ENS 41277
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ENS Event | |
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09:55 Dec 22, 2004 | |
Title | Reactor Scram and Eccs Injection Following Opening of Turbine Bypass Valves |
Event Description | At approximately 04:55 on December 22, 2004, Unit 2 experienced a malfunction of Electro-Hydraulic Control (EHC) system resulting in opening of main turbine bypass valves and resultant loss of reactor pressure. The reactor automatically shutdown on RPS with the completion of a Group I isolation signal (Reactor pressure 850 prig and Reactor mode switch in RUN) resulting in a closure of the Main Steam Isolation Valves (MSIVs). Reactor level lowered to (ECCS) initiation set-point of -48 inches and High Pressure Coolant Injection (HPCI) system and Reactor Core Isolation Coolant (RCIC) system automatically initiated and restored level. When reactor level lowered below the 1 inch set-point, Group II and III Primary Containment Isolation System (PCIS) signals initiated. All Unit parameters are stable and RPS/PCIS/ECCS systems performed as designed. MSIVs remain closed. Reactor level and pressure are stable with HPCI and RCIC systems in control. Group I, II, and III isolations have been reset. The EHC malfunction is presently under investigation by Station Management.
All systems functioned as required. The reactor water level is now at 23 inches and stable and the licensee is conducting a slow depressurization to Mode 4 to investigate the EHC system malfunction. The level transients experience during the scram would be expected with the closure of the MSIVs. The licensee has notified the NRC Resident Inspector. |
Where | |
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Peach Bottom ![]() Pennsylvania (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
Time - Person (Reporting Time:+-0.42 h-0.0175 days <br />-0.0025 weeks <br />-5.75316e-4 months <br />) | |
Opened: | William Dalton 09:30 Dec 22, 2004 |
NRC Officer: | Bill Huffman |
Last Updated: | Dec 22, 2004 |
41277 - NRC Website
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Unit 2 | |
---|---|
Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (100 %) |
After | Hot Shutdown (0 %) |
Peach Bottom ![]() | |
WEEKMONTHYEARENS 569362024-01-29T17:02:00029 January 2024 17:02:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 558992022-05-16T19:52:00016 May 2022 19:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Scram Due to Electrical Transients ENS 555752021-11-14T10:25:00014 November 2021 10:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Trip Due to Lowering Main Condenser Vacuum ENS 536302018-09-30T04:00:00030 September 2018 04:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Scram Due to a Loss of Two Condensate Pumps ENS 472862011-09-21T14:20:00021 September 2011 14:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Relay Malfunction Resulted in a Valid Undervoltage Signal ENS 453482009-09-14T02:44:00014 September 2009 02:44:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Short Period During Plant Shutdown ENS 428892006-10-07T21:50:0007 October 2006 21:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 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 Technical Specification Required Shutdown Due to Loss of Primary Containment Integrity ENS 418322005-07-10T07:18:00010 July 2005 07:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Turbine Trip Resulting in Rps Actuation and Automatic Reactor Scram ENS 412772004-12-22T09:55:00022 December 2004 09:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Reactor Scram and Eccs Injection Following Opening of Turbine Bypass Valves ENS 405372004-02-22T20:10:00022 February 2004 20:10:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram at Peach Bottom 2 Due to Decreasing Condenser Vacuum ENS 401982003-09-25T04:00:00025 September 2003 04:00:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.73(a)(1), Submit an LER Initiation of a Technical Specification Required Shutdown at Peach Bottom 2 2024-01-29T17:02:00 | |
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