Event Notification Report for June 16, 2004
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/15/2004 - 06/16/2004
EVENT NUMBERS
40820408214082241170
Power Reactor
Event Number: 40820
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MIKE GUILL
HQ OPS Officer: JEFF ROTTON
Region: 2 State: VA
Unit: [1] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MIKE GUILL
HQ OPS Officer: JEFF ROTTON
Notification Date: 06/16/2004
Notification Time: 10:11 [ET]
Event Date: 06/16/2004
Event Time: 09:45 [EDT]
Last Update Date: 06/16/2004
Notification Time: 10:11 [ET]
Event Date: 06/16/2004
Event Time: 09:45 [EDT]
Last Update Date: 06/16/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ROBERT HAAG (R2)
ROBERT HAAG (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 |
LOSS OF EMERGENCY ASSESSMENT CAPABILITY
"At 0945 on 6/16/04, the uninterruptible power supply to the Technical Support Center was removed from service for pre-planned maintenance. As a result, the plant Safety Parameter Display System (SPDS) and the Technical Support Center (TSC) computer system are inoperable. This event is a major loss of emergency assessment capability and is reportable under 10CFR50.72(b)(3)(xiii). The expected duration of the maintenance is between 4 and 8 hours."
This pre-planned maintenance also made the ERDS inoperable.
The Licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 06/16/04 @ 1707 BY MIKE GUILL TO C GOULD * * * UPDATE
SPDS and the TSC computer were returned to service at 17:04 on 06/16/04.
The NRC Resident Inspector will be notified.
"At 0945 on 6/16/04, the uninterruptible power supply to the Technical Support Center was removed from service for pre-planned maintenance. As a result, the plant Safety Parameter Display System (SPDS) and the Technical Support Center (TSC) computer system are inoperable. This event is a major loss of emergency assessment capability and is reportable under 10CFR50.72(b)(3)(xiii). The expected duration of the maintenance is between 4 and 8 hours."
This pre-planned maintenance also made the ERDS inoperable.
The Licensee has notified the NRC Resident Inspector.
* * * UPDATE ON 06/16/04 @ 1707 BY MIKE GUILL TO C GOULD * * * UPDATE
SPDS and the TSC computer were returned to service at 17:04 on 06/16/04.
The NRC Resident Inspector will be notified.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 40821
Facility: PERRY
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: STEVEN BENEDICT
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: OH
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: STEVEN BENEDICT
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/16/2004
Notification Time: 15:52 [ET]
Event Date: 06/16/2004
Event Time: 14:00 [EDT]
Last Update Date: 08/16/2004
Notification Time: 15:52 [ET]
Event Date: 06/16/2004
Event Time: 14:00 [EDT]
Last Update Date: 08/16/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
PATRICK LOUDEN (R3)
PATRICK LOUDEN (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
24 HOUR NOTIFICATION OF PLANT EXCEEDING ITS POWER LIMIT
At 1400 hours on June 16, 2004, it was confirmed that the plant had operated in excess of its licensed maximum power limit of 3758 megawatts thermal by about two (2) megawatts thermal. The power limit was determined to have been exceeded due to a feedwater temperature RTD being replaced on May 24, 2004, without having installed a matching transmitter. This error caused a non-conservative input into the core power calculation resulting in a small error. The error allowed the power to be about two (2) megawatts above the limit while indicating that it was within requirements. This condition occurred during two periods on 06/14/04 and 06/15/04. On 06/14/04 the first occurrence lasted for approximately 7 hours. The second occurrence lasted for 16 hours commencing on 06/14/04 and terminating on 06/15/04. The licensee identified this condition on 06/15/04 @ 1130 and the condition was corrected on 06/15/04 @ 1315.
This notification is being submitted in accordance with PNPP Operating License Condition 2.F, as a potential violation of the Maximum Power Level specified in PNPP Operating License
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM K Russell to W Gott at 1356 on 8/16/04 * * *
"A 24 hour notification was made on June 16, 2004, in accordance with [Perry Nuclear Power Plant] PNPP Operating License Condition 2.F, a potential violation of the maximum power level specified in PNPP Operating License Condition 2.C(1). At the time of discovery, maximum licensed power level was determined to have been exceeded by about 2 megawatts thermal as a result of a feedwater resistance temperature detector (RTD) being replaced without installing a matching transmitter. The feedwater temperature provided by this RTD provides an input to the core power calculation and was initially determined to have caused an error in the calculation of about 3.1 megawatts.
"Subsequently, as-found calibration data was taken that determined the RTD loop error was smaller than initially calculated. The resultant error in thermal power was calculated to be 0.1 megawatts. Review of the power history using the recalculated thermal power error resulted in a determination that the maximum licensed power level was not exceeded. Since the maximum licensed power level was not exceeded, this notification retracts ENF 40821. This retraction was discussed with the Resident NRC Inspector."
Notified R3DO (Clayton)
At 1400 hours on June 16, 2004, it was confirmed that the plant had operated in excess of its licensed maximum power limit of 3758 megawatts thermal by about two (2) megawatts thermal. The power limit was determined to have been exceeded due to a feedwater temperature RTD being replaced on May 24, 2004, without having installed a matching transmitter. This error caused a non-conservative input into the core power calculation resulting in a small error. The error allowed the power to be about two (2) megawatts above the limit while indicating that it was within requirements. This condition occurred during two periods on 06/14/04 and 06/15/04. On 06/14/04 the first occurrence lasted for approximately 7 hours. The second occurrence lasted for 16 hours commencing on 06/14/04 and terminating on 06/15/04. The licensee identified this condition on 06/15/04 @ 1130 and the condition was corrected on 06/15/04 @ 1315.
This notification is being submitted in accordance with PNPP Operating License Condition 2.F, as a potential violation of the Maximum Power Level specified in PNPP Operating License
The licensee notified the NRC Resident Inspector.
* * * RETRACTION FROM K Russell to W Gott at 1356 on 8/16/04 * * *
"A 24 hour notification was made on June 16, 2004, in accordance with [Perry Nuclear Power Plant] PNPP Operating License Condition 2.F, a potential violation of the maximum power level specified in PNPP Operating License Condition 2.C(1). At the time of discovery, maximum licensed power level was determined to have been exceeded by about 2 megawatts thermal as a result of a feedwater resistance temperature detector (RTD) being replaced without installing a matching transmitter. The feedwater temperature provided by this RTD provides an input to the core power calculation and was initially determined to have caused an error in the calculation of about 3.1 megawatts.
"Subsequently, as-found calibration data was taken that determined the RTD loop error was smaller than initially calculated. The resultant error in thermal power was calculated to be 0.1 megawatts. Review of the power history using the recalculated thermal power error resulted in a determination that the maximum licensed power level was not exceeded. Since the maximum licensed power level was not exceeded, this notification retracts ENF 40821. This retraction was discussed with the Resident NRC Inspector."
Notified R3DO (Clayton)
Power Reactor
Event Number: 40822
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE MEYER
HQ OPS Officer: CHAUNCEY GOULD
Region: 3 State: WI
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE MEYER
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/16/2004
Notification Time: 18:27 [ET]
Event Date: 06/16/2004
Event Time: 14:59 [CDT]
Last Update Date: 06/16/2004
Notification Time: 18:27 [ET]
Event Date: 06/16/2004
Event Time: 14:59 [CDT]
Last Update Date: 06/16/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
PATRICK LOUDEN (R3)
HERB BERKOW (NRR)
TOM ANDREWS (IRO)
PATRICK LOUDEN (R3)
HERB BERKOW (NRR)
TOM ANDREWS (IRO)
| 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 |
EMERGENCY SIRENS INADVERTENTLY ACTIVATED
During a weekly growl test of the Point Beach Nuclear Plant (PBNP) emergency sirens on June 16, 2004, the Manitowoc County sirens were inadvertently activated at 1459 CDT. PBNP is investigating the cause of this event. The sirens were activated for approximately one minute. As a result of the inadvertent actuation, the Village of Mishicot, the City of Two Rivers, Manitowoc County, and Kewaunee County, Wisconsin were notified. There was no impact to the plant as a result of the activation of the sirens. The alert notification system remains operable. This report is being submitted in accordance with 10 CFR 50.72(b)(2)(xi) as a result of the notifications made.
The Resident Inspector was notified
During a weekly growl test of the Point Beach Nuclear Plant (PBNP) emergency sirens on June 16, 2004, the Manitowoc County sirens were inadvertently activated at 1459 CDT. PBNP is investigating the cause of this event. The sirens were activated for approximately one minute. As a result of the inadvertent actuation, the Village of Mishicot, the City of Two Rivers, Manitowoc County, and Kewaunee County, Wisconsin were notified. There was no impact to the plant as a result of the activation of the sirens. The alert notification system remains operable. This report is being submitted in accordance with 10 CFR 50.72(b)(2)(xi) as a result of the notifications made.
The Resident Inspector was notified
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
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: 00:00 [EST]
Last Update Date: 11/05/2004
Notification Time: 11:21 [ET]
Event Date: 06/16/2004
Event Time: 00:00 [EST]
Last Update Date: 11/05/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
DAVID SILK (R1)
JOHN HICKEY (NMSS)
DAVID SILK (R1)
JOHN HICKEY (NMSS)
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).
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).