ENS 56221
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ENS Event | |
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11:30 Nov 14, 2022 | |
Title | Reactor Coolant System (RCS) Pressure Boundary Degraded |
Event Description | The following information was provided by the licensee via email:
During a scheduled refueling outage, a walkdown inside containment discovered a small amount of boron on the 1B2 Reactor Coolant Pump (RCP) lower bearing temperature instrument. At 0730 EST on November 14, 2022, with Unit 1 in Mode 6, disassembly of the instrument indicated the source of the boron was from a leak in the thermowell. The thermowell is considered part of the reactor coolant system pressure boundary and as such the condition is reportable. Repairs for the condition are in progress. This event is being reported as an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. |
Where | |
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Oconee ![]() South Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+1.58 h0.0658 days <br />0.0094 weeks <br />0.00216 months <br />) | |
Opened: | Paul Marshall 13:05 Nov 14, 2022 |
NRC Officer: | Donald Norwood |
Last Updated: | Nov 14, 2022 |
56221 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (0 %) |
After | Power Operation (0 %) |
WEEKMONTHYEARENS 562212022-11-14T11:30:00014 November 2022 11:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (RCS) Pressure Boundary Degraded ENS 561972022-11-01T18:33:0001 November 2022 18:33:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (RCS) Pressure Boundary Degraded ENS 495272013-11-11T10:20:00011 November 2013 10:20:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 1 Commenced a Technical Specification Required Shutdown Due to Rcs Leakage ENS 426412006-06-14T18:00:00014 June 2006 18:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Leaking Decay Heat Removal Isolation Valve Bypass Line ENS 414132005-02-16T18:31:00016 February 2005 18:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Reactor Building Normal Sump Level Increasing 2022-11-14T11:30:00 | |
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