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On May 1, 2001, at 0809, with the plant op … On May 1, 2001, at 0809, with the plant operating in Mode 1 at 100% Reactor power, it was discovered that a fire in Fire Area RAS 27 could result in the loss of both trains of Emergency Diesel Generator (EDG) Fuel Oil Transfer Pumps. The condition existed due to a failure to wrap certain essential B' train equipment cables located in that fire area. Assuming a loss of off-site power in conjunction with the fire could result in both Emergency Diesel Generators becoming inoperable in approximately 3 hours, following depletion of fuel oil in the Day Tanks. This condition could significantly impact the ability of the plant to achieve and maintain cold shutdown. The condition is believed to have been caused by a design analysis deficiency during preparation of the original safe shutdown analysis. Fire impairments were generated and compensatory measures (hourly fire watches) were established pending resolution. The condition constitutes an unanalyzed condition that significantly degrades plant safety and is therefore reportable under 10 CFR 50.73(a)(2)(ii)(13). There was no actual fire event involved. Therefore, the condition did not compromise the health and safety of the general public.</br></br>This event is not considered a Safety System Functional Failure (SSFF).</br></br>NRC FORM 356 (1-2001) CIIbPDF - www.fastio.com Waterford Steam Electric Station, Unit 3 � 05000-382 01 I FACILITY NAME (1) � DOCKET (2) � LER NUMBER (6) � PAGE (3) — 005 — 00 6NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001).S. NUCLEAR REGULATORY COMMISSION (1-2001) +
On May 1, 2001, at 0809, with the plant op … On May 1, 2001, at 0809, with the plant operating in Mode 1 at 100% Reactor power, it was discovered that a fire in Fire Area RAS 27 could result in the loss of both trains of Emergency Diesel Generator (EDG) Fuel Oil Transfer Pumps. The condition existed due to a failure to wrap certain essential B' train equipment cables located in that fire area. Assuming a loss of off-site power in conjunction with the fire could result in both Emergency Diesel Generators becoming inoperable in approximately 3 hours, following depletion of fuel oil in the Day Tanks. This condition could significantly impact the ability of the plant to achieve and maintain cold shutdown. The condition is believed to have been caused by a design analysis deficiency during preparation of the original safe shutdown analysis. Fire impairments were generated and compensatory measures (hourly fire watches) were established pending resolution. The condition constitutes an unanalyzed condition that significantly degrades plant safety and is therefore reportable under 10 CFR 50.73(a)(2)(ii)(13). There was no actual fire event involved. Therefore, the condition did not compromise the health and safety of the general public.</br></br>This event is not considered a Safety System Functional Failure (SSFF).</br></br>NRC FORM 356 (1-2001) CIIbPDF - www.fastio.com Waterford Steam Electric Station, Unit 3 � 05000-382 01 I FACILITY NAME (1) � DOCKET (2) � LER NUMBER (6) � PAGE (3) — 005 — 00 6NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (1-2001).S. NUCLEAR REGULATORY COMMISSION (1-2001) +
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