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List of results

• L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 9, Auxiliary Systems  + (00:29:33, 8 July 2018)
• L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 9.5, Fire Protection Program Report  + (00:29:38, 8 July 2018)
• L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 5, Reactor Coolant System  + (00:30:09, 8 July 2018)
• L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 1, Introduction and General Description of Plant Site Characteristics  + (00:31:12, 8 July 2018)
• RA-17-003, Brunswick, Units 1 & 2, Catawba, Units 1 & 2, McGuire, Units 1 & 2, Oconee, Units 1, 2 & 3, H. B. Robinson, Unit 2 - Transmittal of Emergency Plan Implementing Procedure AD-EP-ALL-1000, Revision 2  + (00:36:58, 8 July 2018)
• LR-N17-0088, Enclosures 1 & 2: Pseg Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86  + (00:43:33, 8 July 2018)
• LR-N17-0088, Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Re  + (00:59:03, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, List of Current Pages and Master Table of Contents  + (00:59:11, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 8, Electric Power  + (00:59:23, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 7, Instrumentation and Controls  + (00:59:40, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems  + (00:59:51, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 4, Reactor  + (00:59:59, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 18, Human Factors Engineering  + (01:00:04, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 17, Quality Assurance  + (01:00:08, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 16, Technical Specifications  + (01:00:12, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 15, Accident Analyses  + (01:00:30, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 14, Initial Test Program  + (01:00:42, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 13, Conduct of Operation  + (01:00:49, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management  + (01:01:01, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 10, Steam and Power Conversion System  + (01:01:08, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant  + (01:01:29, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems, Appendix 5A  + (01:01:40, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 6, Engineered Safety Features, Appendices 6A Thru 6C  + (01:01:48, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Appendices 3A Through 3I  + (01:01:57, 8 July 2018)
• LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Appendices 13A - 13L  + (01:02:03, 8 July 2018)

• BVY 17-009, Vermont Yankee - Calculation ENTGVY036-CALC-001, Revision 1, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant  + (01:36:32, 8 July 2018)

• BVY 17-009, Attachment 3: Vermont Yankee Supporting Evaluation and Calculation VYC-3200, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant  + (01:36:36, 8 July 2018)
• LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 9.1-1 Through 9.1-9  + (01:39:11, 8 July 2018)
• LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 6.3-1A Through 6.3-4  + (01:39:14, 8 July 2018)
• LR-N17-0034, Redacted Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figures 5.5-1 Through 5.5-7  + (01:39:18, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Effective Page Listing, Table of Contents, Chapter 1 Redacted, Introduction and General Description of the Plant  + (01:39:29, 8 July 2018)
• LR-N17-0034, Redacted - Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Figure 3.8-1 Through 3.8-56  + (01:39:33, 8 July 2018)
• LR-N17-0034, Redacted-Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 2.2, Nearby Industrial, Transportation, and Military Facilities  + (01:39:38, 8 July 2018)
• DCL-17-048, Diablo Canyon, Units 1 and 2 - Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section Xi Examination Requirements for Class 1 and 2 Piping Welds, Request for R  + (01:43:11, 8 July 2018)
• L-2017-078, St. Lucie, Units 1 and 2 - Submittal of 2016 Annual Environmental Operating Report  + (01:54:22, 8 July 2018)
• JAFP-17-0036, James A. FitzPatrick, Transmittal of Emergency Plan Updates  + (02:13:56, 8 July 2018)
• RS-17-059, Clinton Power Station, Unit 1, Submittal of Revisions to Radiological Emergency Plan  + (02:17:44, 8 July 2018)
• ONS-2017-030, Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2  + (02:36:18, 8 July 2018)
• ONS-2017-030, Submittal of Oconee Nuclear Station, Units 1, 2, and 3, Emergency Plan Revision 2017-002  + (02:36:23, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Requirements Manual  + (02:41:24, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases  + (02:41:46, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 4 Through Chapter 5  + (02:43:14, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 2  + (02:43:28, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1  + (02:43:49, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 2, Figures 2B5B1-1 to 2B7-44  + (02:44:05, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 2, Figures 2B1-1 to 2B5A-1  + (02:44:17, 8 July 2018)
• NL-17-0534, Joseph M. Farley Nuclear Plant - Submittal of Updated Final Safety Analysis Report, 10 CFR 50.59 Report, Fire Hazard Analysis Changes, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and Revised NRC Commitme  + (02:44:23, 8 July 2018)
• RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 5.1, Appendices  + (03:18:02, 8 July 2018)
• NL-17-0516, Edwin I. Hatch Nuclear Plant, Unit 2 - Submittal of Cycle 25 Core Operating Limits Report Version 1  + (03:26:08, 8 July 2018)
• RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 2.0, Fire Hazards Analysis  + (03:33:27, 8 July 2018)
• RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix E - Requirements Resulting from TMI-2 Accident  + (03:34:42, 8 July 2018)