to the general public |
| at 1422 PST on 03/07/00 regarding the retrieval of boxes of radioactive |
| waste that also may contain a hazardous substance: |
| |
| "Energy Northwest retrieves low-level radioactive waste shipment - RICHLAND, |
| WA -- |
| |
| Acting on its own initiative, Energy Northwest has retrieved four boxes of |
| low-level radioactive waste from US Ecology Inc. because the boxes possibly |
| also contain what is classified as a hazardous substance. The combination |
| of radioactive and hazardous wastes is considered mixed waste. US Ecology |
| operates the commercial low-level radioactive waste disposal site at |
| Hanford. US Ecology is not licensed to accept mixed waste. Energy |
| Northwest discovered this potential problem internally and notified US |
| Ecology, the state departments of Health and Ecology, the Nuclear Regulatory |
| Commission and other interested parties. Energy Northwest owns the |
| Northwest's only commercial nuclear power plant, which produces enough |
| electricity to serve a city the size of Seattle with power at a competitive |
| price. The plant is located about 10 miles north of Richland. During the |
| plant's last refueling outage, which ended in October, Energy Northwest used |
| a specialized process to clean and coat the interior of certain steam lines |
| that had become somewhat corroded during 15 years of operation. The pipe |
| was cleaned with blasting grit that became slightly radioactive. The grit |
| and the corrosion deposits removed from the pipe are considered to be |
| low-level waste. Immediately after cleaning, a metal coating was sprayed |
| onto the inside of the piping. The spray was created by melting a |
| nickel-chromium wire in an electrical arc, creating fine particles that |
| coated the walls of the piping. Some of these fine particles possibly mixed |
| with some of the used grit. The nickel-chromium wire is made of materials |
| very much like those used to make kitchen cookware. However, under certain |
| conditions nickel-chromium could be considered to be hazardous waste. When |
| the pipe cleaning-coating operation was under way, it wasn't clear to Energy |
| Northwest officials that the final waste could be classified as mixed waste. |
| In October, waste from the pipe operation was gathered and placed in four |
| metal boxes, each four feet by four feet by six feet. In December, the |
| boxes were taken to the US Ecology disposal site on the Hanford Nuclear |
| Reservation. The US Ecology site is licensed for low-level radioactive |
| waste, such as that from medical clinics. In January, an Energy Northwest |
| employee questioned whether the mixture of arc-spray residue and grit might |
| possibly be classified as mixed waste, rather than low-level waste. Energy |
| Northwest then told US Ecology it would retrieve the boxes. The boxes had |
| not yet been buried. Energy Northwest retrieved the boxes in late February. |
| A plan to sample and analyze waste is being prepared. The material will be |
| tested to determine if the waste should be classified as mixed waste. If |
| not, the boxes will be returned to US Ecology. If the waste is classified |
| as mixed waste, Energy Northwest will explore other storage and disposal |
| options." |
| |
| The licensee notified Washington State Officials and plan to notify the NRC |
| Resident Inspector. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36766 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PADUCAH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/07/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 20:33[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/07/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 02:32[CST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/07/2000|
| CITY: PADUCAH REGION: 3 +-----------------------------+
| COUNTY: McCRACKEN STATE: KY |PERSON ORGANIZATION |
|LICENSE#: GDP-1 AGREEMENT: Y |ROGER LANKSBURY R3 |
| DOCKET: 0707001 |THOMAS ESSIG NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: ERIC WALKER | |
| HQ OPS OFFICER: DICK JOLLIFFE | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NCFR NON CFR REPORT REQMNT | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| - C-333A AUTOCLAVE WATER INVENTORY CONTROL SYSTEM PRIMARY CONDENSATE ALARM |
| RECD - |
| |
| At 0232 CST on 03/07/00, the Plant Shift Superintendent (PSS) was notified |
| that a primary condensate alarm was received on the C-333A Position 2 South |
| autoclave Water Inventory Control (WIC) System. The WIC System is required |
| to be operable while heating in Mode 5 according to TSR 2.2.4.2. The |
| autoclave was checked according to the alarm response procedure, removed |
| from service, and the WIC System was declared inoperable by the PSS. |
| |
| Troubleshooting was Initiated and is continuing in order to determine the |
| reason for the alarm. |
| |
| The safety system actuation is reportable to the NRC as required by Safety |
| Analysis Report, Section 6.9, Table 1, Criterion J.2, Safety System |
| Actuation due to a valid signal as a 24-hour event notification. |
| |
| The NRC resident Inspector has been notified of this event. |
| |
| PGDP Problem Report No, ATR-00-1340; PGDP Event Report No, PAD-2000-020. |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
|Fuel Cycle Facility |Event Number: 36767 |
+------------------------------------------------------------------------------+
+------------------------------------------------------------------------------+
| FACILITY: PORTSMOUTH GASEOUS DIFFUSION PLANT |NOTIFICATION DATE: 03/08/2000|
| RXTYPE: URANIUM ENRICHMENT FACILITY |NOTIFICATION TIME: 02:37[EST]|
| COMMENTS: 2 DEMOCRACY CENTER |EVENT DATE: 03/07/2000|
| 6903 ROCKLEDGE DRIVE |EVENT TIME: 10:38[EST]|
| BETHESDA, MD 20817 (301)564-3200 |LAST UPDATE DATE: 03/08/2000|
| CITY: PIKETON REGION: 3 +-----------------------------+
| COUNTY: PIKE STATE: OH |PERSON ORGANIZATION |
|LICENSE#: GDP-2 AGREEMENT: N |ROGER LANKSBURY R3 |
| DOCKET: 0707002 | |
+------------------------------------------------+ |
| NRC NOTIFIED BY: KURT SISLER | |
| HQ OPS OFFICER: DOUG WEAVER | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NBNL RESPONSE-BULLETIN | |
| | |
| | |
| | |
| | |
+------------------------------------------------------------------------------+
EVENT TEXT
+------------------------------------------------------------------------------+
| BULLETIN 91-01 24 HOUR REPORT |
| |
| At 1038 hours on 3/7/00, was discovered that a 5 gallon bucket containing |
| used, potentially contaminated oil was spaced less than 2 feet from another |
| like container. The two containers were 23 inches apart rather than the |
| minimum 24 inches required by NCSA-PLANTO45.AO1 requirement #5. This |
| spacing violation constitutes the loss of one control of the double |
| contingency principle. The spacing violation was corrected at 1055 hours. |
| A walk-down of the affected area verified that no other spacing issues |
| exist. |
| |
| The licensee notified the NRC resident inspector. |
+------------------------------------------------------------------------------+
Page Last Reviewed/Updated Thursday, March 25, 2021
Page Last Reviewed/Updated Thursday, March 25, 2021