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Event Notification Report for March 22, 2011

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/21/2011 - 03/22/2011

** EVENT NUMBERS **


46607 46677 46688

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 46607
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD FISHER
HQ OPS Officer: PETE SNYDER
Notification Date: 02/11/2011
Notification Time: 12:35 [ET]
Event Date: 02/11/2011
Event Time: 08:45 [EST]
Last Update Date: 03/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
RONALD BELLAMY (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 100 Power Operation 100 Power Operation

Event Text

TEARS DISCOVERED IN FLEXIBLE PIPE SEALS

"On February 11, 2011, during a plant walk down, it was discovered that two flexible boots sealing two piping penetrations in the secondary containment boundary had a total of three small tears rendering them inoperable.

"Technical Specification 3.6.6.2, 'Secondary Containment,' is applicable in Modes 1, 2, 3, and 4 and was entered. Since Secondary Containment was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to control the release of radioactive material. Further engineering review will be conducted to more fully evaluate the impact on radiological controls."

No actual release occurred as a result of this condition.

The licensee notified the NRC Resident Inspector, the State of Connecticut and the Town of Waterford.


* * * RETRACTION FROM ROBERT ACQUARO TO DONALD NORWOOD AT 1503 EDT ON 3/21/2011 * * *

"On February 11, 2011, small tears were discovered on flexible boots sealing two piping penetrations in the secondary containment boundary on Millstone Power Station Unit 3. Operators made a report in accordance with 10CFR50.72(b)(3)(v)(C).

"Subsequently, an engineering evaluation has been completed that concludes that the discovered tears would not have prevented the fulfillment of the safety function of the secondary containment boundary. Therefore, the condition reported in event report 46607 is being retracted.

"The NRC Senior Resident Inspector has been notified."

Notified R1DO (Rogge).

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Power Reactor Event Number: 46677
Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [ ] [ ]
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: CHRIS WEICHLER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/17/2011
Notification Time: 00:01 [ET]
Event Date: 03/16/2011
Event Time: 16:47 [EDT]
Last Update Date: 03/17/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
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

Event Text

HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE

"On 03/16/11, at 1647 [EST], Peach Bottom Atomic Power Station Unit 2 declared the High Pressure Coolant Injection system inoperable for a condition found during testing which could cause the system to malfunction when swapping suction sources. While lined up to the suppression pool suction flow path, unsatisfactory results were obtained while venting for system fill verification, indicating potential voiding of a portion of the pump discharge piping. Unit 2 HPCI remains available while aligned to its normal suction, the condensate storage tank.

"This report is being submitted pursuant to 10CFR 50.72(b)(3)(v)(D).

"The NRC resident has been informed of this notification."

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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
Notification Date: 03/21/2011
Notification Time: 13:19 [ET]
Event Date: 03/18/2011
Event Time: [CDT]
Last Update Date: 03/21/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
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

Event Text

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."

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Thursday, March 29, 2012