| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/26/2009 - 08/27/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 45288 | Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: JANX INTEGRITY GROUP
Region: 1
City: REIDSVILLE State: NC
County:
License #: 085-1117-1
Agreement: Y
Docket:
NRC Notified By: HENRY BARNES
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/24/2009
Notification Time: 13:29 [ET]
Event Date: 06/01/2009
Event Time: [EDT]
Last Update Date: 08/24/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JOHN WHITE (R1DO)
LARRY CAMPER (FSME)
| Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE STUCK OUTSIDE CAMERA
"On June 1, 2009, licensee personnel were performing radiography when the projector fell on the guide tube while the source was exposed, preventing the source from being retracted into the shield. Licensee personnel tried to retract the source but were unsuccessful. The area was secured and monitored until a source retrieval team could be assembled and arrive on site. On June 2, 2009, the source retrieval team arrived and performed the source retrieval. The damaged guide tube was replaced and tested and the camera operates properly. The radiographer received 325 mRem by dosimeter and the radiographer's assistant received 38 mRem. No overexposure is anticipated.
"The incident was reported to the Agency within the 30 day reporting time. However, the received report was misplaced until August 24, 2009.
"Incident Number: 09-40
"NMED Number: NC090040" |
| Power Reactor | Event Number: 45299 | Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-2
NRC Notified By: JOSHUA SISAK
HQ OPS Officer: VINCE KLCO | Notification Date: 08/25/2009
Notification Time: 21:15 [ET]
Event Date: 08/25/2009
Event Time: 19:35 [EDT]
Last Update Date: 08/26/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JOHN WHITE (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 OFFSITE NOTIFICATION DUE TO A WATER LEAK CONTAINING TRITIUM
"Oyster Creek Nuclear Generating Station notified the New Jersey Department of Environmental Protection of a leak of water containing tritium from an underground condensate transfer pipe at the turbine building penetration of less than 20 gpm and concentration of approximately 10 million picocuries/milliliter.
"The leaking water is being pumped to storage drums and a plan is being developed to replace the six-inch condensate transfer piping which penetrates the turbine building inside a 42 Inch long sixteen inch diameter penetration sleeve. Previously, water was observed coming from the sleeve into the turbine building where it was draining to a sump. The leak coming out of the turbine building was uncovered during excavation to determine if the condensate was leaking to the soil."
The licensee notified the NRC Resident Inspector.
* * * UPDATE PROVIDED BY CALVIN TAYLOR TO JASON KOZAL AT 0907 ON 08/26/09 * * *
The licensee corrected the reported concentration to 10 million picocuries/liter.
Additionally, after closer examination the leak rate was determined to be approximately 5 GPM vice the initially reported less than 20 GPM.
The licensee will be issuing a press release.
Notified the R1DO (White). |
| Power Reactor | Event Number: 45300 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN COVINGTON
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/26/2009
Notification Time: 09:20 [ET]
Event Date: 08/26/2009
Event Time: 09:00 [EDT]
Last Update Date: 08/26/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MALCOLM WIDMANN (R2DO)
|
| 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 RESPONSE CAPABILITY DUE TO MAINTENANCE RENDERING TSC NON-FUNCTIONAL
"The TSC Air Handling Unit will be taken OOS to repair one of the two compressors. In order to perform this corrective maintenance, the TSC HVAC will be removed from service for [approximately] 1 hour to disconnect the compressor to be repaired and in doing so will render the TSC HVAC inoperable which renders the TSC as non-functional. The TSC HVAC will be restarted to return the TSC to an operable and functional status. The work to repair or replace the compressor is planned to be completed within (1-3 days). After the work is completed, the system will be taken out of service again to reconnect the compressor ([approximately] 1 hr) and return the TSC HVAC to service."
The licensee notified the NRC Resident Inspector. |
| Fuel Cycle Facility | Event Number: 45302 | Facility: PADUCAH GASEOUS DIFFUSION PLANT
RX Type: URANIUM ENRICHMENT FACILITY
Comments: 2 DEMOCRACY CENTER
6903 ROCKLEDGE DRIVE
BETHESDA, MD 20817 (301)564-3200
Region: 2
City: PADUCAH State: KY
County: McCRACKEN
License #: GDP-1
Agreement: Y
Docket: 0707001
NRC Notified By: BILLY WALLACE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/26/2009
Notification Time: 16:19 [ET]
Event Date: 08/25/2009
Event Time: 21:40 [CDT]
Last Update Date: 08/26/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
MALCOLM WIDMANN (R2DO)
JACK GUTTMANN (NMSS)
| Event Text AUTOCLAVE PRESSURE RELIEF SYSTEM INOPERABLE
"On 08-25-09, the Plant Shift Superintendent (PSS) was notified that C-360 (Toll Transfer & Sampling Building) Autoclave #4 had a failure in the autoclave pressure relief system. The autoclave pressure relief system utilizes a rupture disc in series with a relief valve. A pressure indicator is located between the rupture disc and the relief valve to verify that the pressure between the two devices is less than 5 psig per TSR 2.1.3.2 Condition A. This pressure is limited to prevent any significant bias to the actuation pressure of the rupture disc. TSR 2.1.3.2 requires that the actuation pressure of the autoclave pressure relief system shall not exceed 157.5 psig. On 08-25-09 at 2140 CDT, an operator was preparing to place the #4 autoclave into service, per the proper operating procedure, when the pressure between the rupture disc and the relief valve was found to be 5.5 psig, a pressure which indicated a failure in this required safety system. The autoclave was in a mode where this TSR system is required to be operable. There is low safety significance to this failure as the TSR does allow the current operating cycle to be completed under this condition.
"Since the operating cycle was just started and steam had not been applied to the autoclave, the operating evolution was abandoned and the autoclave was declared inoperable and taken out of service.
"This event is reportable as a 24 hour event in accordance with 10CFR 76.120(c)(2)(i). This is an event in which equipment is disabled or fails to function as designed when: a.) the equipment is required by a TSR to prevent releases, prevent exposures to radiation and radioactive materials exceeding specified limits, mitigate the consequences of an accident, or restore this facility to a pre-established safe condition after an accident; b.) the equipment is required by a TSR to be available and operable and either should have been operating or should have operated on demand, and c.) no redundant equipment is available and operable to perform the required safety function. The NRC Resident Inspector has been notified of this event.
"PGDP Assessment and Tracking Report No. ATRC-09-2084; PGDP Event Report No. PAD-2009-12; Worksheet No. Responsible Division: Operations" | |