(Revision 2), Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)
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RIS 2005-25, Y020070010 - RIS 2005-025, Supplement 1, Clarification of Guidelines for Control of Heavy Loads
RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-10
ONS-2015-072, Updated Final Safety Analysis Report, Revision 24, Chapter 9 - Auxiliary Systems
RA-14-010, Summary of Changes to Exelon Generation Company,Llc, Quality Assurance Topical Report, NO-AA-10
ONS-2013-037, Licensing Basis for Protected Service Water System - Responses to Request for Additional Information Item Nos. 172 Through 189, License Amendment Request (LAR) 2008-07 - Supplement 7
RA-12-006, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10
LR-N17-0088, Redacted - Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 3, Design of Structures, Components, Equipment and Systems, Sections 3.6 Through 3.11
LR-N17-0088, Enclosures 1 & 2: Pseg Nuclear, LLC Quality Assurance Topical Report, NO-AA-10, Revision 86
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3.7.B.2-27 Through 3D-17
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 5, Structures
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and Systems
NRC-12-0067, Fermi 2, Submittal of Revision 18 to the Updated Final Safety Analysis Report, 10 CFR 50.59 Evaluation Summary Report, Commitment Management Report and Revision to the Technical Requirements Manual and the Technical Specifications Bases
L-2010-212, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report - Unit 4 Cycle 24 Update, Chapter 5, Structures
RA-10-050, Technical Specification Change Request No. 340, Proposed Revision to Appendix B Environmental Technical Specifications of the Facility Operating License
RA-10-001, Submittal of Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, Revision 84
RA-08-006, Submittal of Exelon Generation Company, LLC and Amergen Energy Company, LLC Quality Assurance Topical Report, NO-AA-10, Revision 80
RAIO-0118-58469, LLC Response to NRC Request for Additional Information No. 131 (Erai No. 8970) on the NuScale Design Certification Application
RAIO-0718-60789, LLC Response to NRC Request for Additional Information No. 38 (Erai No. 8838) on the NuScale Design Certification Application
ND-18-1006, Supplement to Request for License Amendment and Exemption: Changes to Tier 2* Departure Evaluation Process (LAR-17-037S4)
ND-18-0319, Supplement to Request for License Amendment and Exemption: Tier 1 and Tier 2* Editorial and Consistency Changes (LAR-17-042S1)
RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)
NSD-NRC-97-5324, Submits Major Issues Resulting from NRC Structural Design Review on 970804-15.W Believes That AP600 Basemat Is Acceptable for All of Conditions in Certified Design
NSD-NRC-97-5388, Forwards Summary of W Responses Re Nuclear Island Basement. Response Should Permit Resolution of All Remaining Open Items Re Nuclear Island Basement
NSD-NRC-98-5541, Provides Westinghouse Responses to FSER Open Items on AP600. Summary of Encl Responses Provided in Table 1.NRC Should Review Encls & Inform Westinghouse of Status to Be Designated in NRC Status Column of Oits
ST-HL-AE-1674, Forwards Comments & marked-up SER (NUREG-0781) Re Operation of South Texas Projects 1 & 2
ST-HL-AE-1428, Forwards Response to Draft SER or FSAR Items Q220.04N, Q220.08N,Q220.09N,Q220.13N,Q220.25N & Q220.30N Re Revised Response to NRC Structural Engineering Branch Questions. Info Will Be Incorporated in Future FSAR Amend
NSD-NRC-97-4935, Forwards Documents Which Summarize Westinghouse Response to Issues in NRC Re AP600 Structural Module
B11215, Forwards Addl Info Requested to Close Draft SER & Structural Audit Open & Confirmatory Items 3,8,9,19,27,29,32,33,36,39 & 42.All Remaining Structural Confirmatory Items Expected to Be Resolved at Early June 1984 Meeting
NPL-94-0319, Provides Clarification of Design Codes & Methods Used to Design Steel Embedments Described in DG Addition Project Design Summary Submitted on 930924 in Support of TS Change 166,subsequently Submitted on 940526
BECO-93-148, Responds to NRC Request for Addl Info Re Proposed TS Change, Spent Fuel Storage Capacity Expansion
3F0409-04, Attachment B Through E - Crystal River, Unit 3 - License Amendment Request 303, Revision 1, Revision to Final Safety Analysis Report Sections 5.4.3, Structural Design Criteria, and 5.4.5.3, Missile Analysis.
3F0509-07, License Amendment Request 303, Revision 1, Supplement 1: Revision to Final Safety Analysis Report Sections 5.4.3, Structural Design Criteria, and 5.4.5.3, Missile Analysis, Response to Request for Additional Information
NSD-NRC-97-5456, Forwards Response to Shield Bldg Roof Dser Open Item 3.8.4.4-2.Shear Reinforcement Changed to Respond to Staff Comments.Revised Design Shown in Proposed Revs to SSAR Included W/Response
NSD-NRC-98-5561, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status of Column of Oits, Provided in Table 1
ET-NRC-93-3886, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 930126,0218,0312 & 0413 Ltrs.Westinghouse Responses to Remainder of Requests for Addl Info Contained in Will Be Provided Prior to 930529
NUREG/CR-7153, NRC071 - NUREG/CR-7153, Expanded Materials Degradation Assessment (Emda), Volume 4: Aging of Concrete and Civil Structures (Oct. 2014)
LIC-15-0142, Supplement of License Amendment Request 15-03; Revise Current Licensing Basis to Use ACI Ultimate Strength Requirements
LIC-15-0077, License Amendment Request 15-03; Revise Current Licensing Basis to Use ACI Ultimate Strength Requirements
3F0409-04, Attachment B Through E - Crystal River, Unit 3 - License Amendment Request 303, Revision 1, Revision to Final Safety Analysis Report Sections 5.4.3, Structural Design Criteria, and 5.4.5.3, Missile Analysis
RS-24-130, NO-AA-12, Revision 0, Restoration Quality Assurance Program
B11160, Forwards Responses to Structural & Geotechnical Engineering Branch Draft SER Open Items,Per Bj Youngblood & Items Identified During 840323 Structural Audit.Fsar Amends Will Be Included in Future Amend