ENS 48348
ENS Event | |
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19:15 Sep 26, 2012 | |
Title | Technical Specification 3.0.3 Entered Due to Surveillance Testing Not Being Completed as Required |
Event Description | Pressurizer Pressure LO Instrument surveillance testing was discovered to not have been completed as required. Existence of an internal jumper on solid state protection system input to logic cards prevented complete circuit testing. Unit 1 and unit 2 entered Technical Specification [TS] 3.0.3 at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />.
Alternate method of surveillance testing on one of the trains was completed and TS 3.0.3 was exited on Unit 1 at 2203 EDT and Unit 2 at 2132 EDT. The licensee plans to complete surveillance testing on the second train before 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on 9/27/12. The licensee is currently in TS 3.3.2. The licensee has notified the NRC Resident Inspector. The states of North Carolina and South Carolina will be notified. Local county governments of York, Gaston, and Mecklenberg counties will also be notified.
Catawba nuclear station is retracting EN #48348 for both units 1 and 2 based on completion of testing and investigation of system operability. The testing determined that both units respective train 'A' and 'B' pressurizer pressure low were operable and would have functioned as needed. This condition is not reportable under 10 CFR 50.72(b)(3)(ii)(B) and 10 CFR 50.72(b)(3)(v)(D). The licensee has notified the NRC Resident Inspector. R2DO (O'Donohue) notified. |
Where | |
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Catawba ![]() South Carolina (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
Time - Person (Reporting Time:+3.2 h0.133 days <br />0.019 weeks <br />0.00438 months <br />) | |
Opened: | Brian Haynes 22:27 Sep 26, 2012 |
NRC Officer: | Dong Park |
Last Updated: | Oct 4, 2012 |
48348 - NRC Website
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Unit 1 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 2 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |