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List of results

• ML16228A042  + (WCAP-18054-NP, Rev. 0, Analysis of Capsule Y from the Exelon Generation Byron Unit 1 Reactor Vessel Radiation Surveillance Program)
• BYRON 2016-0078, WCAP-18056-NP, Rev. 0, Analysis of Capsule Y from the Exelon Generation Byron Unit 2 Reactor Vessel Radiation Surveillance Program  + (WCAP-18056-NP, Rev. 0, Analysis of Capsule Y from the Exelon Generation Byron Unit 2 Reactor Vessel Radiation Surveillance Program)
• CNS-15-078, WCAP-18060-NP, Revision 1, Response to RAIs Concerning the Use of RAPTOR-M3G for the Catawba Unit 1 Measurement Uncertainty Recapture (MUR) Power Uprate Fluence Evaluations  + (WCAP-18060-NP, Revision 1, Response to RAIs Concerning the Use of RAPTOR-M3G for the Catawba Unit 1 Measurement Uncertainty Recapture (MUR) Power Uprate Fluence Evaluations)
• ML16271A451  + (WCAP-18092-NP, Revision 1, Analysis of Capsule V from the Exelon Generation Braidwood Unit 1 Reactor Vessel Radiation Surveillance Program)
• L-18-030, WCAP-18102-NP, Rev 1, Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation  + (WCAP-18102-NP, Rev 1, Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation)
• BW160072, WCAP-18107-NP, Revision 0, Analysis of Capsule V from the Exelon Generation Braidwood Unit 2 Reactor Vessel Radiation Surveillance Program  + (WCAP-18107-NP, Revision 0, Analysis of Capsule V from the Exelon Generation Braidwood Unit 2 Reactor Vessel Radiation Surveillance Program)
• ML18204A010  + (WCAP-18124-NP-A, Revision 0, Fluence Determination with RAPTOR-M3G and Ferret, July 2018)
• ML22153A139  + (WCAP-18124-NP-A, Revision 0, Supplement 1-NP-A, Revision 0, Fluence Determination with RAPTOR-M3G and Ferret - Supplement for Extended Beltline Materials)
• ML20344A388  + (WCAP-18124-NP-A, Revision 0, Supplement 1-NP, Fluence Determination with RAPTOR-M3G and Ferret - Supplement for Extended Beltline Materials)
• AEP-NRC-2018-22, WCAP-18133-NP, Revision 0, Inspection Flaw Acceptance Criteria for D.C. Cook Unit 2 Reactor Vessel Internals MRP-227-A Primary and Expansion Components  + (WCAP-18133-NP, Revision 0, Inspection Flaw Acceptance Criteria for D.C. Cook Unit 2 Reactor Vessel Internals MRP-227-A Primary and Expansion Components)
• 2CAN101602, WCAP-18166-NP, Revision 0, Analysis of Capsule 284 from the Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 Reactor Vessel Radiation Surveillance Program  + (WCAP-18166-NP, Revision 0, Analysis of Capsule 284 from the Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 Reactor Vessel Radiation Surveillance Program)
• ML18215A178  + (WCAP-18169-NP, Rev 1, Arkansas Nuclear One Unit 2 Heatup and Cooldown Limit Curves for Normal Operation)
• ML18085A161  + (WCAP-18242-NP, Rev. 0, Surry, Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity for Subsequent License Renewal)
• ML18085A164  + (WCAP-18243-NP, Rev. 0, Surry, Units 1 and 2, Heatup and Cooldown Limit Curves for Normal Operation)
• ML19204A358  + (WCAP-18258-NP, Revision 1, Flaw Tolerance Evaluation for Susceptible Reactor Coolant Loop Cast Austenitic Stainless Steel Elbow Components for Surry Units 1 and 2)
• ML18072A013  + (WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis, Using Leak-Before-Break Methodology)
• ML18334A268  + (WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology (Non-Proprietary))
• ML18072A014  + (WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis, Using Leak-Before-Before Break Methodology)
• ML18334A269  + (WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology)
• AEP-NRC-2018-02, WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis Using Leak-Before-Break Methodology  + (WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis Using Leak-Before-Break Methodology)
• ML18334A270  + (WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis for D.C. Cook, Units 1 and 2, Using Leak-Before-Break Methodology)
• ML18334A271  + (WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D.C. Cook, Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break)
• ML18274A095  + (WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D. C. Cook Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break, September 2018 (Non-Proprietary))
• NL-19-0796, WCAP-18414-NP, Rev 0, J.M. Farley Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis (Non-Proprietary Version)  + (WCAP-18414-NP, Rev 0, J.M. Farley Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis (Non-Proprietary Version))
• ML21214A338  + (WCAP-18443-NP-A, Rev 0, Qualification of the Two-Dimensional Transport Code PARAGON2)
• ML24227A593  + (WCAP-18446-NP-A, Revision 0, Incremental Extension of Burnup Limit for Westinghouse and Combustion Engineering Fuel Designs)

• ML20318A001  + (WCAP-18461-A Topical Report Verification)
• ML20318A001  + (WCAP-18461-A Topical Report Verification)

• ML20318A000  + (WCAP-18461-A Verification)
• ML20325A000  + (WCAP-18461-A Withholding Determination)
• ML20020A009  + (WCAP-18461-NP, Rev. 0, Common Q Platform and Component Interface Module System Elimination of Technical Specification Surveillance Requirements)
• ML22316A016  + (WCAP-18482-NP-A, Revision 0, Westinghouse Advanced Doped Pellet Technology (Adopttm) Fuel (Non-Proprietary))
• ML21090A113  + (WCAP-18546-NP, Westinghouse Axiom Cladding for Use in Pressurized Water Reactor Fuel)
• ML23089A066  + (WCAP-18546-NP-A, Revision 0, Westinghouse Axiom Cladding for Use in Pressurized Water Reactor Fuel)
• ML20302A377  + (WCAP-18558-NP, Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program. Part 1 of 4)
• ML20302A381  + (WCAP-18558-NP, Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program. Part 3 of 4)
• ML20302A380  + (WCAP-18558-NP, Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program. Part 2 of 4)
• ML20302A376  + (WCAP-18558-NP, Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program.)
• L-20-208, WCAP-18558-NP, Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program. Part 4 of 4  + (WCAP-18558-NP, Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program. Part 4 of 4)
• EPID:L-2020-LLL-0023  + (WCAP-18558-NP, Analysis of Capsule Y from the Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program. Part 4 of 4)
• ML22067A150  + (WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Section 6 Through Appendix B)
• ML22067A154  + (WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 4)
• ML22067A152  + (WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 2)
• L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D  + (WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D)
• ML22067A149  + (WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Cover Through Section 5)
• ML22067A153  + (WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 3)
• ML22067A151  + (WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 1)
• L-PI-23-002, WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7)  + (WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 7 of 7))
• ML23075A349  + (WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 4 of 7))
• ML23075A347  + (WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 2 of 7))
• ML23075A348  + (WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 3 of 7))
• ML23075A351  + (WCAP-18795-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, (Part 6 of 7))