ENS 42867
ENS Event | |
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14:51 Aug 9, 2006 | |
Title | Invalid Eecw Pump Actuation During Testing |
Event Description | This 60-day telephone notification is being made under reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid actuation of an emergency service water system component that does not normally run and which provides an ultimate heat sink.
At 0951 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.618555e-4 months <br /> CDT on August 9, 2006, with Unit 1 defueled and Units 2 and 3 operating at 100% power, the B3 Emergency Equipment Cooling Water (EECW) pump was tripped when an undervoltage relay was manually operated during functional testing of relaying associated with the 1B Core Spray (CS) pump breaker. While operations personnel were responding to the pump trip, but before the testing activity could be halted, performance of subsequent steps in the functional testing activity resulted in an automatic start of this same pump and then another trip when a companion undervoltage relay was manually operated. Auto-starting of associated EECW pumps upon CS pump starts is part of the equipment logic and had been anticipated, and the B3 EECW pump had been placed in service prior to beginning the relay functional testing to avoid an automatic start. The potential for tripping loads other than the 1B Core Spray pump breaker was discussed in the pre job briefing, however, the actual test instruction steps did not provide detail sufficient to ensure only specific undervoltage relay contacts were operated. Rather than operating only specific relay contacts, test personnel operated the entire relay, resulting in the unplanned trip, restart, and trip of the B3 EECW pump. The logic downstream from the manually operated undervoltage relays and the B3 EECW pump responded in accordance with the plant design. No other plant equipment was affected during this event, though the 2B Core Spray pump would have also tripped had it been running at the time the undervoltage relays were operated. The B3 EECW pump was secured, and the testing activity was suspended. Other operating EECW pumps were not affected and no degradation of EECW system function occurred. There were no safety consequences or impacts on the health and safety of the public. The event was entered into TVA's corrective action program for evaluation and resolution. Reference corrective action document PER 108425. The licensee notified the NRC Resident Inspector. |
Where | |
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Browns Ferry Alabama (NRC Region 2) | |
Reporting | |
10 CFR 50.73(a)(1), Submit an LER, Invalid Actuation | |
Time - Person (Reporting Time:+1224.18 h51.008 days <br />7.287 weeks <br />1.677 months <br />) | |
Opened: | Rodney Nacoste 15:02 Sep 29, 2006 |
NRC Officer: | Mark Abramovitz |
Last Updated: | Sep 29, 2006 |
42867 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
Unit 3 | |
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Reactor critical | Critical |
Scram | No |
Before | Power Operation (100 %) |
After | Power Operation (100 %) |
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00:58:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System (Pcis) Actuation ENS 428672006-08-09T14:51:0009 August 2006 14:51:00 10 CFR 50.73(a)(1), Submit an LER Invalid Eecw Pump Actuation During Testing ENS 428372006-07-18T09:47:00018 July 2006 09:47:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System Actuation Due to Loss of Power to One Reactor Protection System Bus ENS 423892006-01-13T17:57:00013 January 2006 17:57:00 10 CFR 50.73(a)(1), Submit an LER Unplanned, Invalid Actuation of Emergency Diesel Generator ENS 422152005-11-15T14:05:00015 November 2005 14:05:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System (Pcis) Actuation ENS 411812004-09-28T18:02:00028 September 2004 18:02:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System Actuation from Loss-Of-Power to Reactor Protection System (Rps) Bus 2A ENS 411802004-09-25T23:14:00025 September 2004 23:14:00 10 CFR 50.73(a)(1), Submit an LER Invalid Primary Containment Isolation System Actuation from Loss-Of-Power to Reactor Protection System (Rps) Bus 3B 2021-04-01T18:02:00 [Table view] | |