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ENS 48421
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Category
ENS Notification  and Power Reactor
CFR
10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor +, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition +, 10 CFR 50.72#b3iiB +  and 10 CFR 50.72#b3v +
Current power
100  +
Current reactor mode
Power Operation +
Description
During BFNP (Browns Ferry Nuclear Plant) N … During BFNP (Browns Ferry Nuclear Plant) NFPA (National Fire Protection Association) 805 transition review, it was determined in the event of an Appendix-R fire, fire induced circuit damage could potentially result in the Residual Heat Removal System Division II inboard isolation valve being prevented from opening or cause the valve to spuriously close on units 2 and 3. The current Appendix R safe shutdown analysis credits opening of these valves. Failure to open these valves results in loss of ability to provide long term cooling to the core.</br>Compensatory actions in the form of fire watches to mitigate this condition are in place in accordance with the BFNP Fire Protection Report.</br>This condition is being reported pursuant to 10CFR50.72(b)(3)(ii)(B) and 10CFR50.72(b)(3)(v).</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.  +
Discovered date
18:14:00, 18 October 2012  +
Emergency class
Non Emergency +
Entered date
18:57:00, 18 October 2012  +
Event date
18:14:00, 18 October 2012  +
Event description
During BFNP (Browns Ferry Nuclear Plant) N … During BFNP (Browns Ferry Nuclear Plant) NFPA (National Fire Protection Association) 805 transition review, it was determined in the event of an Appendix-R fire, fire induced circuit damage could potentially result in the Residual Heat Removal System Division II inboard isolation valve being prevented from opening or cause the valve to spuriously close on units 2 and 3. The current Appendix R safe shutdown analysis credits opening of these valves. Failure to open these valves results in loss of ability to provide long term cooling to the core.</br>Compensatory actions in the form of fire watches to mitigate this condition are in place in accordance with the BFNP Fire Protection Report.</br>This condition is being reported pursuant to 10CFR50.72(b)(3)(ii)(B) and 10CFR50.72(b)(3)(v).</br>The NRC Resident Inspector has been notified. NRC Resident Inspector has been notified.  +
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ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +, ENS 48421 +  and ENS 48421 +
Initial power
100  +
Initial reactor mode
Power Operation +
Last update date
00:00:00, 18 October 2012  +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
02:02:44, 2 March 2018  +
NRC officer
Vince Klco +
Notification date
18:57:00, 18 October 2012  +
Originated by
Eric Steele +
Reactor critical
true  +
Reactor scram
false  +
Reactor type
GE-4 +
Region
NRC Region 2 +
Reporting criterion
10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor +  and 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition +
Reporting time
0.03 d (0.72 hours, 0.00429 weeks, 9.86256e-4 months)  +
Site
Browns Ferry +
Start date
18:14:00, 18 October 2012  +
State
Alabama +
System
Residual Heat Removal +
Title
Fire Protection Review Identifies a Potential Unanalyzed Condition  +
Topic
Safe Shutdown +  and Unanalyzed Condition +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://www.nrc.gov/reading-rm/doc-collections/event-status/event/2012/20121019en.html#en48421  +
Unit
2  +  and 3  +
 
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