ENS 46353
ENS Event | |
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14:58 Oct 22, 2010 | |
Title | Spent Fuel Storage Related Defect - Cask Leakage Rate Greater than Technical Specification |
Event Description | On 10/22/10, at 1058 EDT, a troubleshooting of Independent Spent Fuel Storage Installation (ISFSI) Cask TN-50-A indicated that a leak existed in the cask lid sealing area at a rate greater than allowed by ISFSI Cask Technical Specification (TS) Section 3.1.3, Cask Helium Leak Rate. TS 3.1.3 limits the Cask Helium Leak Rate to 1.0 E-05 ref-cc/sec. The cask is currently in unloading operations and is located within the Peach Bottom Atomic Power Station Unit 3 containment building. Preliminary review indicates that a leak exists at the weld plug that provides sealing of the drilled interseal passageway associated with the drain port penetration of the cask lid. This leak effectively provides a bypass of the main lid outer confinement seal.
This report if being submitted pursuant to 10CFR72.75(c)(1) as a result of a material defect in a weld in the cask main lid. This report is also being submitted pursuant to 10CFR72.75 (c) (2) as a result of a resolution in the effectiveness of the cask confinement system. The Certificate of Compliance for this cask is 1027 (Amendment 1). The NRC Resident Inspector has been informed of this notification.
On 10/27/10, at 1107 [EDT], troubleshooting of Independent Spent Fuel Storage Installation (ISFSI) Cask TN-68-01 identified that a helium leak exists in the cask lid sealing area at a leak rate greater than allowed by ISFSI Cask Technical Specification Section 3.1.3, Cask Helium Leak Rate. TS 3.1.3 limits the Cask Helium Leak Rate to 1.0 E-O5 ref-cc/sec. The cask was in LOADING OPERATIONS and is currently located within the [Peach Bottom Atomic Power Station] PBAPS Unit 2 containment building. Preliminary review indicates that a leak exists in the Cask Main Lid Outer Closure Seal. The cask will be repaired and tested prior to returning the cask to the Independent Spent Fuel Storage Installation (ISFSI). No release of radiation occurred as a result of this issue. This report is being submitted pursuant to 10CFR 72.75(c)(2) as a result of a reduction in the effectiveness of the cask confinement system. The Certificate of Compliance for this cask is 1027 (Amendment 0). The NRC Resident Inspector has been informed. Notified R1DO (Caruso), NRR EO (Thorp), NMSS EO (Lorson), and IRD (Grant). |
Where | |
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Peach Bottom Pennsylvania (NRC Region 1) | |
Reporting | |
10 CFR 72.75(c )(1), ISFSI Defect 10 CFR 72.75(c )(2), ISFSI Degradation | |
Time - Person (Reporting Time:+1.9 h0.0792 days <br />0.0113 weeks <br />0.0026 months <br />) | |
Opened: | Brad Deihl 16:52 Oct 22, 2010 |
NRC Officer: | Eric Simpson |
Last Updated: | Oct 27, 2010 |
46353 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 3 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 463732010-10-27T15:07:00027 October 2010 15:07:00
[Table view]10 CFR 72.75(c)(2), ISFSI Degradation Spent Fuel Storage Related Defect - Cask Leakage Rate Greater than Technical Specification ENS 463532010-10-22T14:58:00022 October 2010 14:58:00 10 CFR 72.75(c)(1), ISFSI Defect, 10 CFR 72.75(c)(2), ISFSI Degradation Spent Fuel Storage Related Defect - Cask Leakage Rate Greater than Technical Specification 2010-10-27T15:07:00 | |