05000263/FIN-2016004-01
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Finding | |
|---|---|
| Title | Licensee-Identified Violation |
| Description | Welding Blanket Partially Covered Reactor Building Ventilation Intake (CAP 1539781) The following violation of very-low significance (Green) was identified by the licensee and was a violation of NRC requirements and met the criteria of the NRC Enforcement Policy for being dispositioned as a Non-Cited Violation (NCV). The licensee identified a finding of very low safety significance (Green) and an associated NCV of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, on October 28, 2016, when the licensee failed to follow procedures while performing activities affecting quality. Specifically, the licensee failed to identify and control modifications of safety-related SSCs in accordance with FPEMOD03; Temporary Modifications, in that operators installed a welding blanket which partially blocked the suction of VAC10A and 10B (intakes of the Reactor Building main supply fans) to prevent welding sparks from being sucked into the intakes and failed to follow steps in that procedure. Procedure FPEMOD03, Revision 13 states, in part, that This procedure shall be applied to Safety-Related SSCs, should be applied to augmented quality or reliability related SSCs, and may be applied to commercial facility changes. Contrary to these requirements, the licensee failed to use FPEMOD03 to evaluate the physical change of installing welding blankets over Safety-Related Reactor Building Ventilation main supply fan intakes for potential plant impact prior to installation. Specifically, this resulted in an increase in negative pressure of the reactor building and an increase of steam chase temperatures which had the potential to upset plant stability by initiating a Group 1 Isolation. This was identified by the licensee during a deliberate observation process by the Shift Manager. Immediate corrective actions included stopping the welding, removing the welding blanket, reducing the steam chase temperature. The licensee documented this issue in the corrective action program (CAPs 1539781, 1541340, and 1541514). The performance deficiency was determined to be more than minor because it adversely affected the Configuration Control attribute of the Initiating Events Cornerstone, with the objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. The finding screened as Green based on answering no to the Initiating Events screening questions in inspection manual chapter (IMC) 0609 Appendix A, The Significance Determination Process for Findings at Power, effective July 1, 2012. The issue was entered into the corrective action program as CAPs 1539781, 1541340, and 1541514. The inspectors concluded the issue was licensee-identified based on the guidance in IMC 0612, Power Reactor Inspection Reports, issue date May 06, 2016. |
| Site: | Monticello  |
|---|---|
| Report | IR 05000263/2016004 Section 4OA7 |
| Date counted | Dec 31, 2016 (2016Q4) |
| Type: | NCV: Green |
| cornerstone | Initiating Events |
| Identified by: | Licensee-identified |
| Inspection Procedure: | |
| Inspectors (proximate) | D Krause G Hansen K Riemer L Haeg P Zurawski R Baker S Bell |
| Violation of: | 10 CFR 50 Appendix B Criterion V |
| INPO aspect | |
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Finding - Monticello - IR 05000263/2016004 | |||||||||||||||||||||||||||||||||||||||||
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Finding List (Monticello) @ 2016Q4
Self-Identified List (Monticello)
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