05000313/FIN-2017001-04
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Finding | |
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| Title | Licensee-Identified Violation |
| Description | The licensee identified that four seal injection check valves to the Unit 1 reactor coolant pumps (RCPs), which functioned as containment isolation valves, were missing internal springs required per original design. Due to the vertical orientation of the valves, the valves needed these springs to ensure that the valve disc would seat properly during reverse flow. The licensee also identified they had failed to test these ASME Code Class C check valves close safety function in accordance with ASME Code for Operation and Maintenance of Nuclear Power Plants (OM) Code. The licensee had been testing the close function by manually closing the check valves with their handwheels. Title 10 CFR Part 50.55a.(f)(4)(ii), requires in part, that ASME Code Class 3 pumps and valves must meet the inservice test requirements of ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The 2003 Addenda to the 2001 ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants, Section ISTC-5220, Check Valves, Subsection ISTC-5221, Valve Obturator Movement, Paragraph (a)(1), states in part, that check valves shall be exercised by verifying that on cessation or reversal of flow, the obturator has traveled to the seat. Contrary to the above, prior to November 29, 2016, the inservice tests to verify operational readiness of RCP seal injection check valves did not comply with the applicable version of the ASME OM Code requirement to exercise check valves by verifying that on cessation or reversal of flow, the obturator has traveled to the seat. Specifically, the licensee was manually closing these stop check valves in accordance with their test procedure to satisfy inservice testing. The licensee immediately installed springs for these valves as required and wrote a test procedure to test these valves in accordance with ASME OM Code. The licensee documented the issue in their corrective action program as Condition Report CR-ANO-2016-05149. Using NRC Inspection Manual Chapter 0609, Appendix A, "The Significance Determination Process (SDP) For Findings At-Power, dated June 19, 2012, the inspectors determined the finding to be of very low safety significance (Green) because the finding did not represent an actual open pathway in the physical integrity of reactor containment, containment isolation system and heat removal components. |
| Site: | Arkansas Nuclear  |
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| Report | IR 05000313/2017001 Section 4OA7 |
| Date counted | Mar 31, 2017 (2017Q1) |
| Type: | NCV: Green |
| cornerstone | Barrier Integrity |
| Identified by: | Licensee-identified |
| Inspection Procedure: | |
| Inspectors (proximate) | B Correll B Tindell E Uribe J Choate M Kirk M Tobin N O'Keefe |
| Violation of: | 10 CFR 50.55a |
| INPO aspect | |
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Finding - Arkansas Nuclear - IR 05000313/2017001 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Arkansas Nuclear) @ 2017Q1
Self-Identified List (Arkansas Nuclear)
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