ENS 48696
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ENS Event | |
|---|---|
20:16 Jan 23, 2013 | |
| Title | Concurrent Loss of High Pressure Reactor Makeup Systems Capability |
| Event Description | On 1/23/2013 at 1516 [EST], Nine Mile Point 2 (NMP2) had a failure of a Reactor Building General Area temperature trip unit occur resulting in the closure of an isolation valve on the Reactor Core Isolation Cooling (RCIC) system steam supply line. Concurrent with this failure, the High Pressure Core Spray (HPCS) system was inoperable for planned surveillance testing. With both the RCIC and HPCS systems inoperable, NMP2 entered a Technical Specification Required Action to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. At 1550, the HPCS system was restored to OPERABLE. Based on the concurrent loss of the high pressure reactor makeup capability of these two systems, it was determined that the condition is reportable under section 50.72(b)(3)(v) as the following safety functions were impacted: (A) Shutdown the reactor and maintain it in a safe shutdown condition; and (D) Mitigate the consequences of an accident.
NMP2 remains in a stable condition at rated power. The offsite grid is stable with no restrictions or warnings in effect. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Nine Mile Point  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
| Time - Person (Reporting Time:+1.78 h0.0742 days <br />0.0106 weeks <br />0.00244 months <br />) | |
| Opened: | Mark Greer 22:03 Jan 23, 2013 |
| NRC Officer: | Vince Klco |
| Last Updated: | Jan 23, 2013 |
| 48696 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Nine Mile Point with 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | |
WEEKMONTHYEARENS 568102023-10-23T00:48:00023 October 2023 00:48:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Average Power Range Monitors Declared Inoperable ENS 551372021-03-13T02:02:00013 March 2021 02:02:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Reactor Recirculation Pump Trip ENS 546922020-05-03T21:50:0003 May 2020 21:50:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Main Control Room Air Treatment System Inoperable ENS 543642019-11-01T07:16:0001 November 2019 07:16:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Core Spray (Hpcs) System Inoperable ENS 541992019-08-04T21:45:0004 August 2019 21:45:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Average Power Range Monitors Declared Inoperable ENS 502962014-07-22T17:43:00022 July 2014 17:43:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Diesel Generator for High Pressure Core Spray Declared Inoperable During Surveillance Testing ENS 498592014-02-27T08:30:00027 February 2014 08:30:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Core Spray (Hpcs) System Declared Inoperable ENS 490292013-05-14T16:15:00014 May 2013 16:15:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Steam Flow Isolation Capability Identified as Non-Functional ENS 487942013-02-28T18:19:00028 February 2013 18:19:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Core Spray Pump Failure ENS 486962013-01-23T20:16:00023 January 2013 20:16:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Concurrent Loss of High Pressure Reactor Makeup Systems Capability ENS 479672012-05-25T17:22:00025 May 2012 17:22:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident De-Energization of Both Divisions of Rhr Suction Line Primary Containment Isolations Valves During Testing ENS 452842009-08-23T21:50:00023 August 2009 21:50:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Unplanned Inoperability of the High Pressure Core Spray System ENS 442062008-05-13T12:25:00013 May 2008 12:25:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to Loss of Offsite Power ENS 409202004-08-03T14:46:0003 August 2004 14:46:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident High Pressure Core Spray Rendered Inoperable Due to Faulty Test Equipment ENS 405062004-02-05T18:40:0005 February 2004 18:40:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident Emergency Diesel Generator Ventilation Exhaust Damper Covered with Snow and Ice ENS 402172003-10-03T01:00:0003 October 2003 01:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Loss of Safe Shutdown Capability Due to All Oprm Channels Being Declared Inoperable. 2023-10-23T00:48:00 | |
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