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{{#Wiki_filter:NRCR11001 Submitted: Mar. 18, 2015 | {{#Wiki_filter:NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | ||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000171 NYS-26 NYS-38 EPRI 1015014, Materials Reliability Program: Evaluation of Controlling Transient Ramp Times Using Piping Methodologies When Considering Environmental Fatigue (F en) Effects (MRP-218) (Sept. 2007) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000172 NYS-26 NYS-38 EPRI 1003536, Materials Reliability Program: Second International Conference on Fatigue of Reactor Components (MRP-84) (Feb. 2003) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000173 NYS-26 NYS-38 Excerpt from Transcript of Advisory Committee on Reactor Safeguards Metallurgy and Reactor Fuels Subcommittee at 105-106 (Dec. 2, 2014) 08/10/2015 NRC000174 NYS-26 NYS-38 Background of the Factors of Safety Used in Divisions I of Sections III and XI of the ASME Rules for Nuclear Vessels (Oct. 1984) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000175 NYS-26 NYS-38 Implementation of Automated, On-line Fatigue Monitoring in a Boiling Water Reactor (1993) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000176 NYS-26 NYS-38 EPRI 1003069, Materials Reliability Program Hot Cell Testing of Baffle/Former Bolts Removed From Two Lead PWR Plants (MRP-51) | |||
(Nov. 2001) (PROPRIETARY) 08/10/2015 NRC000177 NYS-26 NYS-38 ICONE5-2372, Fatigue and Stress Corrosion Cracking Behaviors of Irradiated Stainless Steels in PWR Primary Water (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000178 NYS-26 NYS-38 ASME Code, Section III - Subsection NCA, General Requirements for Division 1 and Division 2 Rules for Construction of Nuclear Facility Components (Jul. 1, 2007) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000179 NYS-26 NYS-38 Regulatory Guide 1.207, Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Mar. 2007) 08/10/2015 NRC000180 NYS-26 NYS-38 NRC Inspection Manual, Chapter 2516, Policy and Guidance for the License Renewal Inspection Program (Aug. 13, 2013) 08/10/2015 NRC000181 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013009 (July 5, 2013) 08/10/2015 NRC000182 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013010 (Sept. 19, 2013) 08/10/2015 NRC000183 NYS-26 NYS-38 NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) 08/10/2015 NRC000184 NYS-25 NYS-26 NYS-38 Letter NL-13-114, Letter from Fred Dacimo, Entergy, to NRC, Implementation of License Renewal Regulatory Commitments Indian Point Nuclear Generating Unit No. 2 Docket No. 50-257 License No. DPR-26 (Aug. 28, 2013) 08/10/2015 NRC000185 NYS-26 NYS-38 Letter from Arthur Burritt, NRC, to Larry Coyle, Entergy, Annual Assessment Letter for Indian Point Nuclear Generating Units 2 and 3 (Report 05000247/2014001 and 05000286/2014001) (Mar. 4, 2015) 08/10/2015 NRC000186 NYS-26 NYS-38 Effect of LWR Coolant Environments on the Fatigue of Reactor Materials, 79 Fed. Reg. 21811 (Apr. 17, 2014) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000187 NYS-26 NYS-38 Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and MD5408) ( Feb. 6, 2013) 08/10/2015 NRC000188 NYS-26 NYS-38 Letter NL-15-060, Letter from Fred Dacimo, Entergy, to NRC, Entergy Actions Required Prior to Entry into Period of Extended Operation Associated with License Renewal Application (LRA) for Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64 (May 12, 2015) 08/10/2015 NRC000189 NYS-38 TSTF-510, Rev. 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Mar. 1, 2011) 08/10/2015 NRC000190 NYS-38 NRC White Paper on Risk-Informed and Performance-Based Regulation 08/10/2015 NRC000191 NYS-38 Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 79 | |||
NRCR11001 Submitted: Mar. 18, 2015 | Fed. Reg. 15144 (Mar. 18, 2014) 08/10/2015 NRC000192 NYS-38 Letter NL-15-001, Letter from Lawrence Coyle, to NRC, Response to Request for Additional Information (RAI) for the Steam Generator Examination Program Results 2014 Refueling Outage (2R21) Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26 (Jan. 15, 2015) 08/10/2015 NRC000193 NYS-38 Letter NL-13-143, Letter from Robert Walpole, to NRC, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Performed During the Spring 2013 Refueling Outage Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64 (Oct. 29, 2013) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | ||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000194 NYS-38 S. Miloudi et al, Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress Corrosion Cracks, in 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (2012) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000195 NYS-26 NYS-38 ASME Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2007 through 2008 Addenda, IWB-2500, Table IWB-2500-1, IWB,3700, IWC-2500, Table IWC-2500-1(Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000196 NYS-25 NRC Staff's Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) (PROPRIETARY) 08/10/2015 NRC000197 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 (PROPRIETARY) 08/10/2015 NRC000198 NYS-25 Enclosure to MRP Letter 2013-025, MRP-227-A Applicability Guidelines for Combustion Engineering and Westinghouse Pressurized Water Reactor Designs (Oct. 4, 2013) 08/10/2015 NRC000199 NYS-25 ASME Code, Section XI, 2007 through 2008 Addenda, IWA-2213 (Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000200 NYS-25 WCAP-17096-NP, Rev. 2, Reactor Internals Acceptance Criteria Methodology and Data Requirements (Dec. 2009) 08/10/2015 NRC000201 NYS-25 "NRC Position on Aging Management of CASS Reactor Vessel Internal Components" (June 11, 2014) 08/10/2015 NRC000202 NYS-25 ASM Handbook, Vol. 19, Fatigue and Fracture, Figure 14 at 595 (1996) (EXCERPT ) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000203 NYS-25 EPRI 1021001NP/BWRVIP-100NP, Final Report, Rev. 1, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Oct. 2010) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000204 NYS-25 PWROG-14048-P, Rev. 0, Functionality Analysis: Lower Support Columns (Dec. 2014) (PROPRIETARY) 08/10/2015 NRC000205 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 3 - Reactor (2014) 08/10/2015 NRC000206 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 14 - Safety Analysis (2014) 08/10/2015 NRC000207 NYS-25 Regulatory Information Conference Presentation Slides, "Recent Materials Inspections of PWR Reactor Internals" (Mar. 2015) 08/10/2015 NRC00208A | |||
- NRC00208E NYS-25 MRP Letter 2014-09, Biennial Report of Recent MRP-227-A Reactor Internals Inspection Results (May 12, 2014) 08/10/2015 NRC000209 NYS-25 EPRI 1013396/BWRVIP-100-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (PROPRIETARY) 08/10/2015 NRC000210 NYS-25 EPRI 1013396NP/ BWRVIP-100NP-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000211 NYS-25 MRP-227, Rev. 1 Presentation Slides, Westinghouse Figures Presented at Public Meeting on March 31, 2015 (Feb. 2015) 08/10/2015 | |||
NRCR11001 Submitted: Mar. 18, 2015 | NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | ||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000220 NYS-25 Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, "Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update," (June 2014) 08/10/2015 NRC00221A | |||
- NRC00221F NYS-25 Babcock & Wilcox Report, S-1473-002, Final Report, Rev. 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant (Dec. 2013) 08/10/2015 NRC000222 NYS-25 IP3 FSAR Rev. 04 Chapter 3 (2011) (EXCERPT) 08/10/2015 NRC000223 NYS-25 IP3 FSAR Rev. 04 Chapter 14 (2011) 08/10/2015 NRC000224 NYS-25 IP3 FSAR Rev. 04 Chapter 16 08/10/2015 NRC00225A | |||
- NRC00225B NYS-25 EPRI 1016593, Final Report, Materials Reliability Program: Aging Management Strategies for Westinghouse and Combustion Engineering PWR Internals (MRP-232) (Dec. 31, 2008) (PROPRIETARY) 08/10/2015 NRC000226 NYS-25 NYS-38 Jeffrey C. Poehler Statement of Professional Qualifications 08/10/2015 NRC000227 NYS-25 NYS-26 NYS-38 Gary Stevens Statement of Professional Qualifications 08/10/2015 NRC000228 NYS-25 Indian Point Unit 2 Technical Specifications 3.1.4 08/10/2015 NRC000229 NYS-25 Indian Point Unit 3 Technical Specifications 3.1.4 08/10/2015 NRC000230 NYS-25 NYS-26 NYS-38 Table of Corrections to Staff Testimony 11/03/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PROPRIETARY) 03/18/2016 NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PUBLIC, REDACTED) 03/18/2016 NRC000232 NYS-25 NYS-38 BWRVIP-99-A, Final Report, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (Oct. 2008) (PROPRIETARY) | |||
(EXCERPT) 03/18/2016 NRC000233 NYS-25 NYS-38 BWRVIP-99, Final Report, BWR Vessel and Internals Project Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components. (Dec. 2001) | |||
(PROPRIETARY) | |||
(EXCERPT) 03/18/2016 NRC000234 NYS-25 NYS-38 BWRVIP-14-A, Final Report, BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (Sept. 2008) | |||
(PROPRIETARY) | |||
(EXCERPT) 03/18/2016 NRC000235 NYS-25 NYS-38 EPRI MRP 2-14-002, Proposed Edits to WCAP-17096-A Draft (Jan. 16, 2014) 03/18/2016 NRC000236 NYS-25 NYS-38 Crack Growth Rate Comparison - Eason-Pathania Model to MRP Model- Excel Spreadsheet 03/18/2016 | |||
NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. (Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits | NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | ||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000171 NYS-26 NYS-38 EPRI 1015014, Materials Reliability Program: Evaluation of Controlling Transient Ramp Times Using Piping Methodologies When Considering Environmental Fatigue (F en) Effects (MRP-218) (Sept. 2007) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000172 NYS-26 NYS-38 EPRI 1003536, Materials Reliability Program: Second International Conference on Fatigue of Reactor Components (MRP-84) (Feb. 2003) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000173 NYS-26 NYS-38 Excerpt from Transcript of Advisory Committee on Reactor Safeguards Metallurgy and Reactor Fuels Subcommittee at 105-106 (Dec. 2, 2014) 08/10/2015 NRC000174 NYS-26 NYS-38 Background of the Factors of Safety Used in Divisions I of Sections III and XI of the ASME Rules for Nuclear Vessels (Oct. 1984) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000175 NYS-26 NYS-38 Implementation of Automated, On-line Fatigue Monitoring in a Boiling Water Reactor (1993) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000176 NYS-26 NYS-38 EPRI 1003069, Materials Reliability Program Hot Cell Testing of Baffle/Former Bolts Removed From Two Lead PWR Plants (MRP-51) | |||
(Nov. 2001) (PROPRIETARY) 08/10/2015 NRC000177 NYS-26 NYS-38 ICONE5-2372, Fatigue and Stress Corrosion Cracking Behaviors of Irradiated Stainless Steels in PWR Primary Water (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000178 NYS-26 NYS-38 ASME Code, Section III - Subsection NCA, General Requirements for Division 1 and Division 2 Rules for Construction of Nuclear Facility Components (Jul. 1, 2007) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000179 NYS-26 NYS-38 Regulatory Guide 1.207, Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Mar. 2007) 08/10/2015 NRC000180 NYS-26 NYS-38 NRC Inspection Manual, Chapter 2516, Policy and Guidance for the License Renewal Inspection Program (Aug. 13, 2013) 08/10/2015 NRC000181 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013009 (July 5, 2013) 08/10/2015 NRC000182 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013010 (Sept. 19, 2013) 08/10/2015 NRC000183 NYS-26 NYS-38 NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) 08/10/2015 NRC000184 NYS-25 NYS-26 NYS-38 Letter NL-13-114, Letter from Fred Dacimo, Entergy, to NRC, Implementation of License Renewal Regulatory Commitments Indian Point Nuclear Generating Unit No. 2 Docket No. 50-257 License No. DPR-26 (Aug. 28, 2013) 08/10/2015 NRC000185 NYS-26 NYS-38 Letter from Arthur Burritt, NRC, to Larry Coyle, Entergy, Annual Assessment Letter for Indian Point Nuclear Generating Units 2 and 3 (Report 05000247/2014001 and 05000286/2014001) (Mar. 4, 2015) 08/10/2015 NRC000186 NYS-26 NYS-38 Effect of LWR Coolant Environments on the Fatigue of Reactor Materials, 79 Fed. Reg. 21811 (Apr. 17, 2014) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000187 NYS-26 NYS-38 Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and MD5408) ( Feb. 6, 2013) 08/10/2015 NRC000188 NYS-26 NYS-38 Letter NL-15-060, Letter from Fred Dacimo, Entergy, to NRC, Entergy Actions Required Prior to Entry into Period of Extended Operation Associated with License Renewal Application (LRA) for Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64 (May 12, 2015) 08/10/2015 NRC000189 NYS-38 TSTF-510, Rev. 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Mar. 1, 2011) 08/10/2015 NRC000190 NYS-38 NRC White Paper on Risk-Informed and Performance-Based Regulation 08/10/2015 NRC000191 NYS-38 Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 79 | |||
Fed. Reg. 15144 (Mar. 18, 2014) 08/10/2015 NRC000192 NYS-38 Letter NL-15-001, Letter from Lawrence Coyle, to NRC, Response to Request for Additional Information (RAI) for the Steam Generator Examination Program Results 2014 Refueling Outage (2R21) Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26 (Jan. 15, 2015) 08/10/2015 NRC000193 NYS-38 Letter NL-13-143, Letter from Robert Walpole, to NRC, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Performed During the Spring 2013 Refueling Outage Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64 (Oct. 29, 2013) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000194 NYS-38 S. Miloudi et al, Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress Corrosion Cracks, in 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (2012) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000195 NYS-26 NYS-38 ASME Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2007 through 2008 Addenda, IWB-2500, Table IWB-2500-1, IWB,3700, IWC-2500, Table IWC-2500-1(Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000196 NYS-25 NRC Staff's Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) (PROPRIETARY) 08/10/2015 NRC000197 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 (PROPRIETARY) 08/10/2015 NRC000198 NYS-25 Enclosure to MRP Letter 2013-025, MRP-227-A Applicability Guidelines for Combustion Engineering and Westinghouse Pressurized Water Reactor Designs (Oct. 4, 2013) 08/10/2015 NRC000199 NYS-25 ASME Code, Section XI, 2007 through 2008 Addenda, IWA-2213 (Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000200 NYS-25 WCAP-17096-NP, Rev. 2, Reactor Internals Acceptance Criteria Methodology and Data Requirements (Dec. 2009) 08/10/2015 NRC000201 NYS-25 "NRC Position on Aging Management of CASS Reactor Vessel Internal Components" (June 11, 2014) 08/10/2015 NRC000202 NYS-25 ASM Handbook, Vol. 19, Fatigue and Fracture, Figure 14 at 595 (1996) (EXCERPT ) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000203 NYS-25 EPRI 1021001NP/BWRVIP-100NP, Final Report, Rev. 1, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Oct. 2010) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000204 NYS-25 PWROG-14048-P, Rev. 0, Functionality Analysis: Lower Support Columns (Dec. 2014) (PROPRIETARY) 08/10/2015 NRC000205 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 3 - Reactor (2014) 08/10/2015 NRC000206 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 14 - Safety Analysis (2014) 08/10/2015 NRC000207 NYS-25 Regulatory Information Conference Presentation Slides, "Recent Materials Inspections of PWR Reactor Internals" (Mar. 2015) 08/10/2015 NRC00208A | |||
- NRC00208E NYS-25 MRP Letter 2014-09, Biennial Report of Recent MRP-227-A Reactor Internals Inspection Results (May 12, 2014) 08/10/2015 NRC000209 NYS-25 EPRI 1013396/BWRVIP-100-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (PROPRIETARY) 08/10/2015 NRC000210 NYS-25 EPRI 1013396NP/ BWRVIP-100NP-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000211 NYS-25 MRP-227, Rev. 1 Presentation Slides, Westinghouse Figures Presented at Public Meeting on March 31, 2015 (Feb. 2015) 08/10/2015 | |||
NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000220 NYS-25 Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, "Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update," (June 2014) 08/10/2015 NRC00221A | |||
- NRC00221F NYS-25 Babcock & Wilcox Report, S-1473-002, Final Report, Rev. 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant (Dec. 2013) 08/10/2015 NRC000222 NYS-25 IP3 FSAR Rev. 04 Chapter 3 (2011) (EXCERPT) 08/10/2015 NRC000223 NYS-25 IP3 FSAR Rev. 04 Chapter 14 (2011) 08/10/2015 NRC000224 NYS-25 IP3 FSAR Rev. 04 Chapter 16 08/10/2015 NRC00225A | |||
- NRC00225B NYS-25 EPRI 1016593, Final Report, Materials Reliability Program: Aging Management Strategies for Westinghouse and Combustion Engineering PWR Internals (MRP-232) (Dec. 31, 2008) (PROPRIETARY) 08/10/2015 NRC000226 NYS-25 NYS-38 Jeffrey C. Poehler Statement of Professional Qualifications 08/10/2015 NRC000227 NYS-25 NYS-26 NYS-38 Gary Stevens Statement of Professional Qualifications 08/10/2015 NRC000228 NYS-25 Indian Point Unit 2 Technical Specifications 3.1.4 08/10/2015 NRC000229 NYS-25 Indian Point Unit 3 Technical Specifications 3.1.4 08/10/2015 NRC000230 NYS-25 NYS-26 NYS-38 Table of Corrections to Staff Testimony 11/03/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc. | |||
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PROPRIETARY) 03/18/2016 NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PUBLIC, REDACTED) 03/18/2016 NRC000232 NYS-25 NYS-38 BWRVIP-99-A, Final Report, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (Oct. 2008) (PROPRIETARY) | |||
(EXCERPT) 03/18/2016 NRC000233 NYS-25 NYS-38 BWRVIP-99, Final Report, BWR Vessel and Internals Project Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components. (Dec. 2001) | |||
(PROPRIETARY) | |||
(EXCERPT) 03/18/2016 NRC000234 NYS-25 NYS-38 BWRVIP-14-A, Final Report, BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (Sept. 2008) | |||
(PROPRIETARY) | |||
(EXCERPT) 03/18/2016 NRC000235 NYS-25 NYS-38 EPRI MRP 2-14-002, Proposed Edits to WCAP-17096-A Draft (Jan. 16, 2014) 03/18/2016 NRC000236 NYS-25 NYS-38 Crack Growth Rate Comparison - Eason-Pathania Model to MRP Model- Excel Spreadsheet 03/18/2016}} | |||
Revision as of 10:50, 30 June 2018
| ML16078A413 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/18/2016 |
| From: | NRC/OGC |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 51011, ASLBP 07-858-03-LR-BD01, 50-286-LR, 50-247-LR | |
| Download: ML16078A413 (31) | |
Text
NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000171 NYS-26 NYS-38 EPRI 1015014, Materials Reliability Program: Evaluation of Controlling Transient Ramp Times Using Piping Methodologies When Considering Environmental Fatigue (F en) Effects (MRP-218) (Sept. 2007) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000172 NYS-26 NYS-38 EPRI 1003536, Materials Reliability Program: Second International Conference on Fatigue of Reactor Components (MRP-84) (Feb. 2003) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000173 NYS-26 NYS-38 Excerpt from Transcript of Advisory Committee on Reactor Safeguards Metallurgy and Reactor Fuels Subcommittee at 105-106 (Dec. 2, 2014) 08/10/2015 NRC000174 NYS-26 NYS-38 Background of the Factors of Safety Used in Divisions I of Sections III and XI of the ASME Rules for Nuclear Vessels (Oct. 1984) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000175 NYS-26 NYS-38 Implementation of Automated, On-line Fatigue Monitoring in a Boiling Water Reactor (1993) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000176 NYS-26 NYS-38 EPRI 1003069, Materials Reliability Program Hot Cell Testing of Baffle/Former Bolts Removed From Two Lead PWR Plants (MRP-51)
(Nov. 2001) (PROPRIETARY) 08/10/2015 NRC000177 NYS-26 NYS-38 ICONE5-2372, Fatigue and Stress Corrosion Cracking Behaviors of Irradiated Stainless Steels in PWR Primary Water (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000178 NYS-26 NYS-38 ASME Code,Section III - Subsection NCA, General Requirements for Division 1 and Division 2 Rules for Construction of Nuclear Facility Components (Jul. 1, 2007) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000179 NYS-26 NYS-38 Regulatory Guide 1.207, Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Mar. 2007) 08/10/2015 NRC000180 NYS-26 NYS-38 NRC Inspection Manual, Chapter 2516, Policy and Guidance for the License Renewal Inspection Program (Aug. 13, 2013) 08/10/2015 NRC000181 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013009 (July 5, 2013) 08/10/2015 NRC000182 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013010 (Sept. 19, 2013) 08/10/2015 NRC000183 NYS-26 NYS-38 NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) 08/10/2015 NRC000184 NYS-25 NYS-26 NYS-38 Letter NL-13-114, Letter from Fred Dacimo, Entergy, to NRC, Implementation of License Renewal Regulatory Commitments Indian Point Nuclear Generating Unit No. 2 Docket No. 50-257 License No. DPR-26 (Aug. 28, 2013) 08/10/2015 NRC000185 NYS-26 NYS-38 Letter from Arthur Burritt, NRC, to Larry Coyle, Entergy, Annual Assessment Letter for Indian Point Nuclear Generating Units 2 and 3 (Report 05000247/2014001 and 05000286/2014001) (Mar. 4, 2015) 08/10/2015 NRC000186 NYS-26 NYS-38 Effect of LWR Coolant Environments on the Fatigue of Reactor Materials, 79 Fed. Reg. 21811 (Apr. 17, 2014) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000187 NYS-26 NYS-38 Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and MD5408) ( Feb. 6, 2013) 08/10/2015 NRC000188 NYS-26 NYS-38 Letter NL-15-060, Letter from Fred Dacimo, Entergy, to NRC, Entergy Actions Required Prior to Entry into Period of Extended Operation Associated with License Renewal Application (LRA) for Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64 (May 12, 2015) 08/10/2015 NRC000189 NYS-38 TSTF-510, Rev. 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Mar. 1, 2011) 08/10/2015 NRC000190 NYS-38 NRC White Paper on Risk-Informed and Performance-Based Regulation 08/10/2015 NRC000191 NYS-38 Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 79
Fed. Reg. 15144 (Mar. 18, 2014) 08/10/2015 NRC000192 NYS-38 Letter NL-15-001, Letter from Lawrence Coyle, to NRC, Response to Request for Additional Information (RAI) for the Steam Generator Examination Program Results 2014 Refueling Outage (2R21) Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26 (Jan. 15, 2015) 08/10/2015 NRC000193 NYS-38 Letter NL-13-143, Letter from Robert Walpole, to NRC, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Performed During the Spring 2013 Refueling Outage Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64 (Oct. 29, 2013) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000194 NYS-38 S. Miloudi et al, Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress Corrosion Cracks, in 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (2012) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000195 NYS-26 NYS-38 ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2007 through 2008 Addenda, IWB-2500, Table IWB-2500-1, IWB,3700, IWC-2500, Table IWC-2500-1(Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000196 NYS-25 NRC Staff's Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) (PROPRIETARY) 08/10/2015 NRC000197 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 (PROPRIETARY) 08/10/2015 NRC000198 NYS-25 Enclosure to MRP Letter 2013-025, MRP-227-A Applicability Guidelines for Combustion Engineering and Westinghouse Pressurized Water Reactor Designs (Oct. 4, 2013) 08/10/2015 NRC000199 NYS-25 ASME Code,Section XI, 2007 through 2008 Addenda, IWA-2213 (Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000200 NYS-25 WCAP-17096-NP, Rev. 2, Reactor Internals Acceptance Criteria Methodology and Data Requirements (Dec. 2009) 08/10/2015 NRC000201 NYS-25 "NRC Position on Aging Management of CASS Reactor Vessel Internal Components" (June 11, 2014) 08/10/2015 NRC000202 NYS-25 ASM Handbook, Vol. 19, Fatigue and Fracture, Figure 14 at 595 (1996) (EXCERPT ) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000203 NYS-25 EPRI 1021001NP/BWRVIP-100NP, Final Report, Rev. 1, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Oct. 2010) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000204 NYS-25 PWROG-14048-P, Rev. 0, Functionality Analysis: Lower Support Columns (Dec. 2014) (PROPRIETARY) 08/10/2015 NRC000205 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 3 - Reactor (2014) 08/10/2015 NRC000206 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 14 - Safety Analysis (2014) 08/10/2015 NRC000207 NYS-25 Regulatory Information Conference Presentation Slides, "Recent Materials Inspections of PWR Reactor Internals" (Mar. 2015) 08/10/2015 NRC00208A
- NRC00208E NYS-25 MRP Letter 2014-09, Biennial Report of Recent MRP-227-A Reactor Internals Inspection Results (May 12, 2014) 08/10/2015 NRC000209 NYS-25 EPRI 1013396/BWRVIP-100-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (PROPRIETARY) 08/10/2015 NRC000210 NYS-25 EPRI 1013396NP/ BWRVIP-100NP-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000211 NYS-25 MRP-227, Rev. 1 Presentation Slides, Westinghouse Figures Presented at Public Meeting on March 31, 2015 (Feb. 2015) 08/10/2015
NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000220 NYS-25 Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, "Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update," (June 2014) 08/10/2015 NRC00221A
- NRC00221F NYS-25 Babcock & Wilcox Report, S-1473-002, Final Report, Rev. 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant (Dec. 2013) 08/10/2015 NRC000222 NYS-25 IP3 FSAR Rev. 04 Chapter 3 (2011) (EXCERPT) 08/10/2015 NRC000223 NYS-25 IP3 FSAR Rev. 04 Chapter 14 (2011) 08/10/2015 NRC000224 NYS-25 IP3 FSAR Rev. 04 Chapter 16 08/10/2015 NRC00225A
- NRC00225B NYS-25 EPRI 1016593, Final Report, Materials Reliability Program: Aging Management Strategies for Westinghouse and Combustion Engineering PWR Internals (MRP-232) (Dec. 31, 2008) (PROPRIETARY) 08/10/2015 NRC000226 NYS-25 NYS-38 Jeffrey C. Poehler Statement of Professional Qualifications 08/10/2015 NRC000227 NYS-25 NYS-26 NYS-38 Gary Stevens Statement of Professional Qualifications 08/10/2015 NRC000228 NYS-25 Indian Point Unit 2 Technical Specifications 3.1.4 08/10/2015 NRC000229 NYS-25 Indian Point Unit 3 Technical Specifications 3.1.4 08/10/2015 NRC000230 NYS-25 NYS-26 NYS-38 Table of Corrections to Staff Testimony 11/03/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PROPRIETARY) 03/18/2016 NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PUBLIC, REDACTED) 03/18/2016 NRC000232 NYS-25 NYS-38 BWRVIP-99-A, Final Report, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (Oct. 2008) (PROPRIETARY)
(EXCERPT) 03/18/2016 NRC000233 NYS-25 NYS-38 BWRVIP-99, Final Report, BWR Vessel and Internals Project Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components. (Dec. 2001)
(PROPRIETARY)
(EXCERPT) 03/18/2016 NRC000234 NYS-25 NYS-38 BWRVIP-14-A, Final Report, BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (Sept. 2008)
(PROPRIETARY)
(EXCERPT) 03/18/2016 NRC000235 NYS-25 NYS-38 EPRI MRP 2-14-002, Proposed Edits to WCAP-17096-A Draft (Jan. 16, 2014) 03/18/2016 NRC000236 NYS-25 NYS-38 Crack Growth Rate Comparison - Eason-Pathania Model to MRP Model- Excel Spreadsheet 03/18/2016
NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000171 NYS-26 NYS-38 EPRI 1015014, Materials Reliability Program: Evaluation of Controlling Transient Ramp Times Using Piping Methodologies When Considering Environmental Fatigue (F en) Effects (MRP-218) (Sept. 2007) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000172 NYS-26 NYS-38 EPRI 1003536, Materials Reliability Program: Second International Conference on Fatigue of Reactor Components (MRP-84) (Feb. 2003) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000173 NYS-26 NYS-38 Excerpt from Transcript of Advisory Committee on Reactor Safeguards Metallurgy and Reactor Fuels Subcommittee at 105-106 (Dec. 2, 2014) 08/10/2015 NRC000174 NYS-26 NYS-38 Background of the Factors of Safety Used in Divisions I of Sections III and XI of the ASME Rules for Nuclear Vessels (Oct. 1984) (EXCERPT) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000175 NYS-26 NYS-38 Implementation of Automated, On-line Fatigue Monitoring in a Boiling Water Reactor (1993) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000176 NYS-26 NYS-38 EPRI 1003069, Materials Reliability Program Hot Cell Testing of Baffle/Former Bolts Removed From Two Lead PWR Plants (MRP-51)
(Nov. 2001) (PROPRIETARY) 08/10/2015 NRC000177 NYS-26 NYS-38 ICONE5-2372, Fatigue and Stress Corrosion Cracking Behaviors of Irradiated Stainless Steels in PWR Primary Water (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000178 NYS-26 NYS-38 ASME Code,Section III - Subsection NCA, General Requirements for Division 1 and Division 2 Rules for Construction of Nuclear Facility Components (Jul. 1, 2007) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000179 NYS-26 NYS-38 Regulatory Guide 1.207, Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Mar. 2007) 08/10/2015 NRC000180 NYS-26 NYS-38 NRC Inspection Manual, Chapter 2516, Policy and Guidance for the License Renewal Inspection Program (Aug. 13, 2013) 08/10/2015 NRC000181 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013009 (July 5, 2013) 08/10/2015 NRC000182 NYS-26 NYS-38 Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013010 (Sept. 19, 2013) 08/10/2015 NRC000183 NYS-26 NYS-38 NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) 08/10/2015 NRC000184 NYS-25 NYS-26 NYS-38 Letter NL-13-114, Letter from Fred Dacimo, Entergy, to NRC, Implementation of License Renewal Regulatory Commitments Indian Point Nuclear Generating Unit No. 2 Docket No. 50-257 License No. DPR-26 (Aug. 28, 2013) 08/10/2015 NRC000185 NYS-26 NYS-38 Letter from Arthur Burritt, NRC, to Larry Coyle, Entergy, Annual Assessment Letter for Indian Point Nuclear Generating Units 2 and 3 (Report 05000247/2014001 and 05000286/2014001) (Mar. 4, 2015) 08/10/2015 NRC000186 NYS-26 NYS-38 Effect of LWR Coolant Environments on the Fatigue of Reactor Materials, 79 Fed. Reg. 21811 (Apr. 17, 2014) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000187 NYS-26 NYS-38 Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and MD5408) ( Feb. 6, 2013) 08/10/2015 NRC000188 NYS-26 NYS-38 Letter NL-15-060, Letter from Fred Dacimo, Entergy, to NRC, Entergy Actions Required Prior to Entry into Period of Extended Operation Associated with License Renewal Application (LRA) for Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64 (May 12, 2015) 08/10/2015 NRC000189 NYS-38 TSTF-510, Rev. 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Mar. 1, 2011) 08/10/2015 NRC000190 NYS-38 NRC White Paper on Risk-Informed and Performance-Based Regulation 08/10/2015 NRC000191 NYS-38 Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 79
Fed. Reg. 15144 (Mar. 18, 2014) 08/10/2015 NRC000192 NYS-38 Letter NL-15-001, Letter from Lawrence Coyle, to NRC, Response to Request for Additional Information (RAI) for the Steam Generator Examination Program Results 2014 Refueling Outage (2R21) Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26 (Jan. 15, 2015) 08/10/2015 NRC000193 NYS-38 Letter NL-13-143, Letter from Robert Walpole, to NRC, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Performed During the Spring 2013 Refueling Outage Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64 (Oct. 29, 2013) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000194 NYS-38 S. Miloudi et al, Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress Corrosion Cracks, in 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors (2012) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000195 NYS-26 NYS-38 ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, 2007 through 2008 Addenda, IWB-2500, Table IWB-2500-1, IWB,3700, IWC-2500, Table IWC-2500-1(Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000196 NYS-25 NRC Staff's Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) (PROPRIETARY) 08/10/2015 NRC000197 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 (PROPRIETARY) 08/10/2015 NRC000198 NYS-25 Enclosure to MRP Letter 2013-025, MRP-227-A Applicability Guidelines for Combustion Engineering and Westinghouse Pressurized Water Reactor Designs (Oct. 4, 2013) 08/10/2015 NRC000199 NYS-25 ASME Code,Section XI, 2007 through 2008 Addenda, IWA-2213 (Jul. 1, 2008) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000200 NYS-25 WCAP-17096-NP, Rev. 2, Reactor Internals Acceptance Criteria Methodology and Data Requirements (Dec. 2009) 08/10/2015 NRC000201 NYS-25 "NRC Position on Aging Management of CASS Reactor Vessel Internal Components" (June 11, 2014) 08/10/2015 NRC000202 NYS-25 ASM Handbook, Vol. 19, Fatigue and Fracture, Figure 14 at 595 (1996) (EXCERPT ) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000203 NYS-25 EPRI 1021001NP/BWRVIP-100NP, Final Report, Rev. 1, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Oct. 2010) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000204 NYS-25 PWROG-14048-P, Rev. 0, Functionality Analysis: Lower Support Columns (Dec. 2014) (PROPRIETARY) 08/10/2015 NRC000205 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 3 - Reactor (2014) 08/10/2015 NRC000206 NYS-25 Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 25, Chapter 14 - Safety Analysis (2014) 08/10/2015 NRC000207 NYS-25 Regulatory Information Conference Presentation Slides, "Recent Materials Inspections of PWR Reactor Internals" (Mar. 2015) 08/10/2015 NRC00208A
- NRC00208E NYS-25 MRP Letter 2014-09, Biennial Report of Recent MRP-227-A Reactor Internals Inspection Results (May 12, 2014) 08/10/2015 NRC000209 NYS-25 EPRI 1013396/BWRVIP-100-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (PROPRIETARY) 08/10/2015 NRC000210 NYS-25 EPRI 1013396NP/ BWRVIP-100NP-A, Final Report, BWR Vessel and Internals Project, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds (Aug. 2006) (CONTAINS COPYRIGHTED MATERIAL) 08/10/2015 NRC000211 NYS-25 MRP-227, Rev. 1 Presentation Slides, Westinghouse Figures Presented at Public Meeting on March 31, 2015 (Feb. 2015) 08/10/2015
NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000220 NYS-25 Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, "Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update," (June 2014) 08/10/2015 NRC00221A
- NRC00221F NYS-25 Babcock & Wilcox Report, S-1473-002, Final Report, Rev. 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant (Dec. 2013) 08/10/2015 NRC000222 NYS-25 IP3 FSAR Rev. 04 Chapter 3 (2011) (EXCERPT) 08/10/2015 NRC000223 NYS-25 IP3 FSAR Rev. 04 Chapter 14 (2011) 08/10/2015 NRC000224 NYS-25 IP3 FSAR Rev. 04 Chapter 16 08/10/2015 NRC00225A
- NRC00225B NYS-25 EPRI 1016593, Final Report, Materials Reliability Program: Aging Management Strategies for Westinghouse and Combustion Engineering PWR Internals (MRP-232) (Dec. 31, 2008) (PROPRIETARY) 08/10/2015 NRC000226 NYS-25 NYS-38 Jeffrey C. Poehler Statement of Professional Qualifications 08/10/2015 NRC000227 NYS-25 NYS-26 NYS-38 Gary Stevens Statement of Professional Qualifications 08/10/2015 NRC000228 NYS-25 Indian Point Unit 2 Technical Specifications 3.1.4 08/10/2015 NRC000229 NYS-25 Indian Point Unit 3 Technical Specifications 3.1.4 08/10/2015 NRC000230 NYS-25 NYS-26 NYS-38 Table of Corrections to Staff Testimony 11/03/2015 NRCR11001 Submitted: Mar. 18, 2015 Entergy Nuclear Operations, Inc.
(Indian Point Units 2 and 3) Docket Nos. 50-247-LR and 50-286-LR ASLBP No. 07-858-03-LR-BD01 Evidentiary Hearing NRC Staff Hearing Exhibits NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PROPRIETARY) 03/18/2016 NRC000231 NYS-25 NYS-38 NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, Dr. Ching Ng, and On Yee Regarding NYS-25, NYS-26B, and NYS-38/RK-TC-5 (PUBLIC, REDACTED) 03/18/2016 NRC000232 NYS-25 NYS-38 BWRVIP-99-A, Final Report, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (Oct. 2008) (PROPRIETARY)
(EXCERPT) 03/18/2016 NRC000233 NYS-25 NYS-38 BWRVIP-99, Final Report, BWR Vessel and Internals Project Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components. (Dec. 2001)
(PROPRIETARY)
(EXCERPT) 03/18/2016 NRC000234 NYS-25 NYS-38 BWRVIP-14-A, Final Report, BWR Vessel and Internals Project, Evaluation of Crack Growth in BWR Stainless Steel RPV Internals (Sept. 2008)
(PROPRIETARY)
(EXCERPT) 03/18/2016 NRC000235 NYS-25 NYS-38 EPRI MRP 2-14-002, Proposed Edits to WCAP-17096-A Draft (Jan. 16, 2014) 03/18/2016 NRC000236 NYS-25 NYS-38 Crack Growth Rate Comparison - Eason-Pathania Model to MRP Model- Excel Spreadsheet 03/18/2016