]> 2026-04-16T18:19:42-04:00 ENS 47784 0 en 100 96 On March 14, 2012, it was determined that in the event of an Appendix R fire, fire damage to cables in Fire Area 2-4, 3-3, or 25-1 could cause a Residual Heat Removal Service Water System (RHRSW) pump to spuriously start. This unanalyzed condition was originally determined to be not reportable. However, during subsequent review on March 28, 2012, this condition was determined to be reportable since the additional load from the spurious start of the RHRSW pump on the associated Emergency Diesel Generator (EDG) could result in the design maximum loading of the EDG being exceeded. As a result of the EDG maximum loading being exceeded, the EDG credited in the Appendix R fire analysis to supply required Appendix R safe shutdown loads could fail. The issue has significant safety impact since the capability to supply power to the Appendix R safe shutdown equipment for the credited EDG is necessary to provide adequate core cooling and decay heat removal during performance of the Browns Ferry Nuclear Plant Safe Shutdown Instructions in an Appendix R fire event. The NRC Resident Inspector has been notified. 2012-03-28T21:15:00Z 2456015.3854167 47784 2012-03-28T22:44:00Z 2456015.4472222 2012-03-28T21:15:00Z 2456015.3854167 On March 14, 2012, it was determined that in the event of an Appendix R fire, fire damage to cables in Fire Area 2-4, 3-3, or 25-1 could cause a Residual Heat Removal Service Water System (RHRSW) pump to spuriously start. This unanalyzed condition was originally determined to be not reportable. However, during subsequent review on March 28, 2012, this condition was determined to be reportable since the additional load from the spurious start of the RHRSW pump on the associated Emergency Diesel Generator (EDG) could result in the design maximum loading of the EDG being exceeded. As a result of the EDG maximum loading being exceeded, the EDG credited in the Appendix R fire analysis to supply required Appendix R safe shutdown loads could fail. The issue has significant safety impact since the capability to supply power to the Appendix R safe shutdown equipment for the credited EDG is necessary to provide adequate core cooling and decay heat removal during performance of the Browns Ferry Nuclear Plant Safe Shutdown Instructions in an Appendix R fire event. The NRC Resident Inspector has been notified. 100 96 2012-03-28T00:00:00Z 2456014.5 2012-03-28T22:44:00Z 2456015.4472222 true false 5328 2012-03-28T21:15:00Z 2456015.3854167 Unanalyzed Condition Discovered During Nfpa 805 Transition Impacting Emergency Diesel Generator Loading 1 2 3 2017-09-24T22:25:39Z 2458021.4344792 ENS 47784 0 0 plainlist 1 [[:Browns Ferry]] ENS 47784# QUERYfbead48633525b0d92c4b4efcc40b476 0 0 plainlist 1 [[:10 CFR 50.72(b)(3)(ii)(B)]] ENS 47784# QUERYd404c21eed3b835554a4de340ba76eda 0 1 plainlist 3 [[Category:Licensee Event Report]] [[ENS::ENS 47784]] ENS 47784# QUERYdb891930e9682f9ef4b9260583717040 0 1 plainlist 5 [[Category:Licensee Event Report]] [[Event date::28 March 2012]] [[Site::Browns Ferry]] ENS 47784# QUERYa27d4ce2b149b75a488294f87ef94914 0 0 plainlist 1 [[:David Hall]] ENS 47784# QUERYcf16280e64d064133c2e25ea877d0c43 0 1 table 3 [[Originated by::David Hall]] [[Category:ENS Notification]] ENS 47784# QUERY814f6422f17f9ec45b4ebe95e800bc56 0 0 plainlist 1 [[:Bill Huffman]] ENS 47784# QUERY7ec70a7b073c046e5fc39f05e37d914c 0 1 table 3 [[NRC officer::Bill Huffman]] [[Category:ENS Notification]] ENS 47784# QUERY4a8e42b1142dd81adaeb308b5733263f 0 0 plainlist list 1 [[:ENS 47784]] ENS 47784# QUERYc718504fac90935203b8fd0891dab027 0 0 plainlist 1 [[:Tennessee Valley Authority]] ENS 47784# QUERY6af81bd43bcba06c903489588528168e 0 1 table 3 [[Category:ENS Notification]] [[Site::Browns Ferry]] ENS 47784# QUERY383ad08b8eb02bdd0c1654f155072e0d 0 1 timeline 5 [[Category:ENS Notification]] [[Site::Browns Ferry]] [[Reporting criterion::10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition]] ENS 47784# QUERYe32947fd07be9b73412908df26b33cb3 0 1 table 5 [[Category:ENS Notification]] [[Site::Browns Ferry]] [[Reporting criterion::10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition]] ENS 47784# QUERY117c8d9481da079d990e63e3828096f5 0 0 template 1 [[:ENS 47784]] ENS 47784# QUERY34e868b5780a92dc9d1a590f60afca5b