05000254/FIN-2017002-01
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Finding | |
|---|---|
| Title | Failure to Establish aProcedure Appropriate for Calibration of RCIC Governor |
| Description | A finding of very low safety significance and an associated non-cited violation of Technical Specification (TS) Section 5.4.1 was self-revealed for the licensees failure to establish a procedure as governed by Regulatory Guide 1.33, Revision 2, Appendix A that was appropriate for performing adjustments to the governing control system for the Unit 1 reactor core isolation cooling (RCIC) system. Specifically, on April 14, 2017, the licensee failed to ensure procedure QCIPM 130004, RCIC Woodward Governor EGM Control Box and Ramp Generator/Signal Convertor in Field Calibration, was appropriate for the accurate calibration of the RCIC system turbine governor actuator such that the system would be capable supplying its TS required flowrate of 400 gallons per minute (gpm). Immediate corrective actions included the licensee declaring the Unit 1 RCIC system inoperable and performing required calibrations at normal operating temperatures and pressures. Additional corrective actions included the licensee making procedural revisions to QCIPM 130004 to include specific guidance on performing turbine governor calibration adjustments and providing training to maintenance control system technicians on performing the procedure tasks and other related tasks that led to the inadequate adjustment. The issue was entered into the licensees CAP as IR 3998478.The performance deficiency was determined to be more than minor, and a finding,because it impacted the Mitigating Systems Cornerstone attribute of Equipment Performance and affected the cornerstone objective because the failure to properly calibrate the RCIC governor led to the system becoming inoperable. The inspectors determined the finding could be evaluated using IMC 0609, Appendix A, Significance Determination Process (SDP) for Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions, and determined that the finding required a detailed risk evaluation by a senior reactor analyst (SRA) because it resulted in the loss of the RCIC system function. A SRA performed a detailed risk evaluation of the performance deficiency using the Quad Cities SPAR Model and determined the total Delta Core Damage Frequency (CDF) was 7E9 (Green). The inspectors determined this finding affected the cross-cutting area of Human Performance, in the aspect of Training, because the licensee failed to ensure the technicians performing the calibration understood null voltage adjustments to the RCIC turbine governor could only be performed when the system was at a specified rated speed and pressure [H.9]. |
| Site: | Quad Cities  |
|---|---|
| Report | IR 05000254/2017002 Section 1R15 |
| Date counted | Jun 30, 2017 (2017Q2) |
| Type: | NCV: Green |
| cornerstone | Mitigating Systems |
| Identified by: | Self-revealing |
| Inspection Procedure: | IP 71111.15 |
| Inspectors (proximate) | R Murray K Carrington J Cassidy A Dahbur A Dunlop J Steffes J Stewart C Mathews K Stoedter |
| Violation of: | Technical Specification |
| CCA | H.9, Training |
| INPO aspect | CL.4 |
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Finding - Quad Cities - IR 05000254/2017002 | |||||||||||||||||||||||||||||||||||||||||||
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Finding List (Quad Cities) @ 2017Q2
Self-Identified List (Quad Cities)
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