05000416/FIN-2017007-06
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Finding | |
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| Title | Failure to Ensure Adequate Design Control Measures Are in Place Associated with Leakage Control Systems |
| Description | The team identified a Green, non-cited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, which states, in part, Measures shall be established to assure that applicable regulatory requirements and the design basis...for those structures, systems, and components to which this appendix applies are correctly translated into specifications, drawings, procedures, and instructions. Specifically, prior to October 17, 2017, the licensee failed to provide adequate procedures or training to licensed operators to ensure the main steam isolation valve-leakage control system and feedwater leakage control system are manually started consistent with the licensees design basis assumptions. In response to this issue the licensee has provided specific guidance and training to the operators. This finding was entered into the licensees corrective action program as Condition Report CR-GGN-2017-09112. The team determined that the failure to ensure adequate design control measures are translated into procedures and training is a performance deficiency. The performance deficiency is more than minor, and therefore a finding, because it was associated with the barrier performance attribute of the Barrier Integrity Cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the plant was operated at power for an extended period of time without adequate procedures and training for licensed operators to ensure that the system would be placed in service in a manner that ensured radiological leakage across main steam isolation valves and through feedwater pi ping is addressed during a postulated accident. In accordance with Manual Chapter 0609, Significance Determination Process, Attachment 4 (effective date October 7, 2016); and the corresponding Appendix A, The Significance Determination Process (SDP) f or Findings At-Power, Exhibit 3, Barrier Integrity Screening Questions (issue date June 19, 2012); the issue was evaluated using Appendix H, Containment Integrity Significance Determination Process (issue date May 6, 2004). Because the opportunities to ensure the design control measures were correctly captured in procedures and instructions for the main steam isolation valve-leakage control system and feedwater leakage control system were in 2001 and 1987, respectively; and the licensee instituted a time-critical operator action program within the last year to prevent such issues from occurring, the issue was determined to have very low safety significance (Green). The performance deficiency was not indicative of current performance. Therefore, no cross-cutting aspect is being assigned. |
| Site: | Grand Gulf  |
|---|---|
| Report | IR 05000416/2017007 Section 1R21 |
| Date counted | Dec 31, 2017 (2017Q4) |
| Type: | NCV: Green |
| cornerstone | Barrier Integrity |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.21M |
| Inspectors (proximate) | W Sifre C Stott N Okonkwo N Day S Hedger C Baron S Gardner T Farnholtz |
| Violation of: | 10 CFR 50 Appendix B Criterion III, Design Control |
| INPO aspect | |
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Finding - Grand Gulf - IR 05000416/2017007 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Grand Gulf) @ 2017Q4
Self-Identified List (Grand Gulf)
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