| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/18/2009 - 11/19/2009 ** EVENT NUMBERS ** |
 | !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! | | Power Reactor | Event Number: 45467 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: ERICK MATZKE
HQ OPS Officer: KARL DIEDERICH | Notification Date: 10/26/2009
Notification Time: 12:47 [ET]
Event Date: 10/26/2009
Event Time: 10:50 [CDT]
Last Update Date: 11/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
DALE POWERS (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text PRESSURIZER AND FEEDWATER STORAGE TANK LEVEL INDICATIONS DO NOT MEET APPENDIX R REQUIREMENTS
"During a review in preparation for converting from 10 CFR 50 Appendix R to NFPA 805, it was discovered that all of the cables for pressurizer and emergency feedwater storage tank level indications did not meet Appendix R cable requirements. A fire in Corridor 4, Corridor 26, or in Room 6 could result in a failure of level indication for these critical components. Corridors 4 and 26 were adequately addressed by existing fire watches. A fire watch was established for Room 6 upon discovery of this condition. Pressurizer level and emergency feedwater storage tank level indicators currently meet their requirements, with the established fire watches."
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM ERICK MATZKE TO DONALD NORWOOD AT 1507 ON 11/18/2009 * * *
"On October 26, 2009, Fort Calhoun reported the [above event].
"During the course of the subsequent evaluation it was determined that the pressurizer level indications do meet the 10 CFR 50 Appendix R separation requirements. There is sufficient redundancy of emergency feedwater storage tank level indications to allow proper operator response to potential plant fires. Therefore, this event is not reportable."
The licensee notified the NRC Resident Inspector.
Notified R4DO (Proulx). |
| Fuel Cycle Facility | Event Number: 45497 | Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: TONY SCHILL
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/14/2009
Notification Time: 18:43 [ET]
Event Date: 11/14/2009
Event Time: 07:30 [EST]
Last Update Date: 11/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(4) - FIRE/EXPLOSION
| Person (Organization):
MARK LESSER (R2DO)
E. WILLIAM BRACH (NMSS)
FUEL'S GROUP E-MAIL ()
| Event Text FIRE IN PROCESS GLOVE BOX
"On Saturday November 14, 2009 at approximately 0730 there was a heated high pressure release from the 5A/5B UF6 cylinder in the CDL facility Sublimation Station 3. At the time of the upset, the operators were in the process of preparing the cylinder for sublimation. They had just satisfactorily performed the valve leak checks (SOP 409 Section 56 step 5.3) and were performing the cylinder pressure test (SOP 409 Section 56 step 5.4). The cylinder was not being heated. The upset occurred when the cylinder valve was opened (step 5.4.7) to vent the cylinder to column 1D01. The release ruptured the connective teflon tubing that was enclosed in braided stainless steel. When flame was observed the operator actuated the CO2 release valve and extinguished the flame. The subsequent damage appears to be limited to: 1). Braided teflon tubing, 2). Singed area on lexan cover of the enclosure, 3). Possible leak on the inlet and outlet side of the eductor.
"Of note, column 1D01 was filled with DI water in preparation for startup. The solution should have a clear appearance but has been discolored by the upset. It appears to have been blackened, possibly from burning Teflon.
"As of 1200 PM the following actions have been taken to place the system in a safe condition:
1. Building 333 personnel were notified of the event and the 301/333 door was posted with caution.
2. Immediate area is roped off.
3. All involved personnel have received incident report forms for completion.
4. A firewatch has been posted (ISA requirement as cylinder contains >7.2 kgs UF6)
5. Supervisor verified valves on UF6 cylinder are shut.
6. Nasal smears taken on all affected personnel (7 dpm max; below action limit of 90).
7. High volume air sample taken with no elevated activity identified.
8. Area sampled for HF with a Draegor Tube (negative).
9. Verified no increase on room CAM [continuous air monitor].
10. Subsequent NCS [nuclear criticality safety] evaluation identified no concerns or NCS reportability issues.
11. System has been locked out of service with operational locks and appropriate signage placed on sublimation station #3.
12. Solution on the floor from the enclosure P traps has been cleaned up.
13. The enclosure overflow traps have been filled.
14. The CO2 gage has been verified functional and operations personnel are in the process of replacing the spent CO2 cylinder.
15. NDA has scanned the NaF trap (no elevated levels found).
16. Plant Superintendent took photos of equipment damage.
17. HP verified no damage to gloves.
18. Sublimation station #1 & 2 have been tagged 'Not Authorized for Use.'
19. All proper notifications made.
20. Plant Superintendent is in the process of developing a timeline of events.
"No actual exposures occurred to the workers, the public, and environment. Potential UF6 exposure to workers. However, no loss of containment occurred.
"No other structures, systems, or equipment components in the area were affected. Safety systems are operational.
"All sublimation stations have been taken out-of-service pending investigation results.
"The event is terminated. No declared emergency class.
"Notifications were made to the local county Emergency Management Coordinator and the Town of Erwin Fire Department.
"The NRC Resident Inspector has been notified." |
| General Information or Other | Event Number: 45501 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: OWENSBY & KRITIKOS
Region: 4
City: ALLIANCE State: LA
County:
License #: LA-2234-L01
Agreement: Y
Docket:
NRC Notified By: SCOTT BLACKWELL
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 11/16/2009
Notification Time: 15:53 [ET]
Event Date: 11/12/2009
Event Time: [CST]
Last Update Date: 11/16/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
PATRICE BUBAR (FSME)
| Event Text AGREEMENT STATE REPORT - PERSONNEL OVEREXPOSURE DURING RADIOGRAPHY
The following report was received via facsimile:
"On November 13, 2009 the RSO [Radiation Safety Officer] for Owensby & Kritikos (O & K), contacted LDEQ [Louisiana Department of Environmental Quality] to report an excessive exposure. O & K had a radiography crew x-raying a pressure vessel. The radiographers believed that they had cranked the source in the camera. One of the radiographers went to the camera without a survey meter to remove the source guide tube. He was trying to put the safety plug on the end of the camera, but it would not go on. At this point, he realized that the source was not in the shielded position. Instead of roping off the area and calling the RSO per their procedures, they got the source in the shielded position themselves. This occurred on November 12, 2009 and the radiographers did not tell the RSO until November 13, 2009. Both of the pocket dosimeters were off scale. The radiographers said they where wearing their rate alarm meters. The personnel monitors were sent to Landauer for emergency processing. One of the radiographers had a dose of 5.57 rem for November with a year dose of 6.67 rem. The other radiographer had a November dose of 0.45 rem and a year dose of 1.00 rem. At this time, LDEQ believes these exposures to be true exposures to the radiographers. The crew had an AEA 660B camera, s/n B1495, that had a 79 Ci Ir-192 source, s/n 57338B. The last leak test was on October 12, 2009. LDEQ has begun an investigation and will report any new information. |
| Power Reactor | Event Number: 45503 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: DON SHEEHAN
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/17/2009
Notification Time: 21:20 [ET]
Event Date: 11/17/2009
Event Time: 17:40 [EST]
Last Update Date: 11/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAYMOND MCKINLEY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF NATIONAL WEATHER SERVICE TONE ALERT RADIO SYSTEM
"At 1819 on November 17, 2009, with Nine Mile Point Unit 1 and Unit 2 operating at 100% power, [Nine Mile Point was] notified via the RECS Line by Oswego County Warning Point, that the National Weather Service Tone Alert Radio System for Nine Mile Point and James A. Fitzpatrick Nuclear Power Plants has been out of service for greater than 1 hour as of 1740 on 11/17/2009.
"This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) population for the Nine Mile Point and James A. Fitzpatrick Nuclear Power Plants. This failure meets the NRC 8-hour reporting criteria per 10 CFR 50.72(b)(3)(xiii).
"The County Alert Sirens, which also function as part of the Public Prompt Notification System, remain operable.
"The loss of the National Weather Service Tone Alert Radio System constitutes a significant loss of emergency off-site communications capability. Compensatory measures were verified to be available should the Prompt Notification System be needed. This includes the use of the hyper-reach system, which is a reverse 911 feature, available from the Oswego County 911 center. Local law enforcement personnel are also available for 'Route Alerting' of the affected areas of the EPZ.
"The event has been entered into the site's corrective action program and the NRC Resident Inspector has been notified."
See EN# 45504 for James A. Fitzpatrick Nuclear Plant.
* * * UPDATE FROM DON SHEEHAN TO JOE O'HARA AT 0432 ON 11/18/09 * * *
"At 0318 on November 18, 2009, notified via the RECS [Radiological Emergency Communication System] Line by Oswego County Warning Point that the National Weather Service Tone Alert Radio System for Nine Mile Point and James A. Fitzpatrick Nuclear Power Plants has been returned to service."
The NRC Resident Inspector has been notified.
Notified R1DO(McKinley) |
| Power Reactor | Event Number: 45504 | Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: THOMAS YURKON
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/17/2009
Notification Time: 21:35 [ET]
Event Date: 11/17/2009
Event Time: 17:40 [EST]
Last Update Date: 11/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAYMOND MCKINLEY (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF NATIONAL WEATHER SERVICE TONE ALERT RADIO SYSTEM
"At 1819 on November 17, 2009, with James A. FitzPatrick (JAF) nuclear Power Plant operating at 100% power, Oswego County Emergency Management notified JAF that the National Weather Service had notified them that the Tone Alert Radios had been out of service since 1740.
"This impacts the ability to readily notify a portion of the Emergency Planning Zone (EPZ) population for the Nine Mile Point and JAF Nuclear Power Plants. This failure meets NRC 8-hour reporting criteria per 10 CFR 50.72(b)(3)(xiii).
"The National Weather Service is currently working to determine the cause of the failure and time frame for system restoration.
"The County Alert Sirens which also function as part of the Public Prompt Notification System remain operable.
"The loss of the Tone Alert Radios constitutes a significant loss of emergency off-site communications ability. Compensatory measures have been verified to be available should the Prompt Notification System be needed. This consists of utilizing the hyper reach system which is a reverse 911 feature available from the county 911 center. Local law enforcement personnel are also available for 'Route Alerting' of the affected areas of the EPZ.
"The event has been entered into the corrective action program and the NRC Resident Inspector has been briefed and the state PSC will also be notified."
See EN# 45503 for Nine Mile Point Nuclear Plant.
* * * UPDATE FROM THOMAS YURKON TO JOE O'HARA AT 0456 ON 11/18/09 * * *
"Notified by Oswego County 911 operator that the Tone Alert radios were restored at 0318 on 11/18/09."
The NRC Resident Inspector was notified.
Notified R1DO(McKinley). |
| Power Reactor | Event Number: 45505 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: RAY SWAFFORD
HQ OPS Officer: JOE O'HARA | Notification Date: 11/18/2009
Notification Time: 03:19 [ET]
Event Date: 11/17/2009
Event Time: 20:34 [CST]
Last Update Date: 11/18/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JONATHAN BARTLEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INADVERTENT HPCI ISOLATION
"On 11/17/09 a 2034 [CST], while performing 2-SR-3.3.6.1.3(3DFT) HPCI Steam line space high temperature functional test, HPCI isolated due to B2 and A1 PCIS Channels picking up. A1 was the channel under test at the lime the isolation occurred. Following the immediate investigation it appears the isolation was due to test equipment configuration failure. This test equipment is still under investigation.
"This incident is reportable as an 8-hour ENS notification under 10CFR 5O.72 (b)(3)(v) as 'any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to:
"d. Mitigate the consequences of an accident.'
"It also requires a 60 day written report in accordance with 10CFR50.73(a)(2Xvii).
"The NRC Resident Inspector has been notified.
"SR number associated with this report: 93270."
The HPCI system has been restored to operable status. | |