ENS 52343
ENS Event | |
|---|---|
12:45 Nov 2, 2016 | |
| Title | Residual Heat Removal Valve Inoperable for Containment Isolation |
| Event Description | During panel walkdown, it was discovered that a tag out for the 'C' Residual Heat Removal pump suction valve was active and the valve was open with its breaker open. This rendered the valve inoperable and Technical Specification 3.6.1.3 Action C for penetration with one inoperable PCIVs was entered. The action was to isolate the penetration by closing the valve within (4) hours or restore power. The event was discovered at 0845 [EDT] and the breaker was closed at 0925 [EDT]. Technical Specification 3.6.1.3 Action C (Isolate penetration within 4 hrs.) was entered at 0130 [EDT] (time breaker was opened per tagout) and exited at 0925 [EDT]. This condition of non-compliance existed from 0530 [EDT] on 11/02/16 until 0925 [EDT] on 11/02/16. This event is being reported under 10CFR50.72 (b)(3)(v)(C).
NRC Resident has been notified.
In accordance with Technical Specification (TS) 3.6.1.3, Primary Containment Isolation Valves, the TS Basis states that one or more barriers are provided for each penetration so that no single credible failure or malfunction of an active component can result in a loss of isolation or leakage that exceeds limits assumed in the safety analyses. When two or more barriers are provided, one of these barriers may be a closed system. During this event, one of the barriers in the penetration became inoperable: 'C' Residual Heat Removal (RHR) pump suction valve 10MOV-13C. After the initial NRC notification, it was confirmed that the RHR system piping is classified as a closed system outside containment. The integrity of the closed-loop RHR system is verified by monitoring the keep-full system. Since the piping is maintained full of water during normal and post-accident modes of operation, a barrier against post-accident, gaseous, containment leakage is provided. Therefore, the affected penetration could have performed its intended safety function since there was redundant equipment in the same system which was operable. This event is not reportable under 10 CFR 50.72(b)(3)(v)(C) and the original notification may be retracted. Finally, the primary containment penetration with 10MOV-13C is with a closed system and the completion time per TS 3.6.1.3 Required Action C is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The valve was restored to operable prior to exceeding this time. The licensee notified the NRC Resident Inspector. Notified the R1DO (Dentel). |
| Where | |
|---|---|
FitzPatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| Time - Person (Reporting Time:+2.83 h0.118 days <br />0.0168 weeks <br />0.00388 months <br />) | |
| Opened: | Thomas Yurkon 15:35 Nov 2, 2016 |
| NRC Officer: | John Shoemaker |
| Last Updated: | Jan 3, 2017 |
| 52343 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (70 %) |
| After | Power Operation (70 %) |
FitzPatrick with 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
WEEKMONTHYEARENS 538282019-01-16T05:00:00016 January 2019 05:00:00
[Table view]10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Secondary Containment Differential Pressure Exceeded Technical Specification Allowed Value ENS 537782018-12-05T05:00:0005 December 2018 05:00:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Three Minute Loss of Secondary Containment Vacuum ENS 523432016-11-02T12:45:0002 November 2016 12:45:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Residual Heat Removal Valve Inoperable for Containment Isolation ENS 519852016-06-07T14:30:0007 June 2016 14:30:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Both Secondary Containment Doors Open Simultaneously ENS 515792015-12-02T01:36:0002 December 2015 01:36:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Secondary Containment Inoperable Due to Secondary Containment Vacuum Being Less than Required Ts Value ENS 515122015-09-22T20:09:00022 September 2015 20:09:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Secondary Containment Differential Pressure Exceeded Technical Specification Allowed Value ENS 514092015-09-18T18:08:00018 September 2015 18:08:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Equipment Failure Results in Inoperable Secondary Containment ENS 514052015-09-17T16:20:00017 September 2015 16:20:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Brief Loss of Secondary Containment Due to Both Airlock Doors Open Simultaneously ENS 512422015-07-20T11:40:00020 July 2015 11:40:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Temporary Loss of Differential Pressure in Secondary Containment ENS 505792014-10-28T21:08:00028 October 2014 21:08:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Reactor Building Vacuum Below Technical Specification Limit 2019-01-16T05:00:00 | |