U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
08/25/2000 - 08/28/2000
** EVENT NUMBERS **
37255 37256 37257 37258 37259 37260 37261 37262 37263
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|General Information or Other |Event Number: 37255 |
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| REP ORG: KANSAS DEPT OF HEALTH & ENVIRONMENT |NOTIFICATION DATE: 08/25/2000|
|LICENSEE: LABETTE COUNTY MEDICAL CENTER |NOTIFICATION TIME: 10:29[EDT]|
| CITY: PARSONS REGION: 4 |EVENT DATE: 08/22/2000|
| COUNTY: STATE: KS |EVENT TIME: 12:00[CDT]|
|LICENSE#: 19-B259-01 AGREEMENT: Y |LAST UPDATE DATE: 08/25/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LARRY YANDELL R4 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: THOMAS A. CONLEY | |
| HQ OPS OFFICER: JOHN MacKINNON | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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| | |
| | |
| | |
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EVENT TEXT
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| POSSIBLE OVEREXPOSURE AGREEMENT STATE REPORT |
| |
| Kansas Department of Health & Environment faxed the following information: |
| |
| "On 08/24/00 at 5 pm this office received a call from Labette Med Center |
| reporting that a nuclear medicine technologist had received an exposure |
| reported by their dosimetry vendor of 8263 mR whole body. |
| |
| "Preliminary Investigation by the dosimetry vendor indicates a possibility |
| of the exposure being to the badge and not the individual. Their |
| Investigation is ongoing. |
| |
| "Labette Med Center has performed blood work and a thyroid profile on the |
| individual and results will be provided when available." |
| |
| The State of Kansas Event Number for this report is KS000018. |
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|Transportation |Event Number: 37256 |
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| REP ORG: NORTHWOOD PANELBOARD |NOTIFICATION DATE: 08/25/2000|
|LICENSEE: NORTHWOOD PANELBOARD |NOTIFICATION TIME: 11:05[EDT]|
| CITY: MAUSTON REGION: 3 |EVENT DATE: 08/25/2000|
| COUNTY: JUNEAU STATE: WI |EVENT TIME: 05:00[CDT]|
|LICENSE#: 22-20033-01 AGREEMENT: N |LAST UPDATE DATE: 08/25/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PATRICK HILAND R3 |
| |BRIAN SMITH NMSS |
+------------------------------------------------+RADDY, NRC (DOT) NRC |
| NRC NOTIFIED BY: ROBERT CLAYPOOL |STAMBAUGH DOE |
| HQ OPS OFFICER: JOHN MacKINNON |FRANK CONGEL IRO |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NTRA TRANSPORTATION EVENT | |
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EVENT TEXT
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| TRACTOR TRAILER TRUCK CARRYING 8 SEALED SOURCES OVERTURNED ON HIGHWAY. |
| |
| Licensee, Northwood Panelboard, located in Solway, MN reported the following |
| event. |
| |
| Northwood Panelboard was shipping 8 sealed source holders, each containing |
| 100 mCi of Cs-137, in two boxes to Radiation Technology located in Odessa, |
| Texas. Vitran Express, the shipping company, informed Northwood Panelboard |
| that the shipping tractor trailer had been involved in an accident on a |
| major highway outside of Mauston, Wi. The tractor trailer is lying on its |
| side blocking traffic. Four sealed source holders are contained in each |
| padlocked crate. The crates are type A packages with a transportation index |
| of 0.1. Wisconsin HAZMAT team has been dispatched to the seen of the |
| accident. NRC Region 3 (Darrel Wiedeman & Robert Gattone) were notified |
| of this event by the licensee. |
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|Other Nuclear Material |Event Number: 37257 |
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| REP ORG: CROW BUTTE RESOURCES |NOTIFICATION DATE: 08/25/2000|
|LICENSEE: CROW BUTTE RESOURCES |NOTIFICATION TIME: 12:31[EDT]|
| CITY: CRAWFORD REGION: 4 |EVENT DATE: 08/25/2000|
| COUNTY: STATE: NE |EVENT TIME: [CDT]|
|LICENSE#: SUA 1534 AGREEMENT: Y |LAST UPDATE DATE: 08/25/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |LARRY YANDELL R4 |
| |SCOTT MOORE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: MIKE GRIFFIN | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NONR OTHER UNSPEC REQMNT | |
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EVENT TEXT
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| LEAK IN PRIMARY LINER |
| |
| The company had high conductivity on the monitor for primary liner leak |
| detection for a settling pond for ion exchanger backwash. The pond mainly |
| contains brine with some residual uranium. An investigation discovered a |
| previously repaired tear had reopened, the tear is located about 3 feet |
| above the water level. It is thought that wind action formed waves were the |
| source of the water. There is no indication of leakage past the secondary |
| liner. The company plans to continue inspecting the primary liner and will |
| lower water level further to make repairs. |
| |
| The company contacted the Nebraska Department of Environmental Quality. |
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|General Information or Other |Event Number: 37258 |
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| REP ORG: CALIFORNIA RADIATION CONTROL PRGM |NOTIFICATION DATE: 08/07/2000|
|LICENSEE: ZENECA AG MANAGEMENT |NOTIFICATION TIME: 18:22[EDT]|
| CITY: RICHMAN REGION: 4 |EVENT DATE: 09/14/1999|
| COUNTY: STATE: CA |EVENT TIME: [PDT]|
|LICENSE#: CA 0564-07 AGREEMENT: Y |LAST UPDATE DATE: 08/25/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |KRISS KENNEDY R4DO |
| |SUSAN SHANKMAN NMSS |
+------------------------------------------------+ROBETA WARREN IAT |
| NRC NOTIFIED BY: KEN PRENDERGAST | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT |
| |
| "During a routine inspection of Zeneca Ag Management, the licensee informed |
| an inspector from the California Radiation Control Program that someone may |
| have intentionally contaminated areas in laboratories B200, B202 and B204 in |
| building 96. After becoming aware of the incident on 9/14/1999, the licensee |
| changed the locks for the storage location of the carbon-14, installed locks |
| on all other refrigerators, and performed bioassays of personnel who worked |
| in these laboratories. All bioassay results were negative. No further |
| facility contaminations occurred." |
| |
| The release of this report was delayed for investigative reasons. |
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|Power Reactor |Event Number: 37259 |
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| FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 08/25/2000|
| UNIT: [1] [] [] STATE: NC |NOTIFICATION TIME: 18:16[EDT]|
| RXTYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 08/25/2000|
+------------------------------------------------+EVENT TIME: 17:30[EDT]|
| NRC NOTIFIED BY: DON BRENTON |LAST UPDATE DATE: 08/25/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|10 CFR SECTION: |KEN BARR IAT |
|DDDD 73.71 UNSPECIFIED PARAGRAPH |JOHN DAVIDSON IAT |
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+-----+----------+-------+--------+-----------------+--------+-----------------+
|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| PHYSICAL SECURITY REPORT |
| |
| Potential tampering event, immediate compensatory measures taken upon |
| discovery. Contact the NRC Operations Center for additional details. |
| |
| The licensee intends to notify the NRC Resident Inspector and the R2 |
| Security Inspector (Dave Thompson). |
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|Other Nuclear Material |Event Number: 37260 |
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| REP ORG: US STEEL, GARY WORKS |NOTIFICATION DATE: 08/26/2000|
|LICENSEE: US STEEL, GARY WORKS |NOTIFICATION TIME: 10:14[EDT]|
| CITY: GARY REGION: 3 |EVENT DATE: 08/26/2000|
| COUNTY: STATE: IN |EVENT TIME: 03:00[CDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 08/26/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |PATRICK HILAND R3 |
| |JOSEPHINE PICCONE NMSS |
+------------------------------------------------+ |
| NRC NOTIFIED BY: BRIAN CONKEL | |
| HQ OPS OFFICER: BOB STRANSKY | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NDAM DAMAGED GAUGE/DEVICE | |
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EVENT TEXT
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| TWO NUCLEAR GAUGES DISPLACED ON MANUFACTURING LINE |
| |
| Two nuclear gauges (2061T and 2061B) were displaced from their mountings on |
| the #6 East galvanizing line when a strip of sheet steel broke. These gauges |
| are both Nucleonic Data Systems model 200 devices, each containing 2.001 Ci |
| of Am-241. The sources are generally licensed under Valmet license |
| GA458-3G. |
| |
| The gauges came to rest on a roll of steel approximately one foot from their |
| mounting positions. A health physics consultant responded to the site and |
| performed surveys and wipe samples, but no damage or leakage was detected. A |
| full investigation of the event is currently being conducted. |
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|Power Reactor |Event Number: 37261 |
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| FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 08/26/2000|
| UNIT: [] [2] [] STATE: AZ |NOTIFICATION TIME: 22:37[EDT]|
| RXTYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 08/26/2000|
+------------------------------------------------+EVENT TIME: 15:39[MST]|
| NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 08/26/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |LARRY YANDELL R4 |
|10 CFR SECTION: | |
|ARPS 50.72(b)(2)(ii) RPS ACTUATION | |
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|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
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|2 A/R Y 100 Power Operation |0 Hot Standby |
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EVENT TEXT
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| AUTOMATIC REACTOR TRIP DUE TO UNEXPECTED CLOSURE OF ALL MAIN STEAM ISOLATION |
| VALVES |
| |
| "The following event description is based on information currently |
| available. If through subsequent reviews of this event, additional |
| information is identified that is pertinent to this event or alters the |
| information being provided at this time, a follow-up notification will be |
| made via the ENS or under the reporting requirements of 10CFR50.73. |
| |
| "On August 26, 2000, at approximately 15:39 MST Palo Verde Unit 2 |
| experienced an automatic reactor trip (RPS actuation) from approximately |
| 100% rated thermal power due to pressure exceeding the high pressurizer |
| pressure reactor trip setpoint. The high pressure resulted from the closure |
| of all main steam isolation valves (MSIVs) coincident with the annunciation |
| of a loss of 'A' train power to the MSIV control cabinet. The unit was at |
| normal temperature and pressure prior to the trip. All CEAs inserted fully |
| into the reactor core. No ESF actuations occurred and none were required. An |
| investigation has commenced to determine why the MSIVs closed. |
| |
| "Due to the MSIV closure, main steam safety valves lifted for a short |
| period. Operators restored reactor coolant system heat removal using |
| atmospheric dump valves and the main steam safety valves reseated. Feedwater |
| to the steam generators was initiated using the 'B' motor driven essential |
| auxiliary feedwater pump and is now maintained by the 'N' motor driven |
| non-essential auxiliary feedwater pump. |
| |
| "Safety related buses remained energized during and following the reactor |
| trip. The offsite power grid is stable. Power distribution for one of the |
| two non-safety buses did not automatically transfer to offsite power. |
| Condenser vacuum was lost and has not yet been restored, thus heat removal |
| remains via the atmospheric dump valves. Unit 2 Operations entered LCO |
| 3.4.17(A) for RCS specific activity greater than 1.0 µCi/gm. No other |
| significant LCOs have been entered as a result of this event. No major |
| equipment was inoperable prior to the event nor contributed to the event. |
| |
| "Unit 2 is stable at normal operating temperature and pressure in Mode 3. |
| The event did not result in any challenges to the fission product barrier. |
| There were no adverse safety consequences or implications as a result of |
| this event. The event did not adversely affect the safe operation of the |
| plant or the health and safety of the public. |
| |
| "Steam generator tube leakage was approximately 0.07 gpd prior to the |
| reactor trip, (0.047% of the technical specification limit. |
| |
| "RCS dose equivalent iodine was approximately 4.28E-02 µCi/gm prior to the |
| reactor trip. (4.28% of the technical specification limit.) |
| |
| "The first post-trip RCS dose equivalent iodine sample indicated 2.06 |
| µCi/ml. |
| |
| "RCS chemistry continues to be monitored." |
| |
| The licensee has notified the NRC Resident Inspector. |
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|Power Reactor |Event Number: 37262 |
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| FACILITY: SURRY REGION: 2 |NOTIFICATION DATE: 08/27/2000|
| UNIT: [1] [2] [] STATE: VA |NOTIFICATION TIME: 13:21[EDT]|
| RXTYPE: [1] W-3-LP,[2] W-3-LP |EVENT DATE: 08/27/2000|
+------------------------------------------------+EVENT TIME: 10:37[EDT]|
| NRC NOTIFIED BY: COLIN BRUCE |LAST UPDATE DATE: 08/27/2000|
| HQ OPS OFFICER: FANGIE JONES +-----------------------------+
+------------------------------------------------+PERSON ORGANIZATION |
|EMERGENCY CLASS: N/A |ROBERT HAAG R2 |
|10 CFR SECTION: |FEMA, DOE, DOA, HHS FAX |
|APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION |EPA, DOT FAX |
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|UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE |
+-----+----------+-------+--------+-----------------+--------+-----------------+
|1 N Y 100 Power Operation |100 Power Operation |
|2 N Y 100 Power Operation |100 Power Operation |
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EVENT TEXT
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| NOTIFICATION TO THE NATIONAL RESPONSE CENTER OF A CHLORINE RELEASE TO THE |
| JAMES RIVER |
| |
| The licensee discovered an overflowing containment dike around the sodium |
| bromide tank for the circulating water chemical treatment system at about |
| 0640 EDT on 8/27/00. The rate of flow was estimated at about 0.5 gpm. The |
| overflow was to the storm drain system then to the discharge canal and |
| ultimately the James River. There is no discharge limit on sodium bromide. |
| The licensee pumped the containment area down to stop the overflow and |
| placed absorption rags around the storm drain. At 0935 EDT the licensee |
| investigating the source of the overflow found that a discharge hose on a |
| sodium hypochloride pump, located in the sodium bromide tank area, had come |
| loose and the source of the overflow. The discharge limit for sodium |
| hypochloride is 13.6 gallons. The licensee estimated approximately 380 |
| gallons had actually been discharged, based on storage tank level decrease |
| and the rain water level in other containment dikes. |
| |
| The licensee notified the National Response Center (incident report #540082) |
| and the State Department of Emergency Services (DES) at 1037 EDT. The |
| National Response Center notified the US Coast Guard and the State DES |
| notified the State Department of Environmental Quality. |
| |
| The licensee intends to notify the NRC Resident Inspector. |
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|General Information or Other |Event Number: 37263 |
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| REP ORG: MARYLAND DEPT OF THE ENVIRONMENT |NOTIFICATION DATE: 08/27/2000|
|LICENSEE: TESTING TECHNOLOGY INC |NOTIFICATION TIME: 18:07[EDT]|
| CITY: WASHINGTON REGION: 1 |EVENT DATE: 08/27/2000|
| COUNTY: STATE: DC |EVENT TIME: [EDT]|
|LICENSE#: AGREEMENT: N |LAST UPDATE DATE: 08/27/2000|
| DOCKET: |+----------------------------+
| |PERSON ORGANIZATION |
| |CHRISTOPHER CAHILL R1 |
| |ROBERT HAAG R2 |
+------------------------------------------------+JOSEPHINE PICCONE NMSS |
| NRC NOTIFIED BY: RAY MANLEY | |
| HQ OPS OFFICER: FANGIE JONES | |
+------------------------------------------------+ |
|EMERGENCY CLASS: N/A | |
|10 CFR SECTION: | |
|NAGR AGREEMENT STATE | |
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EVENT TEXT
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| AGREEMENT STATE REPORT OF A POTENTIAL OVEREXPOSURE TO MEMBER OF THE PUBLIC |
| |
| Testing Technology Inc. (TTI) was conducting radiographic slab inspections |
| with a 47 Ci Co-60 source at 1100 L Street in northwest Washington, DC. |
| Right after a 'shoot' a gentleman walked out of the office next door; he had |
| gone in to do some work in his office. The individual said he had seen no |
| warnings or postings when he had entered his office area. A reenactment by |
| TTI after the area was clear indicated a field of 200 mrem/hr with an |
| estimated exposure to the individual of 16 mrem. |
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