ENS 47374
ENS Event | |
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20:34 Oct 25, 2011 | |
Title | Deficiency Identified in Transition to Performance Based Standard for Fire Protection |
Event Description | At 1534 on 10/25/11 Site Engineering and Licensing reported the following to the Operations Department:
The following deficiency was identified during reviews for NFPA 805 Transition: Cable 1B11 (#12 awg - Fire Area Route 16, 17) from the shunt in the 250 VDC Battery Board 1 (0-BDDD-280-0001) compartment #1, to the control room ammeter 1-EI-57-38 mounted on Control Room Panel 1-9-8, is not fused or otherwise protected against an electrical fault. The 250 VDC Battery 1 is an un-grounded DC system. However, in a scenario where the 250 VDC Battery Board system negative becomes grounded at the same time the ammeter cable 1B11 has a fault to ground, the cable may not be protected and the cable could auto-ignite anywhere along the cables length from the ground fault location back to the battery source. For example, in a Fire Area 16 (Control Bay) scenario, these ground faults could result in a fire being spread from Fire Area 16 to Fire Area 17 (Battery Board 1). Fuses should be added to protect these cable conductors. A similar condition exists for the remote ammeters on Unit Battery Board 2 (Cable 2B11 - Fire Area Route 16, 18), Unit Battery Board 3 (Cable 3B11 - Fire Area Route 16, 19), Unit Battery Board 4 (Cable 2B4018 - Fire Area Route 16, 26), Unit Battery Board 5 (Cable 1B383 - Fire Area Route 16, 26), and Unit Battery Board 6 (Cable 3B336 - Fire Area Route 16, 26). This condition is reportable as an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification to the NRC IAW 10CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.' This is also reportable as 60 day written report IAW 10CFR 50.73(a)(2)(ii)(B). Fire watch compensatory measures are in place for the Fire Areas of concern. Ref. FPIP#09-1920 The NRC resident has been notified of this event. This event was entered into the licensee's Corrective Action Program as PER# 452185. |
Where | |
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Browns Ferry ![]() Alabama (NRC Region 2) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
LER: | 05000461/LER-2011-007 |
Time - Person (Reporting Time:+3.25 h0.135 days <br />0.0193 weeks <br />0.00445 months <br />) | |
Opened: | Mark Moebes 23:49 Oct 25, 2011 |
NRC Officer: | Bill Huffman |
Last Updated: | Oct 26, 2011 |
47374 - NRC Website
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Unit 1 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (50 %) |
After | Power Operation (50 %) |
Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 3 | |
---|---|
Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
WEEKMONTHYEARENS 542662019-09-11T00:34:00011 September 2019 00:34:00
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