ENS 42889
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ENS Event | |
|---|---|
21:50 Oct 7, 2006 | |
| Title | Technical Specification Required Shutdown Due to Loss of Primary Containment Integrity |
| Event Description | At 17:50, on 10/07/2006, the Peach Bottom Atomic Power Station identified a crack approximately 4 inches long on a Unit 2, Reactor Core Isolation Cooling (RCIC) test line, as the line penetrates the Suppression Pool of Primary Containment. The degraded piping represents a loss of primary containment integrity, placing one of the principle safety barriers in a 'Seriously Degraded' condition as defined by 10CFR50.72 (b)(3)(ii)(A). This condition required a Reactor Shutdown per the plants Technical Specifications (TS) [TS 3.6.1.1]. Unit 2 was manually scrammed, at 20:16, in order to shutdown the reactor and place the unit in Mode 3 per the Technical Specifications. The TS required shutdown is reportable per 10CFR50.72(b)(2)(i). The unplanned reactor scram is reportable per 10CFR50.72(b)(2)(iv)(B). The reactor scram and resultant Emergency Safety Feature actuations were completed as required. In addition, the loss of primary containment integrity represents a condition that 'could have prevented the fulfillment of a safety function of a structure required to control the release of radioactive material' and/or 'mitigate the consequences of an accident.' This is reportable per 10CFR50.72(b)(3)(v)(C) and (D). Unit 2 is currently shutdown, Mode 3, with an RPV cooldown in progress, with plans to Enter Mode 4 by 02:00 on 10/08/06.
All control rods fully inserted on the Manual Reactor Scram. The reactor is currently being fed from the condensate system with decay heat being removed to the condenser via the MSL drains. The electric plant is in a normal shutdown lineup. See EN # 42887 for related NOTICE OF UNUSUAL EVENT. Additional 10 CFR Section not listed above: 50.72(b)(3)(v)(D) ACCIDENT MITIGATION The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Peach Bottom  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 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 | |
| Time - Person (Reporting Time:+1.98 h0.0825 days <br />0.0118 weeks <br />0.00271 months <br />) | |
| Opened: | Robert Steigerwald 23:49 Oct 7, 2006 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Oct 8, 2006 |
| 42889 - NRC Website | |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (22 %) |
| After | Hot Shutdown (0 %) |
Peach Bottom with 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 | |
WEEKMONTHYEARENS 569802024-02-19T15:45:00019 February 2024 15:45:00
[Table view]10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Loss of Reactor Building Ventilation ENS 569362024-01-29T17:02:00029 January 2024 17:02:00 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 549712020-10-29T14:30:00029 October 2020 14:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Through-Wall Leakage Identified on Reactor Coolant System Pressure Boundary During Testing 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 536172018-09-21T04:00:00021 September 2018 04:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded High Pressure Coolant Injection System Inoperable ENS 530312017-10-23T08:00:00023 October 2017 08:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Leakage Identified on One Inch Line Socket Weld for the B Recirculation Pump ENS 505712014-10-29T15:20:00029 October 2014 15:20:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Maximum Allowable Primary Containment Leakage Rate Exceeded 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 452892009-08-24T18:15:00024 August 2009 18:15:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Station Safety Grade Pneumatic Supply Issue 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 420032005-09-20T09:00:00020 September 2005 09:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Small Leak on Rhr Injection Drain Line 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 2024-02-19T15:45:00 | |
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