ENS 50579
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ENS Event | |
|---|---|
21:08 Oct 28, 2014 | |
| Title | Reactor Building Vacuum Below Technical Specification Limit |
| Event Description | On the evening of October 28, 2014 at 1708 EDT, with James A. FitzPatrick (JAF) Nuclear Power Plant operating at 100 percent power, the Reactor Building differential pressure decreased below the JAF Technical Specification (TS) Surveillance Requirement (SR) value of at least 0.25 inches water vacuum for a period of thirty-four (34) seconds. This occurred during restoration of the Reactor Building Ventilation System (RBVS) following planned maintenance. The Reactor Building differential pressure was 0.50 inches water vacuum with the 'A' RBVS fans in-service in conjunction with the Standby Gas Treatment System (SGTS). The Reactor Building differential pressure decreased to 0.19 inches water vacuum when the SGTS was secured. The Reactor Building Vent was subsequently isolated, and the alternate 'B' RBVS fans were placed in-service; the differential pressure increased to within the required 0.25 inches water vacuum value.
The JAF TS bases associated with Secondary Containment state that, 'for Secondary Containment to be considered OPERABLE, it must have adequate leak tightness to ensure that the required vacuum can be established and maintained.' Troubleshooting activities indicated that the transient was due to a non-safety related, non-TS damper downstream of one of the 'A' RBVS fans that did not fully stroke open. The subject damper is not part of Secondary Containment, and has no safety related function. This condition did not impact the leak tightness of Secondary Containment or the ability of the associated equipment to establish and maintain the required differential pressure. Secondary Containment would have fulfilled its safety function. However, because the JAF TS SR value of 0.25 inches water vacuum was not met, Secondary Containment was considered Technical Specification INOPERABLE for a period of thirty-four (34) seconds. The Secondary Containment is considered a single-train system; therefore, this condition is reportable pursuant to 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented fulfillment of a safety function. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| LER: | 05000333/LER-2014-002 |
| Time - Person (Reporting Time:+39.95 h1.665 days <br />0.238 weeks <br />0.0547 months <br />) | |
| Opened: | Thomas Yurkon 13:05 Oct 30, 2014 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Oct 30, 2014 |
| 50579 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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 | |
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