Event Notification Report for March 18, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/17/2011 - 03/18/2011
EVENT NUMBERS
46688466814668446680
Power Reactor
Event Number: 46688
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: DONNA GUINN
HQ OPS Officer: CHARLES TEAL
Region: 4 State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: DONNA GUINN
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/21/2011
Notification Time: 13:19 [ET]
Event Date: 03/18/2011
Event Time: 00:00 [CDT]
Last Update Date: 03/21/2011
Notification Time: 13:19 [ET]
Event Date: 03/18/2011
Event Time: 00:00 [CDT]
Last Update Date: 03/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
GREG PICK (R4DO)
PART 21 GROUP
GREG PICK (R4DO)
PART 21 GROUP
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
DEFECTIVE KPR-14DG-125 RELAYS DISCOVERED DURING BENCH TESTING
"The following event description is based on information currently available. The condition is reported under 10 CFR 21.21(d)(3)(i).
"Part 21 Report - Potter Brumfield KRP-14DG-125 Relays, supplied by Southern Testing Services (STS) division of Argo Turboserve Corporation (ATC).
"On March 17, 2011, during bench testing of the KRP-14DG-125 Relays, Fort Calhoun Station (FCS) discovered that some of these relays were defective in that one of the contacts would not close properly after energizing and de-energizing the relay coils. If installed in the plant, the improper closure of this contact could defeat the safety function of the relays that provide a signal to the component supported by that contact. This deviation from the design specifications is reportable per 10 CFR 21. FCS does not have any of the affected relays installed in the plant.
"FCS returned the batch of relays to the vendor for further failure modes and effects evaluation and reporting.
"FCS has not provided any of these relays from our stock to any other licensee.
"The vendor and the [NRC] Resident Inspector have been notified."
"The following event description is based on information currently available. The condition is reported under 10 CFR 21.21(d)(3)(i).
"Part 21 Report - Potter Brumfield KRP-14DG-125 Relays, supplied by Southern Testing Services (STS) division of Argo Turboserve Corporation (ATC).
"On March 17, 2011, during bench testing of the KRP-14DG-125 Relays, Fort Calhoun Station (FCS) discovered that some of these relays were defective in that one of the contacts would not close properly after energizing and de-energizing the relay coils. If installed in the plant, the improper closure of this contact could defeat the safety function of the relays that provide a signal to the component supported by that contact. This deviation from the design specifications is reportable per 10 CFR 21. FCS does not have any of the affected relays installed in the plant.
"FCS returned the batch of relays to the vendor for further failure modes and effects evaluation and reporting.
"FCS has not provided any of these relays from our stock to any other licensee.
"The vendor and the [NRC] Resident Inspector have been notified."
Power Reactor
Event Number: 46681
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JIM DAIN
HQ OPS Officer: CHARLES TEAL
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JIM DAIN
HQ OPS Officer: CHARLES TEAL
Notification Date: 03/18/2011
Notification Time: 14:40 [ET]
Event Date: 03/18/2011
Event Time: 00:00 [EDT]
Last Update Date: 03/18/2011
Notification Time: 14:40 [ET]
Event Date: 03/18/2011
Event Time: 00:00 [EDT]
Last Update Date: 03/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
REBECCA NEASE (R2DO)
PART 21 GROUP
REBECCA NEASE (R2DO)
PART 21 GROUP
| 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 | N | 0 | Refueling | 0 | Refueling |
PAINT CHIPS DISCOVERED IN WOODWARD GOVERNORS
Woodward governors purchased as nuclear safety related items for use in turbine driven auxiliary feedwater pumps and emergency diesel generators, were found to have paint chips on internal surfaces. These governors were manufactured by Woodward Governor Company, Loveland, CO for use at the McGuire Nuclear Station.
The NRC Resident Inspector has been informed.
Woodward governors purchased as nuclear safety related items for use in turbine driven auxiliary feedwater pumps and emergency diesel generators, were found to have paint chips on internal surfaces. These governors were manufactured by Woodward Governor Company, Loveland, CO for use at the McGuire Nuclear Station.
The NRC Resident Inspector has been informed.
Agreement State
Event Number: 46684
Rep Org: MINNESOTA DEPARTMENT OF HEALTH
Licensee: BOISE CASCADE PAPER CORPORATION
Region: 3
City: INTERNATIONAL FALLS State: MN
County:
License #: 5011-100-36
Agreement: Y
Docket:
NRC Notified By: BRANDON JURAN
HQ OPS Officer: DONALD NORWOOD
Licensee: BOISE CASCADE PAPER CORPORATION
Region: 3
City: INTERNATIONAL FALLS State: MN
County:
License #: 5011-100-36
Agreement: Y
Docket:
NRC Notified By: BRANDON JURAN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 03/18/2011
Notification Time: 17:34 [ET]
Event Date: 03/18/2011
Event Time: 00:00 [CDT]
Last Update Date: 03/18/2011
Notification Time: 17:34 [ET]
Event Date: 03/18/2011
Event Time: 00:00 [CDT]
Last Update Date: 03/18/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
KENNETH RIEMER (R3DO)
CHRISTEPHER MCKENNEY (FSME)
KENNETH RIEMER (R3DO)
CHRISTEPHER MCKENNEY (FSME)
AGREEMENT STATE REPORT - DENSITY GAUGE STUCK SHUTTER
"The licensee Radiation Safety Officer (RSO) was performing a routine shutter check on a density gauge (Berthold model LB7440); the shutter was difficult to turn so the RSO used pliers to move the shutter to the indicated closed position. The shutter did not close. The detector on the gauge was still reading the same as when the shutter was indicated open. The RSO contacted the manufacturer and is in the process of scheduling them to service the device. The RSO tagged the gauge with a do not operate tag warning people of the problem."
"The licensee Radiation Safety Officer (RSO) was performing a routine shutter check on a density gauge (Berthold model LB7440); the shutter was difficult to turn so the RSO used pliers to move the shutter to the indicated closed position. The shutter did not close. The detector on the gauge was still reading the same as when the shutter was indicated open. The RSO contacted the manufacturer and is in the process of scheduling them to service the device. The RSO tagged the gauge with a do not operate tag warning people of the problem."
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 46680
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WAYNE HARRELSON
HQ OPS Officer: JOE O'HARA
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: WAYNE HARRELSON
HQ OPS Officer: JOE O'HARA
Notification Date: 03/18/2011
Notification Time: 05:32 [ET]
Event Date: 03/18/2011
Event Time: 01:45 [EDT]
Last Update Date: 03/30/2011
Notification Time: 05:32 [ET]
Event Date: 03/18/2011
Event Time: 01:45 [EDT]
Last Update Date: 03/30/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DON JACKSON (R1DO)
DON JACKSON (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
CONTROL ROOM BOUNDARY RENDERED INOPERABLE
"On March 17, 2011 during a control room walk-down, it was discovered that a halon bottle located in the control room was removed from its associated piping for scheduled work. The open piping penetrates the control room boundary rendering it inoperable.
"Technical Specification 3.7.6.1 'Control Room Emergency Ventilation System' is applicable in Modes 1, 2, 3, 4, 5 and 6 was entered. Since control room boundary was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to mitigate the consequences of an accident. Upon discovery the piping was capped re-establishing the control room boundary.
"Further engineering review will be conducted to more fully evaluate the impact on the control room boundary.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D)."
Offsite power is normal and all emergency diesel generators are operable. There was no increase in plant risk.
The NRC Senior Resident Inspector has been notified.
* * * UPDATE AT 1002 EDT ON 03/30/11 FROM WAYNE WOOLERY TO S. SANDIN * * *
The Licensee is retracting this report based on the following:
"On March 17, 2011 during a control room walk down at Millstone Power Station Unit 2, it was discovered that a halon bottle located in the control room was removed from its associated piping for scheduled work. Since the associated piping penetrates the control room boundary, operators declared the control room boundary inoperable. Upon discovery, the piping was capped re-establishing the control room boundary.
"Operators made a report in accordance with 10CFR50.72(b)(3)(v)(D).
"Subsequently, an engineering evaluation has been completed that concludes that the piping opening created by the removal of the halon bottle would not have prevented the fulfillment of the safety function to mitigate the consequences of an accident. Therefore, the condition reported in event report 46680 is being retracted.
"The NRC Resident Inspector has been notified."
Notified R1DO (Powell).
"On March 17, 2011 during a control room walk-down, it was discovered that a halon bottle located in the control room was removed from its associated piping for scheduled work. The open piping penetrates the control room boundary rendering it inoperable.
"Technical Specification 3.7.6.1 'Control Room Emergency Ventilation System' is applicable in Modes 1, 2, 3, 4, 5 and 6 was entered. Since control room boundary was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to mitigate the consequences of an accident. Upon discovery the piping was capped re-establishing the control room boundary.
"Further engineering review will be conducted to more fully evaluate the impact on the control room boundary.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(D)."
Offsite power is normal and all emergency diesel generators are operable. There was no increase in plant risk.
The NRC Senior Resident Inspector has been notified.
* * * UPDATE AT 1002 EDT ON 03/30/11 FROM WAYNE WOOLERY TO S. SANDIN * * *
The Licensee is retracting this report based on the following:
"On March 17, 2011 during a control room walk down at Millstone Power Station Unit 2, it was discovered that a halon bottle located in the control room was removed from its associated piping for scheduled work. Since the associated piping penetrates the control room boundary, operators declared the control room boundary inoperable. Upon discovery, the piping was capped re-establishing the control room boundary.
"Operators made a report in accordance with 10CFR50.72(b)(3)(v)(D).
"Subsequently, an engineering evaluation has been completed that concludes that the piping opening created by the removal of the halon bottle would not have prevented the fulfillment of the safety function to mitigate the consequences of an accident. Therefore, the condition reported in event report 46680 is being retracted.
"The NRC Resident Inspector has been notified."
Notified R1DO (Powell).