05000348/FIN-2010004-03
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Finding | |
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Title | Inadequate Procedure Leads to LOSP on Unit 2 4160 volt Safety Related Bus |
Description | A self-revealing NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified for the licensees failure to modify surveillance test procedure FNP-2-STP-40.0, Safety Injection with Loss of Off-site Power (LOSP) Test. Following implementation of a modification to the LOSP/Safety Injection (SI) sequencer on both units, the licensee failed to update FNP-2-STP-40.0, resulting in an inadequate procedure. The procedure failed to address placing the Test Trip Override Switch in its OFF position during restoration steps. This resulted in an unplanned power interruption to the 2F electrical bus from its only source of power during the test conducted on April 30, 2010, and subsequent re-loading of safety-related loads by the LOSP/SI sequencer, B2F. Following the unplanned power interruption, the licensee implemented a temporary procedure change and promptly restored plant components to required conditions for the current plant mode of operation. The licensee entered the event in its corrective action program (CAP) as CR 2010105854. The finding is more than minor because it adversely affected the procedure quality attribute of the Mitigating Systems (MS) cornerstone objective of ensuring the availability, reliability, and capability of systems responding to initiating events to prevent undesirable consequences (i.e. core damage). Specifically, this finding affected the Unit 2 Train A 4160 volt safety-related 2F electrical buss ability to provide power to engineered safeguards feature components. Because the unit was in Mode 6, with greater than 23 feet of water above the reactor vessel, the significance of this finding was assessed using the Phase 1 screening worksheets of Attachment 4 and Appendix G, Attachment 1, Checklist 4 of IMC 0609, SDP. The inspectors determined this finding was of very low safety significance (Green), because it did not increase the likelihood of a loss of reactor coolant system (RCS) inventory or degrade the licensees ability to terminate a leak path or add to RCS inventory. This finding was assigned a cross-cutting aspect in the resources component of the Human Performance area because complete, accurate, and up-to-date procedures were not provided (H.2(c)). |
Site: | Farley |
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Report | IR 05000348/2010004 Section 4OA3 |
Date counted | Sep 30, 2010 (2010Q3) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | Self-revealing |
Inspection Procedure: | IP 71153 |
Inspectors (proximate) | S Shaeffer R Reyes S Sandal P Capehart J Sowa K Schaaf E Crowe |
CCA | H.7, Documentation |
INPO aspect | WP.3 |
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Finding - Farley - IR 05000348/2010004 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Farley) @ 2010Q3
Self-Identified List (Farley)
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