ENS 53287
ENS Event | |
|---|---|
20:16 Mar 25, 2018 | |
| Title | Control Rod Drive Piping Potentially Inoperable |
| Event Description | On March 25, 2018 at 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br /> [EDT], with the reactor in cold shutdown condition, two control rod drive piping lines were determined to be potentially inoperable in the event of a design basis earthquake due to support defects. The control rod drive piping forms a portion of the reactor coolant pressure boundary and primary containment boundary.
The supports will be repaired prior to plant startup. This event had no impact on the health and/or safety of the public. The NRC Resident Inspector has been notified. The licensee will notify the Commonwealth of Massachusetts.
The purpose of the notification is to retract ENS notification 53287 made on 03/25/18 for Pilgrim Nuclear Power Station. The previous notification reported that control rod drive (CRD) piping could be potentially inoperable in the event of a design basis earthquake, at the time of discovery, due to piping support defects. Subsequent evaluation has demonstrated that the piping was not inoperable. Specifically, after an engineering evaluation, it has been determined that the CRD Hydraulic System operability was never lost and the system was operable, although non-conforming, based on the support configuration not conforming to the pipe support drawings. The affected pipe supports have been restored or reworked to the proper design condition in accordance with the design drawings. The CRD System has subsequently been restored to a fully operable status. Notified R1DO (Jackson) and IRD MOC (Pham). |
| Where | |
|---|---|
| Pilgrim Massachusetts (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+3.45 h0.144 days <br />0.0205 weeks <br />0.00473 months <br />) | |
| Opened: | Joseph Frattasio 23:43 Mar 25, 2018 |
| NRC Officer: | Vince Klco |
| Last Updated: | Apr 13, 2018 |
| 53287 - NRC Website | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
Pilgrim with 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 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 519242016-05-12T20:47:00012 May 2016 20:47:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Deterioration of Spent Fuel Pool Rack Neutron Absorbing Material ENS 514562015-10-05T21:25:0005 October 2015 21:25:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Safe Shutdown Analysis for Fire Event - Open Item with Potential to Impact Capability to Operate Motor Operated Valves 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 472882011-09-22T18:52:00022 September 2011 18:52:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Salt Service Water Pump Inoperability During Postulated Degraded Voltage Conditions ENS 469332011-06-07T12:00:0007 June 2011 12:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Errors in Methodology Used for Emergency Core Cooling System Performance Requirements 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 | |