05000286/FIN-2011002-03
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Finding | |
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Title | Lifting of 32 ABFP Steam Supply Relief Valve |
Description | A self-revealing NCV of very low safety significance (Green) of 10 CFR 50, Appendix B, Criterion Xl, 'Test Control,'was identified because Entergy personnel did not establish an adequate test program to assure that the 32 ABFP steam supply relief valve would perform satisfactorily. Specifically, Entergy personnel did not ensure the 'PCV-1139 Valve and Controller Replacement' modification (Minor Modification Package 97-3-320) acceptance values for the remote setpoint pressure regulating valve MS-PR- 1 139-5 were incorporated into testing procedures. Entergy personnel entered this issue into their CAP as CR-lP3-2011-00232. Corrective actions include performing a higher- tier apparent cause evaluation, performing an operability evaluation and reviewing applicable procedures to ensure that control of the setpoint is maintained. The finding was more than minor because the finding is associated with the Design Control attribute of the Mitigating Systems cornerstone and affected the cornerstone objective to ensure the availability and reliability of systems that respond to initiating events to prevent undesirable consequences. Specifically, as evidenced during the performance of 3-PT-1208 on January 21 , 2011 , PCV-1 139 did not maintain pressure in the normal band on startup and allowed pressure to increase to a level that allowed the steam supply relief valve, MS-52, to repeatedly lift, causing unanticipated unavailability of the 32 ABFP. The inspectors evaluated the finding in accordance with IMC 0609, Attachment 4, 'Phase 1 - lnitial Screening and Characterization of Findings,'and determined it was of very low safety significance (Green), because the finding was not a design or qualification deficiency, did not represent a loss of system safety function, and was not risk significant with respect to external initiating events. The inspectors determined that this finding had a cross-cutting aspect in the resources program area of Human Performance because Entergy personnel did not ensure that complete, accurate and up{o-date design documentation and procedures were adequate to assure nuclear safety. Specifically, Entergy personnel did not properly incorporate into procedures the acceptance values for the remote setpoint pressure regulating valve. |
Site: | Indian Point ![]() |
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Report | IR 05000286/2011002 Section 1R15 |
Date counted | Mar 31, 2011 (2011Q1) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | Self-revealing |
Inspection Procedure: | IP 71111.15 |
Inspectors (proximate) | C Newport E Gray J Noggle M Gray M Halter P Cataldo T O'Hara |
CCA | H.5, Work Management |
INPO aspect | WP.1 |
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Finding - Indian Point - IR 05000286/2011002 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Indian Point) @ 2011Q1
Self-Identified List (Indian Point)
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