05000397/FIN-2015004-02
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Finding | |
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| Title | Licensee-Identified Violation |
| Description | Technical Specification 5.4.1.a, Procedures, requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, dated February 1978. Paragraph 9.a of Regulatory Guide 1.33, Appendix A, requires, in part, written procedures for performing maintenance that can affect the performance of safety-related equipment. The licensee established Procedures ISP-MS-Q901, RPS, Reactor Water Level Low, Level 3 Div 1 CFT/CC, Revision 10, and PPM 10.24.34, PM Calibration Test Barton Differential Indicating Switch, Revision 13, to meet the Regulatory Guide 1.33 requirements when performing maintenance on safety-related Barton main steam level indicating switches. Contrary to the above, prior to June 25, 2015, the licensee failed to maintain written procedures for performing maintenance that can affect the performance of safety-related equipment. Specifically, the licensee failed to include instructions in Procedures ISP-MS-Q901 or PPM 10.24.34 for setting the mechanical stop inside Barton main steam level indicating switches. Subsequently, the mechanical indicator in the switches for MS-LIS-24A and MS-LIS-24C became mechanically bound on the rubber stop within the switch when the level was raised off-scale high during the refueling outage. The licensee implemented corrective action by inserting a half scram signal to comply with technical specifications, calibrating the affected switches including steps to set the mechanical stop, and initiating a condition report. The finding represented a loss of safety system function for reactor water level low (level 3) scram signals and for shutdown cooling isolation logic. Because the finding affected mitigating equipment during at-power and shutdown operations, the inspectors assessed the finding in both the Inspection Manual Chapter (MC) 0609, Appendix A, Significance Determination Process for At-Power Findings, and MC 0609, Appendix G, Shutdown Operations Significance Determination Process. Using Exhibit 2 of MC 0609, Appendix A, and Exhibit 3 of MC 0609, Appendix G, inspectors determined that the finding required a detailed risk evaluation for the at-power portion of the finding and a Phase 2 evaluation for the shutdown portion of the finding because the finding represented a loss of safety-system function. A Region IV senior reactor analyst determined the issue was of very low safety significance (Green) and represented a total change to the core damage frequency of 4.4E-7/year. The dominant sequences were anticipated transients without scram and shutdown loss of inventory. For the at-power exposure, risk was mitigated by the use of the standby liquid control system and recirculation pump trips for the anticipated transients without scram. For the shutdown exposure, risk was mitigated by automatic injection by an emergency core cooling system pump for the losses of inventory. This issue was entered into the licensees corrective action program as AR 332078332078 |
| Site: | Columbia  |
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| Report | IR 05000397/2015004 Section 4OA7 |
| Date counted | Dec 31, 2015 (2015Q4) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | Licensee-identified |
| Inspection Procedure: | |
| Inspectors (proximate) | D Bradley G Kolcum J Groom R Lantz S Hedger S Janicki |
| Violation of: | Technical Specification - Procedures Technical Specification |
| INPO aspect | |
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Finding - Columbia - IR 05000397/2015004 | ||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Columbia) @ 2015Q4
Self-Identified List (Columbia)
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