ENS 41359
ENS Event | |
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20:50 Jan 26, 2005 | |
Title | Potential for Carbon Dioxide Migration Into 4160/460 Volt Switchgear Rooms |
Event Description | An Engineering Evaluation was initiated to assess the potential for CO2 [carbon dioxide] migration in the event of a CO2 fire suppression system discharge in the Salem Unit 1 and 2 - 4160 volt or 460 volt Switchgear Rooms or Lower Electrical Penetration Areas. The results presented in the evaluation conservatively identified that when CO2 systems are discharged, CO2 migration can result in concentrations in some adjacent areas that would require the use of self-contained breathing apparatus (SCBAs) for entry, or in some cases should be restricted to transit activities only.
Some of these adjacent areas are required to be accessible by operators to perform manual actions in the plant to achieve and maintain safe shutdown. Based on the time line established in the Salem Manual Action Feasibility Studies for operator actions in the response to a fire in a Switchgear Room, the ability to shutdown the plant in the event of a fire concurrent with a CO2 discharge could be impacted. The immediate action is to isolate the CO2 system and implement the necessary compensatory measure for the inoperable CO2 system as delineated within Station Fire protection program. With the CO2 systems isolated, the ability to safely shutdown the plant in the event of a fire in these areas is restored. Additional actions are being evaluated at this time to restore the CO2 system. This event is being reported in accordance with 10CFR50.72(b)(3)(v) and Salem Unit 2 License Condition 2.I. No ESF, ECCS or safety related equipment has been impacted by this condition. Both Units remain at 100% power. There were no personnel injuries associated with this condition. Lower Alloway Creek Township and the State of New Jersey will be notified. The NRC Resident Inspector was notified of this event by the licensee. |
Where | |
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Salem ![]() New Jersey (NRC Region 1) | |
Reporting | |
10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Other Unspec Reqmnt | |
Time - Person (Reporting Time:+-3.07 h-0.128 days <br />-0.0183 weeks <br />-0.00421 months <br />) | |
Opened: | Frank Soens 17:46 Jan 26, 2005 |
NRC Officer: | John Mackinnon |
Last Updated: | Jan 26, 2005 |
41359 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Salem ![]() | |
WEEKMONTHYEARENS 521292016-07-28T09:41:00028 July 2016 09:41:00
[Table view]10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Source Range Instruments Reading Improperly During a Reactor Startup ENS 475172011-12-11T17:58:00011 December 2011 17:58:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Intermediate Range Nuclear Instrument High Flux Trip Set Points Set Incorrectly ENS 430382006-12-07T22:28:0007 December 2006 22:28:00 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 Loss of Safe Shutdown Capability ENS 413592005-01-26T20:50:00026 January 2005 20:50:00 Other Unspec Reqmnt, 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Potential for Carbon Dioxide Migration Into 4160/460 Volt Switchgear Rooms ENS 409042004-07-29T01:00:00029 July 2004 01:00:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor Unidentified Reactor Coolant System (Rcs) Leak 2016-07-28T09:41:00 | |