05000282/FIN-2011003-01
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Finding | |
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| Title | Failure to Maintain Reactor Head Height/Distance Limitation From Reactor Vessel |
| Description | A finding of very low safety significance and an associated NCV of 10 CFR Part 50, Appendix B, Criterion V, was identified by the inspectors on May 23, 2011, due to the licensees failure to follow Procedure D58.1.10 Unit 1-Reactor Vessel Head Replacement. Specifically, licensee personnel failed to ensure that the Unit 1 reactor vessel head was lifted no higher than the 756 3 elevation of the Unit 1 containment when the head was within 15 feet of the reactor vessel flange. Corrective actions for this issue included a human performance event investigation and the issuance of two procedure change requests to provide enhanced knowledge of the height and distance limitations during reactor vessel head movement. The issue was entered into the corrective action program (CAP) as CAP 1287268. The inspectors determined that this issue was more than minor because, if left uncorrected, the failure to comply with Procedure D58.1.10 could lead to more significant safety concerns including exceeding the reactor vessel head drop/heavy loads analysis criteria. The finding is associated with the Initiating Events Cornerstone. The inspectors contacted a regional Senior Reactor Analyst (SRA) for assistance in determining the risk significance of this finding since the SDP for shutdown conditions did not address reactor vessel head drop concerns. The SRA concluded that the use of IMC 0609, Appendix M, Significance Determination Process Using Qualitative Criteria, was the appropriate method for determining the significance. In accordance with IMC 0609, Appendix M, management review of this issue determined that this finding was of very low safety significance since the movement of the reactor head did not exceed the reactor head drop analysis criteria. This finding was cross-cutting in the area of Human Performance, Work Practices, Supervisory and Management Oversight, because the licensee did not appropriately provide oversight of work activities, including contractors, such that nuclear safety was supported. |
| Site: | Prairie Island  |
|---|---|
| Report | IR 05000282/2011003 Section 1R20 |
| Date counted | Jun 30, 2011 (2011Q2) |
| Type: | NCV: Green |
| cornerstone | Initiating Events |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.2 |
| Inspectors (proximate) | J Jandovitz M Mitchell C Brown M Phalen K Stoedter D Betancourt J Corujo-Sandin E Sanchez N Feliz-Adorno S Lynch S Shah |
| CCA | H.2, Field Presence |
| INPO aspect | LA.2 |
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Finding - Prairie Island - IR 05000282/2011003 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Prairie Island) @ 2011Q2
Self-Identified List (Prairie Island)
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