| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/05/2004 - 11/08/2004 ** EVENT NUMBERS ** |
 | Other Nuclear Material | Event Number: 41170 | Rep Org: ABBEY METAL CORPORATION
Licensee: ABBEY METAL CORPORATION
Region: 1
City: MOONACHIE State: NJ
County:
License #:
Agreement: N
Docket:
NRC Notified By: LAURA ZIEGLER
HQ OPS Officer: JEFF ROTTON | Notification Date: 11/03/2004
Notification Time: 11:21 [ET]
Event Date: 06/16/2004
Event Time: [EST]
Last Update Date: 11/05/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
DAVID SILK (R1)
JOHN HICKEY (NMSS)
| Event Text GENERAL LICENSED RADIOACTIVE MATERIAL LOST DURING BUILDING FIRE
During a fire in the licensee building on 06/16/04, a XMET model 2000 instrument, serial # 500577 was destroyed completely. The instrument probe (serial # 501888) contained two sealed sources, 20 millicuries Cd-109 and 30 millicuries Am-241. The local fire department and Hazmat team responded to the scene. The licensee RSO conducted a survey and found no contamination or radiation. NRC Region 1 office was notified on 6/30/04.
* * * UPDATE PROVIDED BY LAURA ZIEGLER TO JEFF ROTTON ON 11/05/04 AT 1115 EST * * *
Oxford Instruments voluntarily made the report for Abbey Metal Corporation on 11/03/04 after discussions with that company. The Event Notification has been updated to reflect that the Reporting Organization should be Abbey Metal Corporation, the company that owned the device destroyed in the fire under a general license. The device was originally sold to Abbey Metal Corporation by Metorex, Inc. Oxford Instruments recently purchased Metorex, Inc and was attempting to close out all previously existing open items.
Notified R1DO (Silk) and NMSS EO ( Sandra Wastler). |
| Power Reactor | Event Number: 41174 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DAN LYON
HQ OPS Officer: JOHN MacKINNON | Notification Date: 11/05/2004
Notification Time: 12:03 [ET]
Event Date: 11/05/2004
Event Time: 07:05 [EST]
Last Update Date: 11/05/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DAVID SILK (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text EMERGNECY SIRENS FOUND INOPERABLE DUE TO EQUIPMENT MALFUNCTION
"Indian Point Emergency Center (IPEC) Units 2 & 3 are making an eight-hour non-emergency notification in accordance with 10CFR50.72(b)(3)(xiii). On November 5, 2004, at 0705 hours during a routine daily check it was discovered that 88 of 156 sirens were in communication failure due to equipment malfunction that occurred at approximately 1950 hours on November 4, 2004. At 0710 hours on November 5, 2004 the equipment malfunction was corrected and all but one siren was returned to service. The one siren out of service is unrelated to the event." State and Local counties were notified of the loss of the emergency sirens.
The licensee has been notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 41175 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: CHRIS THORNELL
HQ OPS Officer: JOHN MacKINNON | Notification Date: 11/05/2004
Notification Time: 14:22 [ET]
Event Date: 11/05/2004
Event Time: 09:11 [CST]
Last Update Date: 11/05/2004 | 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 | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text INADVERTENT LOSS OF "B" TRAIN SITE POWER DURING TESTING
"At 09:11 a.m. CST on November 5, 2004, an inadvertent "B" Train Loss of Site Power occurred when the normal power supply breaker to the 1G 4160V bus opened during testing. The 1B Emergency Diesel Generator started and powered up the 1G 4160V Bus as required and the Loss of Site Power Sequencer started all "B" Train LOSP Loads as required. Abnormal Operating Procedures for the LOSP and Loss of Train "A" or "B" Train RHR were completed as required for the event. The "A" Train RHR pump was manually started to provide core cooling and circulation flow as required for Mode 6. Core alterations were in progress for reload which were suspended immediately upon the event
"Systems which did not function as required:
Upon the auto start signal for the 1B Motor Driven Auxiliary Feedwater Pump, the 4160V power supply breaker tripped open. The flag on the breaker indicated it was due to a time delay over current on one of the phases. Investigation into this problem is in progress."
Spent Fuel Pool cooling was not lost because it was being powered from "A" Train. Site power was restored to "B" Train 4160V bus at 0959 CST. An event investigation is being performed by the licensee.
The NRC Resident Inspector has been informed of this event by the licensee. |
| Power Reactor | Event Number: 41176 | Facility: SURRY
Region: 2 State: VA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: JOHN MOSCOE
HQ OPS Officer: HOWIE CROUCH | Notification Date: 11/06/2004
Notification Time: 03:17 [ET]
Event Date: 11/06/2004
Event Time: 02:52 [EST]
Last Update Date: 11/06/2004 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
STEPHEN CAHILL (R2)
JAMES LYONS (NRR)
RICHARD WESSMAN (IRD)
KEVIN BOSCOE (FEMA)
SWO (DHS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text NOTICE OF UNUSUAL EVENT DUE TO A FIRE IN THE UNIT 1 TURBINE BASEMENT
The licensee declared an Unusual Event due to an onsite fire not under control for greater than 10 minutes. The fire was in the "A" water box internal coating. Maintenance was performing cutting operations in the water box when the fire started. There were no injuries.
The fire was fought by the onsite fire brigade and outside assistance was not required. The fire lasted 18 minutes. A reflash watch has been posted.. Unit 1 was shutdown at the time of the fire and shutdown cooling was not affected nor was any safety-related equipment. Unit 2, operating at 100% power, was not affected by the fire.
The NRC did not change response mode due to this incident.
The licensee will be notifying the NRC Resident Inspector.
* * * UPDATE FROM MOSCOE TO SANDIN AT 0337 EST ON 11/06/04 * * *
The Unusual Event was terminated by the licensee at 0321 hrs. EST. The termination criteria was the fire was out and a reflash watch stationed.
Notified DHS, FEMA, IRD (Wessman), R2DO (Cahill) and NRR (Lyons). |
| Power Reactor | Event Number: 41177 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: KEVIN DAHM
HQ OPS Officer: STEVE SANDIN | Notification Date: 11/07/2004
Notification Time: 06:20 [ET]
Event Date: 11/07/2004
Event Time: 06:20 [EST]
Last Update Date: 11/07/2004 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
PATRICK LOUDEN (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text LOSS OF SPDS AND ERDS DUE TO PLANNED MAINTENANCE
"The Safety Parameter Display System (SPDS) and Emergency Response Data System (ERDS) were removed from service while implementing a planned modification to replace the Visual Annunciator System, Iso-Mimic display system, and support planned maintenance on uninterruptible power supplies. SPDS and ERDS will be returned to service in approximately 14 days. During this period, any out of service indication on the SPDS can be obtained by control board indications. The Emergency Notification System will remain operable. These conditions are reportable in accordance with 10 CFR 50.72(b)(3)(xiii). The NRC Resident inspector has been notified. The plant is in Mode 4, Reactor Coolant Temperature is 115 deg and Div. 1 RHR is in shutdown cooling." |
| Power Reactor | Event Number: 41179 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: JIM STANFORD
HQ OPS Officer: JOHN MacKINNON | Notification Date: 11/07/2004
Notification Time: 21:04 [ET]
Event Date: 11/07/2004
Event Time: 16:35 [EST]
Last Update Date: 11/07/2004 | 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 | | 1 | N | Y | 7 | Power Operation | 2 | Startup | Event Text "A" AUXILIARY FEEDWATER (AFW) PUMP MANUALLY STARTED DUE TO DECREASING STEAM GENERATOR WATER LEVEL.
"The 'A' motor driven AFW pump was manually started in response to lowering Steam Generator (SG) level. The plant was in Mode 1 with reactor power at approximately 7%, preparing for startup of the turbine generator. Steam Generator Feedwater flow to the Steam Generators was being supplied by the main feedwater system through the main feedwater regulating bypass valves operating in automatic control. The operating crew observed a lowering trend in 'C' Steam Generator level. Upon reaching the lower end of the procedurally established normal control band (time=1633), the operating crew took the following actions in accordance with plant procedures: (1) the associated feedwater regulating bypass valve was taken to manual control to attempt restoration of normal SG level, (2) the 'A' motor driven AFW pump was manually started (time= 1635) to supply AFW to the SG and (3) reactor power lowered to reduce steam demand. These actions resulted in the restoration of 'C' SG level to normal. Normal operating SG level is 57%. Lo Lo Steam Generator Level Trip occurs at 25%. The lowest SG level observed during the evolution was approximately 43%. The cause of the irregular Feedwater control is currently being investigated. The plant is currently at approximately 2.5% power with all Steam Generator levels at normal operating levels. No automatic ESF Actuations occurred. The NRC Senior Resident was informed." | |