05000482/FIN-2012002-02
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Finding | |
|---|---|
| Title | Failure to Test ASME O&M Code Category A Valves in Post-LOCA Flow Path |
| Description | The inspectors identified a non-cited violation of 10 CFR Part 50.55a(f)(4), Codes and Standards, for failure to adequately demonstrate that the seat leakage for 12 emergency core cooling system and containment spray valves remained within acceptable limits. These valves have a combined allowable leakage rate of 3.8 gpm to ensure that control room operator radiation doses remain within regulatory limits during an accident. Since the flowpaths have valves for which seat leakage is limited to a specific maximum amount, the inspectors identified that they should be considered Category A valves as specified in ASME OM (American Society of Mechanical Engineers Operations & Maintenance) Code. Wolf Creek subsequently took corrective action to perform valve seat leakage testing on March 10, 2012, which demonstrated that leakage was within acceptable limits. Additionally, Wolf Creek plans to change Chapter 15 of the USAR and correct its ASME OM Code basis document. This issue was entered into the licensees corrective action program as condition report 46927. Failure to correctly identify and perform testing needed to assure plant design for control room habitability is a performance deficiency. This finding is greater than minor because it was associated with the Barrier Integrity Cornerstone attribute of configuration control and affects the cornerstone objective to provide reasonable assurance that physical design barriers (fuel cladding, reactor coolant system, and containment) protect the public from radionuclide releases caused by accidents or events. Specifically, it affects the design control objective by failing to ensure that design limits were met on a periodic basis. Using Inspection Manual Chapter 0609.04, the issue was determined to not impact public and control room dose (above regulatory limits), it did not impact the control room due to toxic gas, it did not represent an actual open containment bypass path (above of regulatory limits), and did not impact hydrogen igniters. Therefore, this finding was found to be of very low safety significance. Also, public dose was not impacted with a potential radiation dose above a 10 CFR Part 50, Appendix I criteria. This finding did not have a cross-cutting aspect since the error associated with the inservice testing program was not reflective of current licensee performance because the failure to identify and include these valves occurred more than 3 years ago. |
| Site: | Wolf Creek  |
|---|---|
| Report | IR 05000482/2012002 Section 1R22 |
| Date counted | Mar 31, 2012 (2012Q1) |
| Type: | NCV: Green |
| cornerstone | Barrier Integrity |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.22 |
| Inspectors (proximate) | C Peabody Z Hollcraft G Callaway J Melfi N O'Keefe C Long |
| INPO aspect | |
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Finding - Wolf Creek - IR 05000482/2012002 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Wolf Creek) @ 2012Q1
Self-Identified List (Wolf Creek)
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