ENS 53287
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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. |
| 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: | Mar 26, 2018 |
| 53287 - NRC Website
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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 | |
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