05000373/FIN-2007009-04: Difference between revisions
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by Mark Hawes) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 12: | Line 12: | ||
| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71111.21 | | Inspection procedure = IP 71111.21 | ||
| Inspector = P Lougheed, N Valos, G Hausman, C Baron, N Feliz,- | | Inspector = P Lougheed, N Valos, G Hausman, C Baron, N Feliz, -Adomog Nicely, A Stone, C Acosta, -Aceved | ||
| CCA = H.6 | | CCA = H.6 | ||
| INPO aspect = WP.2 | | INPO aspect = WP.2 | ||
| description = The inspectors identified an NCV of 10 CFR Part 50.59, Changes, Tests, and Experiments, which had very low safety significance. Specifically, the licensee failed to complete a 50.59 evaluation for removing main control room lake level instrumentation from service. Although the UFSAR stated that the lake level was continuously monitored in the main control room, the level instrument had not functioned reliably for several years and was removed from the plant maintenance schedule in December 2005. At the time of the inspection, control room monitoring of the lake level was not available. The licensee entered the issue into their corrective action program and initiated more frequent operator rounds as a compensatory measure. The finding was more than minor because the inspectors could not reasonably determine that this change would not have ultimately required prior approval from the NRC. This finding was categorized as Severity Level IV because the underlying technical issue for the finding was determined to be of very low safety significance based on a Phase 1 screening in accordance with IMC 0609, Appendix A, Significance Determination of Reactor Inspection Findings for At-Power Situation. The inspectors concluded that this finding was cross-cutting in the area of Human Performance, Resources, because the licensee failed to effectively address a long standing equipment issue (H.2(a)). | | description = The inspectors identified an NCV of 10 CFR Part 50.59, Changes, Tests, and Experiments, which had very low safety significance. Specifically, the licensee failed to complete a 50.59 evaluation for removing main control room lake level instrumentation from service. Although the UFSAR stated that the lake level was continuously monitored in the main control room, the level instrument had not functioned reliably for several years and was removed from the plant maintenance schedule in December 2005. At the time of the inspection, control room monitoring of the lake level was not available. The licensee entered the issue into their corrective action program and initiated more frequent operator rounds as a compensatory measure. The finding was more than minor because the inspectors could not reasonably determine that this change would not have ultimately required prior approval from the NRC. This finding was categorized as Severity Level IV because the underlying technical issue for the finding was determined to be of very low safety significance based on a Phase 1 screening in accordance with IMC 0609, Appendix A, Significance Determination of Reactor Inspection Findings for At-Power Situation. The inspectors concluded that this finding was cross-cutting in the area of Human Performance, Resources, because the licensee failed to effectively address a long standing equipment issue (H.2(a)). | ||
}} | }} | ||
Revision as of 19:32, 20 February 2018
| Site: | LaSalle  |
|---|---|
| Report | IR 05000373/2007009 Section 1R21 |
| Date counted | Sep 30, 2007 (2007Q3) |
| Type: | TEV: Severity level IV |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.21 |
| Inspectors (proximate) | P Lougheed N Valos G Hausman C Baron N Feliz -Adomog Nicely A Stone C Acosta -Aceved |
| CCA | H.6, Design Margins |
| INPO aspect | WP.2 |
| ' | |