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Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023
License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program
L-2022-177, Subsequent License Renewal Application - Second Annual Update2022-11-28028 November 2022
Subsequent License Renewal Application - Second Annual Update
L-2022-160, Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22022-10-0404 October 2022
Station,, Point Beach Units 1 and 2, License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2
NRC 2022-0025, License Amendment Request 295, Beacon Power Distribution Monitoring System2022-09-26026 September 2022
License Amendment Request 295, Beacon Power Distribution Monitoring System
ML22193A1142022-09-12012 September 2022
Issuance of Amendment Nos. 270 and 272 Elimination of the Requirements to Maintain the Post-Accident Sampling System
L-2021-221, Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 12021-11-19019 November 2021
Subsequent License Renewal Application - Aging Management Requests for Additional Information (RAI) Set 10 Responses Supplement 1
L-2021-147, Subsequent License Renewal Application - Aging Management Supplement 3 Revision 12021-07-26026 July 2021
Subsequent License Renewal Application - Aging Management Supplement 3 Revision 1
L-2021-129, Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses2021-07-0808 July 2021
Ssubsequent License Renewal Application: Aging Management Requests for Confirmation Of/Additional Information (Rci/Rai) Set 1 Responses
L-2021-113, Subsequent License Renewal Application - Aging Management Supplement 32021-05-27027 May 2021
Subsequent License Renewal Application - Aging Management Supplement 3
NRC-2021-0011, Technical Specification Bases and Technical Requirement Manual Change Summary2021-04-0202 April 2021
Technical Specification Bases and Technical Requirement Manual Change Summary
NRC 2020-0032, Application for Subsequent Renewed Facility Operating Licenses2020-11-16016 November 2020
Application for Subsequent Renewed Facility Operating Licenses
ML20329A2142020-11-16016 November 2020
Enclosure 1, Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application Enclosures Summary
ML20329A2642020-11-16016 November 2020
Enclosure 4, Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)
ML20329A2192020-11-16016 November 2020
Enclosure 2, Affidavits Supporting Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390
ML20329A2482020-11-16016 November 2020
Enclosure 3, Attachment 2, Appendix E Applicant'S Environmental Report Subsequent Operating License Renewal Point Beach Nuclear Plant Units 1 and 2
NRC 2020-0020, License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss2020-08-13013 August 2020
License Amendment Request (LAR) 293, One-Time Extension of Renewed Facility Operating License Condition 4.1, Containment Building Construction Truss
NRC 2020-0003, License Amendment Request 289: Tornado Missile Protection Licensing Basis2020-02-0606 February 2020
License Amendment Request 289: Tornado Missile Protection Licensing Basis
NRC 2018-0028, NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2018-07-30030 July 2018
NextEra Energy Point Beach, LLC (NextEra) - License Amendment Request 290, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements
NRC 2018-0001, Transmittal of Construction Truss License Amendment Request Document2018-04-12012 April 2018
Transmittal of Construction Truss License Amendment Request Document
NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency2018-03-30030 March 2018
License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency
NRC 2017-0043, License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Plants2017-08-31031 August 2017
License Amendment Request 287, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, System, and Components (Sscs) for Nuclear Power Plants
NRC 2017-0028, License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2017-06-23023 June 2017
License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
NRC 2017-0017, License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances2017-03-31031 March 2017
License Amendment Request 278, Risk-Informed Approach to Resolve Construction Truss Design Code Nonconformances
NRC 2016-0030, License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region2016-07-29029 July 2016
License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region
NRC-2016-0009, License Amendment Request 2821 Modify the Wording of Surveillance Requirement 3.4.12.7 Associated with the Power-operated Relief Valves2016-03-10010 March 2016
License Amendment Request 2821 Modify the Wording of Surveillance Requirement 3.4.12.7 Associated with the Power-operated Relief Valves
NRC 2016-0002, License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program2016-02-12012 February 2016
License Amendment Request 280, Removal of Completed License Conditions and Change to the Ventilation Filter Testing Program
NRC 2015-0075, License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation2016-01-15015 January 2016
License Amendment Request 279, Elimination of Technical Specification 3.7.14, Primary Auxiliary Building Ventilation
NRC 2015-0004, LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2015-03-27027 March 2015
LAR 266 to Revise Technical Specifications to Adopt TSTF-51 0, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
NRC 2014-0075, Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog2014-12-0808 December 2014
Supplement to License Amendment Request 273 Application for Technical Specification Change Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Prog
NRC 2014-0003, License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program2014-07-0303 July 2014
License Amendment Request 273 Re Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program
NRC-2014-0035, License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2014-07-0202 July 2014
License Amendment Request (LAR) 275, Application to Revise Technical Specifications Task Force (TSTF) Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
NRC 2013-0092, License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 8052013-09-16016 September 2013
License Amendment Request 271 Supplement 1 Transition to 10 CFR 50.48(c)- NFPA 805
NRC 2013-0028, Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 22013-06-26026 June 2013
Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 3
ML13182A3502013-06-26026 June 2013
License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 3
NRC 2013-0028, License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 32013-06-26026 June 2013
License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 3
NRC 2013-0051, License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding2013-06-0404 June 2013
License Amendment Request 272, Exemption Request - Optimized Zirlo Fuel Rod Cladding
NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-03-0101 March 2013
Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2013-01-15015 January 2013
License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
NRC 2012-0073, License Amendment Request 269, Revised License Pages Cyber Security Plan Implementation Schedule Milestone Change2012-09-17017 September 2012
License Amendment Request 269, Revised License Pages Cyber Security Plan Implementation Schedule Milestone Change
NRC 2012-0065, License Amendment Request 270, Operations Manager Qualification Requirements2012-08-16016 August 2012
License Amendment Request 270, Operations Manager Qualification Requirements
NRC 2012-0040, License Amendment Request 269, Cyber Security Plan Implementation Schedule Milestone Change2012-06-18018 June 2012
License Amendment Request 269, Cyber Security Plan Implementation Schedule Milestone Change
NRC 2011-0066, License Amendment Request 254, Removal of the Table of Contents from Technical Specifications2011-06-23023 June 2011
License Amendment Request 254, Removal of the Table of Contents from Technical Specifications
NRC 2010-0189, License Amendment Request 261, Extended Power Uprate Response to Request for Clarification2010-12-21021 December 2010
License Amendment Request 261, Extended Power Uprate Response to Request for Clarification
NRC 2010-0154, License Amendment Request 261 - Extended Power Uprate - Response to Request for Additional Information2010-09-28028 September 2010
License Amendment Request 261 - Extended Power Uprate - Response to Request for Additional Information
NRC 2010-0146, License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-09-28028 September 2010
License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
NRC 2010-0145, License Amendment Request 261, Supplement 9 Extended Power Uprate2010-09-21021 September 2010
License Amendment Request 261, Supplement 9 Extended Power Uprate
NRC 2010-0132, License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information2010-09-0101 September 2010
License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information
NRC 2010-0133, License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change2010-08-12012 August 2010
License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change
NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-08-0202 August 2010
License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
NRC 2010-0084, License Amendment Request 263A, Request for Approval of Revised Cyber Security Plan2010-07-0808 July 2010
License Amendment Request 263A, Request for Approval of Revised Cyber Security Plan
2023-09-19
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Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NRC 2020-0032 Enclosure 1 Page 1 of 7 ENCLOSURE 1 POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 SUBSEQUENT LICENSE RENEWAL APPLICATION ENCLOSURES
SUMMARY
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NRC 2020-0032 Enclosure 1 Page 2 of 7 ENCLOSURES
SUMMARY
Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application Enclosures Summary Affidavits Supporting Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390 Attachment 1 CAW-20-5109, Affidavit for Westinghouse proprietary portions of Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application (SLRA) Table 4.3.4-1 Sentinel Locations, dated October 30, 2020 (Enclosure 5 Attachment 1)
Attachment 2 CAW-20-5091, Affidavit for Westinghouse proprietary portions of WCAP-18554-P Revision 1, dated September 16, 2020 (Enclosure 5 Attachment 2)
Attachment 3 Framatome Affidavit dated November 4, 2020 for proprietary information contained in the following reports:
- Framatome Topical Report BAW-2192, Revision 0, Supplement 3P, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels A & B Service Loads, October 2020 (Enclosure 5, Attachment 3),
- Framatome Topical Report BAW-2178, Revision 0, Supplement 2P, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads, October 2020 (Enclosure 5, Attachment 4), and
- Framatome Technical Report ANP-3886P, Revision 0, PWROG-20043-P, PWROG - PBN Unit 1 IS Plate A9811-1 Equivalent Margins Analysis for SLR, October 2020 (Enclosure 5, Attachment 5)
Attachment 4 CAW-20-5065, Affidavit for Westinghouse proprietary portions of LTR-SDA-II-20-05-P, Rev. 2, dated July 7, 2020 (Enclosure 5 Attachment 6)
Attachment 5 CAW-20-5071, Affidavit for Westinghouse proprietary portions of LTR-SDA-II-20-08-P, Rev. 1, dated July 20, 2020 (Enclosure 5 Attachment 7)
Attachment 6 CAW-20-5101, Affidavit for Westinghouse proprietary portions of LTR-SDA-II-20-13-P, Rev. 2, dated September 29, 2020 (Enclosure 5 Attachment 8)
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NRC 2020-0032 Enclosure 1 Page 3 of 7 ENCLOSURES
SUMMARY
Attachment 7 CAW-20-5110, Affidavit for Westinghouse proprietary portions of File No.: 2000088.310P - PROPRIETARY, Revision 1, EAF Refined Analyses (Charging Nozzle, Hot Leg Surge Nozzle, SI Nozzle, SI/RHR Tee), dated November 3, 2020 (Enclosure 5 Attachment 9)
Attachment 8 CAW-20-5102, Affidavit for Westinghouse proprietary portions of LTR-SDA-20-064-P, Rev. 1, dated October 7, 2020 (Enclosure 5 Attachment 10)
Attachment 9 CAW-20-5057, Affidavit for Westinghouse proprietary portions of WCAP-14439-P, Revision 4, dated June 12, 2020 (Enclosure 5 Attachment 11)
Attachment 10 CAW-20-5073, Affidavit for Westinghouse proprietary portions of LTR-PAFM-05-58-P, Rev. 3, dated July 23, 2020 (Enclosure 5 Attachment 12)
Attachment 11 CAW-20-5067, Affidavit for Westinghouse proprietary portions of LTR-SDA-20-020-P, Rev. 1, dated July 9, 2020 (Enclosure 5 Attachment 13)
Attachment 12 CAW-20-5066, Affidavit for Westinghouse proprietary portions of LTR-REA-20-29-P, Rev. 0, dated July 8, 2020 (Enclosure 5 Attachment 14) Attachment 1 Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application (Public Version) November 2020 Attachment 2 Appendix E Applicants Environmental Report Subsequent Operating License Renewal Point Beach Nuclear Plant Units 1 and 2 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)
Attachment 1 Westinghouse LTR-REA-20-28-NP, Revision 0, Reactor Vessel, Reactor Vessel Supports, and Concrete Bioshield Exposure Data in Support of the Point Beach Unit 2 Subsequent License Renewal (SLR) Time-Limited Aging Analysis (TLAA), July 31, 2020 Attachment 2 WCAP-18554-NP, Revision 1, Fracture Mechanics Assessment of Reactor Pressure Vessel Structural Steel Supports for Point Beach Units 1 and 2, September 2020
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NRC 2020-0032 Enclosure 1 Page 4 of 7 ENCLOSURES
SUMMARY
Attachment 3 Westinghouse WCAP-18555-NP, Revision 1, Point Beach Units 1 and 2 Time-Limited Aging Analyses on Reactor Vessel Integrity for Subsequent License Renewal, August 2020 Attachment 4 Framatome Topical Report BAW-2192, Revision 0, Supplement 3NP, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels A & B Service Loads, October 2020 Attachment 5 Framatome Topical Report BAW-2178, Revision 0, Supplement 2NP, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads, October 2020 Attachment 6 Framatome Technical Report ANP-3886NP, Revision 0, PWROG-20043-NP, PWROG - PBN Unit 1 IS Plate A9811-1 Equivalent Margins Analysis for SLR, October 2020 Attachment 7 Structural Integrity Associates, Inc. Report No.2000088.401, Revision 2, Cycle Counts and Fatigue Projections for 80 Years of Plant Operation for Point Beach Nuclear Units 1 and 2, October 19, 2020 Attachment 8 Westinghouse LTR-SDA-II-20-05-NP, Revision 2, Environmentally Assisted Fatigue Screening Results for Point Beach Unit 1 and Unit 2 Safety Class 1 Primary Equipment, June 30, 2020 Attachment 9 Structural Integrity Associates, Inc. Report No.
2000088.402, Revision 1, Environmentally-Assisted Fatigue Evaluation for 80 Years of Plant Operation for Point Beach Nuclear Units 1 and 2, September 25, 2020 Attachment 10 Westinghouse LTR-SDA-II-20-08-NP, Revision 1, Environmentally Assisted Fatigue Evaluation Results for the Point Beach Unit 1 and Unit 2 Primary Equipment Sentinel Locations for Subsequent License Renewal, July 15, 2020 Attachment 11 Westinghouse LTR-SDA-II-20-13-NP, Revision 2, Environmentally Assisted Fatigue Evaluation Results for the Point Beach Unit 1 and Unit 2 Pressurizer Lower Head for Subsequent License Renewal, September 23, 2020
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NRC 2020-0032 Enclosure 1 Page 5 of 7 ENCLOSURES
SUMMARY
Attachment 12 Structural Integrity Associates, Inc. File No. 2000088.310P
- REDACTED, Revision 1, EAF Refined Analyses (Charging Nozzle, Hot Leg Surge Nozzle, SI Nozzle, SI/RHR Tee), August 14, 2020 Attachment 13 Structural Integrity Associates, Inc. Calculation No. PBCH-03Q-301, Revision 3, Evaluation of Thermal Stratification Due to Valve Leakage, September 25, 2020 Attachment 14 Westinghouse LTR-SDA-20-064-NP, Revision 1, ASME Section XI Appendix L Evaluation Results for the Point Beach Units 1 and 2 Pressurizer Spray Nozzles, October 7, 2020 Attachment 15 Structural Integrity Associates Calculation PBCH-06Q-301, Revision 1, Containment Penetration Fatigue Evaluation, November 11, 2003 Attachment 16 Westinghouse WCAP-14439-NP, Revision 4, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Point Beach Nuclear Plant Units 1 and 2 for the Subsequent License Renewal Program (80 Years), June 2020 Attachment 17 Westinghouse LTR-SDA-II-20-06, Revision 1, Leak-Before-Break Reconciliation of the Point Beach Units 1 and 2 Pressurizer Surge Line, Residual Heat Removal Line, and Accumulator Line Piping Systems for the Subsequent License Renewal Program, May 4, 2020 Attachment 18 Westinghouse LTR-PAFM-05-58-NP, Revision 3, Flaw Tolerance Evaluation for Susceptible Reactor Coolant Loop Cast Austenitic Stainless Steel Piping Components in Point Beach Units 1 and 2 for 80 years, July 2020 Attachment 19 Westinghouse LTR-SDA-20-020-NP, Revision 1, Point Beach Units 1 and 2 Reactor Coolant Pump Casings ASME Code Case N-481 Analysis for 80-year Subsequent License Renewal (SLR), July 2020 Attachment 20 Westinghouse LTR-AMLR-20-26-NP, Revision 1, Transmittal of Results from the MRP-191 Revision 2 Review in Support of Subsequent License Renewal for Point Beach Units 1 and 2, June 11, 2020
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NRC 2020-0032 Enclosure 1 Page 6 of 7 ENCLOSURES
SUMMARY
Attachment 21 Westinghouse LTR-REA-20-29-NP, Revision 0, Comparison of Point Beach Unit 1 Reactor Internals Fluence Values to the Representative 3-Loop Plant for MRP-191, Revision 2, July 7, 2020 10 CFR 2.390 Withheld Proprietary Documents Note: The attachments for Enclosure 5 are split between OSM 2 and OSM 3 as shown on each OSM index. Below is the combined list of Enclosure 5 attachments and the OSM that contains them.
Attachment 1 Point Beach Nuclear Plant Units 1 and 2 Subsequent License Renewal Application (SLRA) Table 4.3.4-1 Sentinel Locations (OSM 2)
NOTE: These proprietary pages replace pages 4.3-20, 4.3-21 and 4.3-22 of Enclosure 3.
Attachment 2 WCAP-18554-P, Revision 1, Fracture Mechanics Assessment of Reactor Pressure Vessel Structural Steel Supports for Point Beach Units 1 and 2, September 2020 (OSM 3)
Attachment 3 Framatome Topical Report BAW-2192, Revision 0, Supplement 3P, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels A & B Service Loads, October 2020 (OSM 2)
Attachment 4 Framatome Topical Report BAW-2178, Revision 0, Supplement 2P, Revision 0, Low Upper-Shelf Toughness Fracture Mechanics Analysis of Reactor Vessels of B&W Owners Reactor Vessel Working Group for Levels C & D Service Loads, October 2020 (OSM 2)
Attachment 5 Framatome Technical Report ANP-3886P, Revision 0, PWROG-20043-P, PWROG - PBN Unit 1 IS Plate A9811-1 Equivalent Margins Analysis for SLR, October 2020 (OSM 2)
Attachment 6 Westinghouse LTR-SDA-II-20-05-P, Revision 2, Environmentally Assisted Fatigue Screening Results for Point Beach Unit 1 and Unit 2 Safety Class 1 Primary Equipment, June 30, 2020 (OSM 3)
Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 NRC 2020-0032 Enclosure 1 Page 7 of 7 ENCLOSURES
SUMMARY
Attachment 7 Westinghouse LTR-SDA-II-20-08-P, Revision 1, Environmentally Assisted Fatigue Evaluation Results for the Point Beach Unit 1 and Unit 2 Primary Equipment Sentinel Locations for Subsequent License Renewal, July 15, 2020 (OSM 3)
Attachment 8 Westinghouse LTR-SDA-II-20-13-P, Revision 2, Environmentally Assisted Fatigue Evaluation Results for the Point Beach Unit 1 and Unit 2 Pressurizer Lower Head for Subsequent License Renewal, September 23, 2020 (OSM 3)
Attachment 9 Structural Integrity Associates, Inc. File No. 2000088.310P
- PROPRIETARY, Revision 1, EAF Refined Analyses (Charging Nozzle, Hot Leg Surge Nozzle, SI Nozzle, SI/RHR Tee), August 14, 2020 (OSM 2)
Attachment 10 Westinghouse LTR-SDA-20-064-P, Revision 1, ASME Section XI Appendix L Evaluation Results for the Point Beach Units 1 and 2 Pressurizer Spray Nozzles, October 7, 2020 (OSM 3)
Attachment 11 Westinghouse WCAP-14439-P, Revision 4, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Point Beach Nuclear Plant Units 1 and 2 for the Subsequent License Renewal Program (80 Years), June 2020 (OSM 3)
Attachment 12 Westinghouse LTR-PAFM-05-58-P, Revision 3, Flaw Tolerance Evaluation for Susceptible Reactor Coolant Loop Cast Austenitic Stainless Steel Piping Components in Point Beach Units 1 and 2 for 80 years, July 2020 (OSM 3)
Attachment 13 Westinghouse LTR-SDA-20-020-P, Revision 1, Point Beach Units 1 and 2 Reactor Coolant Pump Casings ASME Code Case N-481 Analysis for 80-year Subsequent License Renewal (SLR), July 2020 (OSM 3)
Attachment 14 Westinghouse LTR-REA-20-29-P, Revision 0, Comparison of Point Beach Unit 1 Reactor Internals Fluence Values to the Representative 3-Loop Plant for MRP-191, Revision 2, July 7, 2020 (OSM 3)
