Welder Qualification for Areas of Limited Accessibility
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LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 4, Reactor
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 10, Steam and Power Conversion System
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
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, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 5 - Reactor Coolant System and Connected Systems
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 10.0 - Steam and Power Conversion System
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 6.0 - Engineered Safety Features
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 10.0 - Main Steam and Power Conversion System
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 5 - Reactor Coolant System and Connected Systems
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 5.0, Reactor Coolant System and Connected Systems
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 10.0, Steam and Power Conversion System
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
1CAN040302, License Amendment Request to Modify the Fuel Assembly Enrichment, the Spent Fuel Pool (SFP) Boron Concentration TS 3. 7.14, the Loading Restrictions in the SFP in TS 3,7,15m and to Modify the Fuel Storage Design Features in TS 4.3
2CAN010304, Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
ULNRC-03916, Forwards Util 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CCS After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment. Supporting Info,Encl
PLA-7935, 0 to Updated Final Safety Analysis Report, Section 10.3, Main Steam Supply System
ST-HL-AE-2093, Forwards Revised FSAR Section 3.12, Conformance W/Nrc Reg Guides. Section Updated to Reflect Util Position on All Applicable Reg Guides
ST-HL-AE-1480, Forwards marked-up FSAR Chapter 7 Pages Re safety-related Display Instrumentation in Response to Draft Ser/Fsar Items F 7.5-1,7.5-21 & 7.5-22.Pages Will Be Incorporated Into Future FSAR Amend
RBG-21536, Forwards Rev to FSAR & Tech Specs Resulting from Final Review of Fracture Toughness & Reactor Vessel Matl Surveillance Program Requirements Per 10CFR50.Revs Will Be Included in Future Amend to FSAR
ET-NRC-93-3791, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 920923,1001,09 & 28 Ltrs.Info Covers safety-related HVAC Sys,Reactor Vessel Modeling,Reactor Vessel Internal Limits & Design Soil Profile Envelopes
ST-HL-AE-1268, Forwards Revised FSAR Questions & Responses Re Diesel Generators & Lighting Sys.Revised Info Will Be Incorporated Into FSAR Amend 49
LD-88-039, Forwards Addl Info Re Chapters 1 & 10 to CESSAR-DC,per NRC 880311 Request
LD-88-034, Provides Addl Info on CESSAR-DC Chapter 10 Re Secondary Water Chemistry,Per NRC 880225 request.CESSAR-DC Section 10.3.5.1 Revised to Make Clear That C-E Secondary Water Chemistry Program Includes Immediate Shutdown Limits
LD-93-011, Forwards Responses to 22 Issues Re Closure of Sys 80+ Draft SER Issues
LD-92-123, Forwards Section 17.3, Design Reliability Assurance Program Plan for Sys 80+ Standard Design, Rev 1 & Responses to 79 Issues Identified in Dser for Sys 80+
LD-92-045, Submits Listing of Deviations Between Acceptance Criteria of NRC Std Review Plan & Sys 80+ Design Certification Application & Submits Std Review Plan Comments
LD-91-071, Responds to NRC Requests for Addl Info for Review of C-E SSAR-Design Certification Rept.Proposed Revs to SSAR Encl
RAIO-0818-61388, LLC Response to NRC Request for Additional Information No. 492 (Erai No. 9551) on the NuScale Design Certification Application
NLS2006028, Report HI-2043224, Licensing Report on the Wet Fuel Storage Capacity Expansion at Cooper Nuclear Station
ST-HL-AE-1509, Forwards Response to Draft SER or FSAR Item C 3.7-1 Re Seismic Design Confirming Frequencies of Floor Subsystems in Each Bldg Higher than Corresponding Limit.Encl marked-up FSAR Pages Will Be Incorporated in Future Amend