ENS 52744
ENS Event | |
|---|---|
18:11 May 10, 2017 | |
| Title | Appendix J Local Leakage Exceeded Acceptance Criteria |
| Event Description | On Wednesday May 10, 2017, at 1411 EDT, with the reactor at 0 percent core thermal power (CTP), Pilgrim Nuclear Power Station (PNPS) was in a Refueling Outage, performing a review of Local Leak Rate Testing results, when it was concluded that PNPS had exceeded its Title 10 Code of Federal Regulations Part 50, Appendix J, Option B, Type B and C Local Leak Rate Test (LLRT) leakage criteria.
Previously, on April 22, 2017, when PNPS was performing LLRT of the High Pressure Coolant Injection (HPCI) steam exhaust line check valves, both valves failed to meet their LLRT acceptance criteria specified in plant procedures. Neither of the check valves seated acceptably. Based on the ongoing evaluation of these test exceedances, it was concluded that these test results cause the plant to exceed the overall as-found minimum path Appendix J acceptance criteria of 0.6 La (126.3 SLM [Standard Liters per Minute]). Further investigation is ongoing. This event has no impact on the health and safety of the public. The licensee has notified the NRC Senior Resident Inspector. This notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), any event or condition that resulted in the condition of the nuclear power plant, including its principle safety barriers, being seriously degraded. The licensee will notify the Commonwealth of Massachusetts Emergency Management Agency. |
| Where | |
|---|---|
| Pilgrim Massachusetts (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+3.48 h0.145 days <br />0.0207 weeks <br />0.00477 months <br />) | |
| Opened: | John Whaley 21:40 May 10, 2017 |
| NRC Officer: | Bethany Cecere |
| Last Updated: | May 10, 2017 |
| 52744 - NRC Website
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Pilgrim with 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 532872018-03-25T20:16:00025 March 2018 20:16:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Control Rod Drive Piping Potentially Inoperable ENS 527442017-05-10T18:11:00010 May 2017 18:11:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Appendix J Local Leakage Exceeded Acceptance Criteria ENS 490612013-05-23T08:55:00023 May 2013 08:55:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Primary Containment Declared Inoperable During Hpci Testing ENS 433222007-04-26T23:30:00026 April 2007 23:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition During Weld Deposit Overlay Repair ENS 402112003-10-01T08:30:0001 October 2003 08:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Vessel Boundry Leakage Found During Inspection 2018-03-25T20:16:00 | |