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Farley Nuclear Plant Insulation Analysis and Closure Process

This document provides detailed information on the Farley Nuclear Plant's insulation analysis and closure process, including options considered, timelines, testing plans, and proposed variances. The plant utilizes a Westinghouse 3-Loop PWR system with stringent containment cleanliness programs to meet clean plant criteria. Various strategies are discussed to justify closure decisions and address debris limits. The closure process involves industry programs, testing plans, modification timelines, and readiness reviews. Detailed actions and considerations before the 2019 deadline are outlined.

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Farley Nuclear Plant Insulation Analysis and Closure Process

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  1. Option 2a Template Example Phillip Grissom – Southern Nuclear Based on Farley (more or less) 2012-10-19

  2. Plant Information • Westinghouse 3-Loop PWR • >99.997% RMI Insulation • < 1 ft3 Temp-Mat on Steam Generator instrument lines (reference legs) in ZOI • 125 lbs Latent Debris, 18.75 lbs Latent Fiber assumed • GEH Stacked Disk Strainers 878 ft2 per each of 2 RHR trains, separate CS strainers (2) • Debris Interceptors installed but not credited

  3. GSI-191 Status • No further questions except in-vessel • Assuming 100% Bypass (157 FA) • Latent only = 54 gm/FA • With Temp-Mat = 88 gm/FA • Assume NEI Clean Plant Criteria • Latent only =18 gm/FA • With Temp-Mat = 30 gm/FA

  4. GSI-191 Closure Decision • Essentially Clean Plant, but can’t meet 15 gm/FA with standard latent debris assumptions – Options: • Additional plant specific transport and bypass analysis/testing – Option 1 • Replace Temp-Mat with RMI & implement extensive & stringent containment cleanliness program – Option 1 • Risk Informed Option 2b or 3 • Support PWROG program – Option 2a

  5. GSI-191 Closure Decision – Option 2a • PWROG testing and analysis plan could justify as-is condition by increased gm/FA • Higher fiber limit by solving differences between test facilities • Delayed or no chemical effects (affects strainer and core DP) • Higher core DP acceptance criteria via system analysis • Additional fuel tests using strainer bypass fiber characterization based on NEI fiber preparation method • Boric Acid Precipitation with fiber – justify higher fiber limit

  6. GSI-191 Schedule Clock Start 1/14 1/13 1/15 1/17 1/16 4/14 7/14 10/12 4/13 7/13 10/13 10/14 4/15 7/15 10/15 4/16 7/16 10/16 4/17 7/17 10/17 3rd Outage Industry Program WCAP SE PWROG Integrated Program U1 Outages U2 Outages Modification Timeline Design Vendor Dwgs Design Readiness Review Work Order Planning Mod Specification and PO for Engineered Items Evaluate Mods, Develop Plan, Approve Budget Farley Submittal documenting closeout plans Industry Program WCAP SE PWROG Integrated Program Farley Complete Actions before 2019

  7. Template Considerations • Believe no additional modifications beneficial for Farley • Will re-evaluate 100% bypass assumption if justified – after test protocol refined and accepted • Insufficient time (because of 18 month cycle and RFO timing) to get PWROG results and commit to 3rd RFO after 1/1/2013 (April 2016 vs. 1/1/2019)

  8. Proposed Variance with Template • Within six months of NRC SE on PWROG Program (projected fall of 2015) SNC will submit a final updated supplemental response to support closure of GL 2004-02 for Farley Units 1 & 2 (submittal projected for spring 2016). • Complete the necessary insulation replacements, remediation, or model refinements by January 1, 2019

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