05000461/FIN-2015002-04
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Finding | |
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Title | Failure to Translate Sufficient Gland Stress to Packing Gland Nuts Resulted in Valve Packing Failure and Plant Shutdown |
Description | A finding of very low safety significance and an associated NCV of 10 CFR 50, Appendix B, Criterion III, Design Control, was self-revealed on January 19, 2015, when a steam leak developed from the Reactor Core Isolation Cooling (RCIC) system inboard steam isolation valve (1E51F0063) stem packing. Specifically, the licensee failed to identify and implement a torque value for the gland packing to overcome service induced consolidation and prevent packing leakage. This resulted in a plant down power to 83 percent and subsequent plant shutdown due to increasing unidentified reactor coolant system leakage. The licensee documented the issue in the CAP as action request (AR) 02439437. The licensee repacked the valve utilizing the Procedure Clinton Power Station (CPS) 8120.37, Valve Packing Installation, and the applicable SealPro data sheet. A four ring set of A.P. Services graphite packing was installed with a new live load assembly sized to a new torque value of 59 ft-lbs. and the valve packing was tested to verify no leakage. The inspectors determined that the failure to apply sufficient packing gland torque to overcome service induced consolidation and prevent packing leakage on the RCIC system inboard steam isolation valve was a performance deficiency. The performance deficiency was more than minor in accordance with IMC 0612, "Power Reactor Inspection Reports," Appendix B, "Issue Screening," dated September 7, 2012, because it was associated with the equipment performance attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of those events that upset plant stability and challenge critical safety functions during shutdown, as well as power operations, and is therefore a finding. Using IMC 0609, Attachment 4, Initial Characterization of Findings, and Appendix A, The Significance Determination Process for Findings at Power, issued June 19, 2012, the finding was screened against the Initiating Events cornerstone and determined to be of very low safety significance (Green) because the finding did not result in exceeding the reactor coolant system leak rate for a small loss of coolant accident, cause a reactor trip, involve the complete or partial loss of a support system that contributes to the likelihood of, or caused an initiating event and did not affect mitigation equipment. The inspectors determined that no cross-cutting aspect would be associated with this finding since the performance deficiency occurred in 2010 and was not representative of current licensee performance. (Section 4OA2) |
Site: | Clinton ![]() |
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Report | IR 05000461/2015002 Section 4OA2 |
Date counted | Jun 30, 2015 (2015Q2) |
Type: | NCV: Green |
cornerstone | Initiating Events |
Identified by: | Self-revealing |
Inspection Procedure: | IP 71152 |
Inspectors (proximate) | S Bell S Mischke W Schaup A Dahbur C Phillips E Sanchez-Santiago J Bozga K Stoedter |
Violation of: | 10 CFR 50 Appendix B Criterion III, Design Control |
INPO aspect | |
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Finding - Clinton - IR 05000461/2015002 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Clinton) @ 2015Q2
Self-Identified List (Clinton)
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