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Event Notification Report for January 6, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/05/2004 - 01/06/2004

** EVENT NUMBERS **


40305 40420 40425 40426

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 40305
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL HARRIS
HQ OPS Officer: JEFF ROTTON
Notification Date: 11/10/2003
Notification Time: 00:39 [ET]
Event Date: 11/09/2003
Event Time: 23:15 [EST]
Last Update Date: 01/05/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
STEPHEN CAHILL (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Standby 0 Hot Standby

Event Text

SEQUOYAH UNIT 2 AUXILIARY FEEDWATER ACTUATION DURING OUTAGE

"On 11/9/03 at 2315 [EST], with Unit 2 in Mode 3 in preparation for a Refueling Outage, an unanticipated ESF actuation occurred. With one Main Feedwater Pump (MFP) reset and one MFP tripped per the General Operating Procedures, Main Condenser Vacuum was being broken. Low Condenser vacuum caused the trip of the reset MFP. The signal for trip of two MFPs caused an Aux Feedwater (AFW) start. AFW was in service in manual control per procedure when the start signal was received; however, the start signal caused the Level Control Valves (LCVs) to reposition to their accident position."


The licensee notified the NRC Resident Inspector.

* * * RETRACTION PROVIDED BY B HARRIS TO JEFF ROTTON AT 1442 EST ON 01/05/04 * * *

"On November 9, 2003, after the planned Unit 2 reactor shutdown for refueling outage number 12, an auxiliary feedwater system start signal was initiated. During the shutdown, the auxiliary feedwater pumps (AFW) were started and both main feedwater pumps (MFP) had been tripped. Following transition from emergency operating procedure to the normal plant shutdown procedure, the feedwater isolation signal and one MFP trip were reset to allow shutdown of the turbine-driven pump, in accordance with plant procedures. As a result of the reactor coolant temperature decreasing below 540 degrees Fahrenheit, emergency boration was performed, and subsequently, control room personnel closed the main steam isolation valves (MSIVs) to limit cooldown of the RCS. After closure of the MSIVs, Operations personnel broke main condenser vacuum in accordance with plant procedures. The operators knew by their procedure that this would result in a low-condenser vacuum trip signal to the reset MFP trip bus and, with both MFPs trip bus tripped, the logic would be completed for initiation of an AFW start signal. The procedure states 'Breaking main condenser vacuum will cause loss of main feed pump turbine condenser vacuum to both MFPs resulting in an ESF actuation.'

"On November 10, 2003, at 0039 Eastern standard time, NRC was notified in accordance with 10 CFR 50.72 (b)(3)(iv)(A) of the ESF actuation (event notification No. 40305).

"10 CFR 50.72 and 50.73 requires reporting of any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. NUREG 1022 states that the intent is to require reporting of actuations of systems that mitigate the consequences of significant events. The breaking of the condenser vacuum was driven by plant conditions. However, the start signal to the AFW system was not to mitigate an event for the condition the plant was in (i.e., both MFPs had been secured and decay heat was being controlled by AFW in accordance with normal operating procedures) and is therefore considered a preplanned event.

"Based on the above information, the initiation of the AFW start signal is not reportable and the notification is being withdrawn."

The licensee has notified the NRC Resident Inspector. Notified R2DO(Ayres)

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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 inch by 4 inch hole through the 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 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"

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Power Reactor Event Number: 40425
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: THAD REAMES
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 01/05/2004
Notification Time: 12:47 [ET]
Event Date: 01/05/2004
Event Time: 09:30 [EST]
Last Update Date: 01/05/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
DAVID AYRES (R2)

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

LICENSEE MANAGER TESTED POSITIVE FOR ALCOHOL ON A RANDOM TEST

Contact HOO for additional information

The NRC Resident Inspector will be informed.

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Power Reactor Event Number: 40426
Facility: HADDAM NECK
Region: 1 State: CT
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: CHARLIE REID
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/05/2004
Notification Time: 17:08 [ET]
Event Date: 01/05/2004
Event Time: 08:00 [EST]
Last Update Date: 01/05/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
26.73 - FITNESS FOR DUTY
Person (Organization):
JAMES NOGGLE (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Decommissioned 0 Decommissioned

Event Text

PLANT ACCESS TERMINATED DUE TO POSITIVE FITNESS FOR DUTY TEST

A contractor employee was given an Administrative positive FFD test result due to not showing up for a random FFD test and leaving the site without completing the test. The employee's access to the plant has been terminated. Contact the HOO for additional details.

The licensee notified the NRC Resident Inspector and Connecticut DEP.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012