05000416/FIN-2017003-01
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Finding | |
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Title | Isolation of Reactor Core Isolation Cooling System during Surveillance Testing |
Description | The inspectors reviewed a self-revealed, non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the licensees failure to accomplish quality related activities in accordance with Surveillance Procedure 06-IC-1E31-A-1004, RCIC Equipment Room High Temperature Calibration Channel A, Revision 106. Specifically, on August 21, 2017, the licensee did not follow Step 5.15.4, which states, Identify and disconnect field lead located at Terminal EE-50 in 1H13-P632. This step was not performed correctly; therefore, the reactor core isolation cooling (RCIC) system isolation feature was not bypassed. When performing the next step, an inadvertent isolation of the RCIC system occurred. On August 21, 2017, the licensee restored compliance by performing actions to restore the leads to the correct location and performing the surveillance test satisfactorily. This issue has been entered into the licensees corrective action program as Condition Report CR-GGN-2017-08246.The failure to follow Surveillance Procedure 06-IC-1E31-A-1004 was a performance deficiency. This performance deficiency was more than minor, and therefore a finding, because it was associated with the human performance attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the licensees failure to follow Surveillance Procedure 06-IC-1E31-A-1004 resulted in unplanned inoperability and unavailability of the reactor core isolation cooling system. Using Inspection Manual Chapter 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, and Inspection Manual Chapter 0609, Appendix A, Exhibit 2, Mitigating System Screening Questions, the inspectors determined that the finding was of very low safety significance (Green) because the finding was not a deficiency affecting the design or qualification of a mitigating structure, system, or component; did not represent a loss of safety function; did not represent an actual loss of function of at least a single train for greater than its technical specification allowed outage time, and did not represent an actual loss of function of one or more non-technical specification trains of equipment designated as high safety-significant in accordance with the licensees maintenance rule program for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The inspectors determined that the finding had a field presence cross-cutting aspect within the human performance area because licensee management failed to ensure supervisory and management oversight of work activities, including contractors and supplemental personnel. Specifically, the performer in the field was a supplemental worker that was observed by a licensee instrumentation and controls technician. The technician telephoned the supervisor to ensure that they were performing the steps correctly, and the supervisor did not go into the field to verify the step was performed correctly [H.2]. |
Site: | Grand Gulf |
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Report | IR 05000416/2017003 Section 1R22 |
Date counted | Sep 30, 2017 (2017Q3) |
Type: | NCV: Green |
cornerstone | Mitigating Systems |
Identified by: | Self-revealing |
Inspection Procedure: | IP 71111.22 |
Inspectors (proximate) | M Young N Day R Smith M Hayes T Farina C Steely J Kozal |
Violation of: | 10 CFR 50 Appendix B Criterion V |
CCA | H.2, Field Presence |
INPO aspect | LA.2 |
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Finding - Grand Gulf - IR 05000416/2017003 | |||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||||
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Finding List (Grand Gulf) @ 2017Q3
Self-Identified List (Grand Gulf)
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