05000263/FIN-2012005-01
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Finding | |
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Title | Manipulation of Safety Related Equipment without Appropriate Guidance or Approval of Shift Supervision |
Description | A self-revealed finding of very low safety significance and non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified when the licensee failed to properly restore the reactor core isolation cooling (RCIC) system to an operable status subsequent to completing planned maintenance on the system. Specifically, to facilitate the removal of foreign material from the breaker cubicle, operators manipulated two electrical breakers, (D311-11 and D311-12), without procedural guidance or approval of shift supervision, subsequent to closing those breakers in accordance with clearance restoration instructions. Once identified, the licensee took prompt action to ensure that the affected breakers were in their appropriate positions. Additional immediate corrective actions taken by the licensee included disqualification of the operators that were involved and conducting an operations department standdown. As part of the standdown and prior to performing equipment manipulations, all operators participated in a discussion, lead by shift supervision, associated with the requirements and expectations contained in Fleet Procedure FP-OP-COO-17, Conduct of Operations: Equipment Manipulations and Status Control. The licensee will also perform a root cause evaluation to review this event in more detail. This event was entered into the licensees corrective action program (CAP 01358924). The inspectors determined that operators manipulating safety-related equipment without the appropriate procedures or guidance was a performance deficiency, because it was the result of the failure to meet the requirements of FP-OP-COO-17, Conduct of Operations, a procedure affecting quality; the cause was reasonably within the licensees ability to foresee and correct; and should have been prevented. The inspectors screened the performance deficiency per Inspection Manual Chapter (IMC) 0612, Power Reactor Inspection Reports, Appendix B, and determined that the issue was more than minor because it impacted the Human Performance attribute of the Mitigating Systems Cornerstone and affected the cornerstones objective to ensure the availability reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e. core damage). The inspectors applied IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, to this finding. The inspectors evaluated the issue under the Mitigating Systems Cornerstone, and utilized Exhibit 2, Mitigating Systems Screening Questions, to screen the finding. The inspectors answered No to all the questions in Section A, Mitigating SSCs and Functionality, and Section B, External Event Mitigating Systems, and determined the finding to be of very low safety significance. The inspectors determined that the contributing cause that provided the most insight into the performance deficiency was associated with the cross-cutting area of Human Performance, having decision-making components, and involving aspects associated with making safety-significant or risk-significant decisions using a systematic process, especially when faced with uncertain or unexpected plant conditions, to ensure safety is maintained. |
Site: | Monticello |
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Report | IR 05000263/2012005 Section 1R13 |
Date counted | Dec 31, 2012 (2012Q4) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | Self-revealing |
Inspection Procedure: | IP 71111.13 |
Inspectors (proximate) | P Voss M Learn D Mcneil K Riemer M Phalen S Thomas J Laughlin J Bozga M Jones |
CCA | H.13, Consistent Process |
INPO aspect | DM.1 |
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Finding - Monticello - IR 05000263/2012005 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Monticello) @ 2012Q4
Self-Identified List (Monticello)
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