ENS 47341
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ENS Event | |
|---|---|
14:00 Oct 13, 2011 | |
| Title | Fire Related Unanalyzed Condition That Could Impact Equipment Credited in Safe Shutdown Analysis |
| Event Description | In preparation for converting from 10 CFR 50, Appendix R, to NFPA (National Fire Protection Association) 805, a review of the Brunswick Steam Electric Plant (BSEP) Safe Shutdown Analysis identified conditions that may not ensure a protected train of equipment remains available under certain postulated fire scenarios. The analysis determined that a postulated fire in specific fire areas could cause spurious actuation of critical components, potentially resulting in loss of equipment required for Safe Shutdown. A fire in one of the specified fire areas could potentially adversely affect the following; Suppression Pool level instrument 2-CAC-LT-2602, Residual Heat Removal net positive suction head (i.e., Drywell Containment Overpressure), Reactor Core Isolation Cooling (RCIC), Emergency bus E-1, and Emergency bus E-3.
The initial safety significance of this event is minimal. Fire watches have been established for the affected portions of fire areas RB2-01, RB1-01, TB1, CB-02, and CB-23E. Additionally, fire detection and suppression equipment in the affected areas is fully functional. Fire watches have been established for the affected portions of fire areas RB2-01, RB1-01, TB1, CB-02, and CB-23E. This condition has been entered Into the Corrective Action Program (i.e., CR 493784). This is reportable as an unanalyzed condition that significantly degrades plant safety in accordance with 10 CFR 50.72(b)(3)(ii)(B). Compensatory measures have been established to provide an hourly fire watch for the affected fire areas. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Brunswick  North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| LER: | 05000325/LER-2011-002 |
| Time - Person (Reporting Time:+2.47 h0.103 days <br />0.0147 weeks <br />0.00338 months <br />) | |
| Opened: | Lee Goldstein 16:28 Oct 13, 2011 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Oct 13, 2011 |
| 47341 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
WEEKMONTHYEARENS 499352014-03-20T13:11:00020 March 2014 13:11:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire-Related Unanalyzed Condition That Could Impact Credited Safe Shutdown Analysis ENS 492222013-07-29T14:42:00029 July 2013 14:42:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Related Unanalyzed Condition That Could Impact Credited Safe Shutdown Analysis ENS 482532012-08-30T01:34:00030 August 2012 01:34:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Local Control Capability of Emergency Diesel Generator #2 Not Available Under Certain Conditions ENS 474522011-11-17T18:45:00017 November 2011 18:45:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition on Startup Following Maintenance Outage ENS 473412011-10-13T14:00:00013 October 2011 14:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Fire Related Unanalyzed Condition That Could Impact Equipment Credited in Safe Shutdown Analysis ENS 444252008-08-19T15:10:00019 August 2008 15:10:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Alternate Safe Shutdown Local Start Capability of All Four Emergency Diesel Generators May Not Be Available Under Certain Conditions ENS 411602004-10-29T20:00:00029 October 2004 20:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Unanalyzed Condition Discovered in 480 Volt Switchgear Room 2014-03-20T13:11:00 | |
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