05000482/FIN-2010007-01
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Finding | |
|---|---|
| Title | Inadequate Design of Component Cooling Water Safety/Nonsafety Isolation |
| Description | Green. The team identified a Green noncited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, which states, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions. Specifically, as of October 8, 2010, the licensee failed to incorporate design seismic requirements into the design calculations and actual system operation. This finding was entered into the licensees corrective action program as Condition Report 00028237. The team determined that the failure to adequately analyze the isolation between the safety related and nonsafety- related portions of the component cooling water system was a performance deficiency. This finding was more than minor because it was associated with the design control attribute of the Mitigating Systems Cornerstone and affected the cornerstone objective of ensuring the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the design basis analysis did not ensure that the affected train of component cooling water would perform its required functions after the failure of nonsafety-related component cooling water piping. The inspectors evaluated the issue using Manual Chapter 0609.04, Phase 1 - Initial Screening and Characterization of Findings. This finding affected the Mitigating Systems Cornerstone because seismic protection was degraded. The inspectors determined that this finding represented the degradation of equipment and functions specifically designed to mitigate a seismic event and that during an earthquake the deficiency would degrade one train of component cooling water, a system that supports a safety system or function. Therefore, this finding was potentially risk significant to seismic initiators and a Phase 3 analysis was required. A Region IV senior reactor analyst performed the Phase 3 significance determination. The change in core damage frequency was calculated to be 7.0 x 10-8 indicating that this finding was of very low safety significance (Green). The dominant risk sequence included a seismic initiating event, loss of offsite power, loss of reactor coolant pump seal cooling, and a failure of high pressure recirculation. This finding did not have a crosscutting aspect because the most significant contributor did not reflect current licensee performance. |
| Site: | Wolf Creek  |
|---|---|
| Report | IR 05000482/2010007 Section 1R21 |
| Date counted | Dec 31, 2010 (2010Q4) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.21 |
| Inspectors (proximate) | B Correll C Baron D Strickland J Adams S Kobylarz T Farnholtz |
| INPO aspect | |
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Finding - Wolf Creek - IR 05000482/2010007 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Wolf Creek) @ 2010Q4
Self-Identified List (Wolf Creek)
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