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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
01/02/2004 - 01/05/2004
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 40420 |
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: SIMPSON TACOMA KRAFT, LLC
Region: 4
City: TACOMA State: WA
County:
License #: WN-I014-1
Agreement: Y
Docket:
NRC Notified By: ARDEN C. SCROGGS
HQ OPS Officer: JOHN MacKINNON |
Notification Date: 12/31/2003
Notification Time: 15:50 [ET]
Event Date: 12/31/2003
Event Time: 12:00 [PST]
Last Update Date: 12/31/2003 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
Tom Farnholtz (R4)
LARRY CAMPER (NMSS) |
Event Text
AGREEMENT STATE REPORT: DAMAGED GAUGE
"Licensee: Simpson Tacoma Kraft, LLC
"City and State: Tacoma, Washington
"License Number: WN-I014-1
"Type of License: Fixed Gauge
"Date of Event: 31 December 2003 (when discovered by licensee
"Location of Event: 801 Portland Avenue, Tacoma, Washington
"ABSTRACT: (where, when, how, why; cause, contributing factors, corrective actions, consequences, Dept. of Health (department) on-site investigation; media attention):
"The licensed Radiation Safety Officer reported to the Department, on 31 December, he noticed that process fluids had eroded a ½ inch by 4 inch hole through the ½ inch thick gauge body where it attached to process piping. The damage was apparently confined to the device's body and the event is not considered to present an emergency at this time. The device had been in service for about 12 years and had reached the end of its useful service life. It was being removed to prepare it for disposal.
"The device is a Texas Nuclear Corp. Model 5176, Serial Number 2253, containing 7.4 gigabecquerels (200 millicuries) of Cesium 137.
"The licensee informed the department they would bolt a ½ inch metal plate to the device's attachment point, over the damaged area, to temporarily return the device to its normal level of shielding and integrity. After removal and the temporary repair, the licensee placed the device into secured storage, along with several other similar devices, in preparation for source removal and disposal in January 2004, by a service provider.
"The RSO, approved for device installation, relocation, removal from service, and surveys, reported that the device was reading 1.5 Mr/hr, contact at the damaged area, prior to the temporary repair. A similar, but undamaged, device read 1.2 Mr/hr at the same location. The RSO reported no activity from a wipe survey on the damaged device.
"The Department will perform an on-site investigation on 6 January 2004. No media attention has been attracted, yet.
"Notification Reporting Criteria: 10 CFR 31, General Domestic Licenses for Byproduct Material (damage to shielding)
"Isotope and Activity involved: Cesium 137, 7.4 gigabecquerels (200 millicuries)
"Overexposures? (number of workers/members of the public; dose estimate; body part receiving dose; consequence): N/A
"Lost, Stolen or Damaged? (mfg., model, serial number): damage confined to device body of a Texas Nuclear Corp, Model 5176 device, Serial Number 2253
"`Disposition/recovery: removed from service, temporarily repaired, secured for pending disposal
"Leak test? Wipe survey indicated no contamination, last leak test was negative
"Vehicle: (description; placards; Shipper; package type; Pkg. ID number) N/A
"Release of activity? None
"Activity and pharmaceutical compound intended: N/A
"Misadministered activity and/or compound received: N/A
"Device (HDR, etc.) Mfg., Model; computer program: See above
"Exposure (intended/actual); consequences: N/A
"Was patient or responsible relative notified? N/A
"Was written report provided? Pending
"Was referring physician notified? N/A
"Consultant used? N/A for this event" |
| Fuel Cycle Facility |
Event Number: 40423 |
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: TONY HUDSON
HQ OPS Officer: MIKE RIPLEY |
Notification Date: 01/02/2004
Notification Time: 10:03 [ET]
Event Date: 01/02/2004
Event Time: 02:30 [CST]
Last Update Date: 01/02/2004 |
Emergency Class: NON EMERGENCY
10 CFR Section:
76.120(c)(2) - SAFETY EQUIPMENT FAILURE |
Person (Organization):
DAVID AYRES (R2)
TRISH HOLAHAN (NMSS) |
Event Text
FAILURE OF AUTOCLAVE ISOLATION SYSTEM
"At 0230 on 01-02-04 the Plant Shift Superintendent (PSS) was notified of a failure of the C-360 #3 Autoclave High Pressure Isolation System. Steam was observed leaking from the autoclave head-to-shell interface between the eleven and one o'clock position shortly after initiating a cylinder heat cycle. At the time of discovery, the autoclave was in TSR [Technical Safety Requirements] mode 5 and the High Pressure Isolation System was required to be operable while in this mode. This system is designed to provide containment of the autoclave and prevent an external release of UF6 during a system breach while heating a UF6 cylinder. The PSS declared the system inoperable and TSR LCO 2.1.3.1.C1 actions were implemented to remove the autoclave from service and place it in Mode 2, "Out of Service". The event is reportable as a 24 hour event, as required by 10 CFR 76.120(c)(2)(i); An event in which equipment is disabled or fails to function as designed when 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. The equipment was required by TSR to be available and operable and no redundant equipment was available to perform the required safety function.
"The Senior NRC Resident Inspector has been notified of this event." |
| Power Reactor |
Event Number: 40424 |
Facility: OCONEE
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: SYLVESTER MONTGOMERY
HQ OPS Officer: STEVE SANDIN |
Notification Date: 01/02/2004
Notification Time: 21:30 [ET]
Event Date: 01/02/2004
Event Time: 20:38 [EST]
Last Update Date: 01/03/2004 |
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED |
Person (Organization):
DAVID AYRES (R2)
PAO-TSIN KUO (NRR)
TIM MCGINTY (IRO)
CALDWELL (FEMA)
MARK LOMBARD (NRC) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Hot Standby |
0 |
Hot Standby |
Event Text
UNIT 1 DECLARED AN UNUSUAL EVENT DUE TO 14 GPM UNIDENTIFIED RCS LEAKAGE
At 2038EST Unit 1 Control Room Operators observed and quantified unidentified RCS leakage of approximately 14 gpm based on containment sump pump operation and a corresponding decrease in VCT level. Unit 1 was preparing for startup and there were no ongoing maintenance activities at the time. The licensee declared an Unusual Event entering their emergency procedures to isolate and identify the source of the leakage. As a result, a pressurizer sample line was isolated which terminated the leakage. The licensee will remain in the Unusual Event until an investigation is completed confirming that this was the source. There was no measured increase in radiation levels/humidity inside containment or radioactive release to the environment.
At the time of the report, 3 of the 4 RCPs were operating for forced circulation with the 4th RCP secured earlier in the day during a test. All ECCS systems are available including the EDGs, if needed. Normal makeup is in service to maintain RCS inventory with MFW supplying the Generators for decay heat removal via the steam bypass to the Main Condenser.
The licensee informed state/local agencies and will inform the NRC Resident Inspector.
At 2158EST the NRC determined that this event did not require entry into the Monitoring Phase of Normal Mode.
* * * UPDATE ON 01/03/04 AT 0006 EST FROM SLYVESTER MONTGOMERY TO GERRY WAIG * * *
The licensee terminated the NOUE at 2353 hours EST on 01/02/04. The leak has been identified as coming from a relief valve flange on the pressurizer sample line. Maintenance activities are on-going to repair the leak and the reactor remains in mode 3. The licensee has notified state and local government of the NOUE termination and will be notifying the NRC Resident Inspector.
Notified R2DO (David Ayres), FEMA (Dan Sullivan), DIRO (Tim McGinty), NRR (Pao-Tsin Kuo), NRC (Thomas) |
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