(Draft Was Issued as DG-1150, Dated August 2009), Qualification of Continuous Duty Safety-Related Motors for Nuclear Power Plants
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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, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 7, Instrumentation and Controls
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
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
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, Figure 7.6.5-1 (Sheet 1 of 2) Through Figure 8.3.1-1 (Sheet 4 of 34)
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
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Response to NRC Questions
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 8.0 - Electric Power
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 8.0 - Electric Power
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 3.0, Design of Structures, Components, Equipment and Systems
IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action
ST-HL-AE-1954, Forwards Minutes of 870210 Meeting W/Nrc Re Basis for 30-day post-accident Operability Requirement.Viewgraphs & Attendance List Also Encl
ST-HL-AE-1422, Forwards Response to Draft Ser/Fsar Items Re Section 3.11 Concerning Environ Design of Mechanical & Electrical Equipment.Encl marked-up FSAR Pages Will Be Incorporated in Future FSAR Amend
TXX-6745, Forwards Revised Environ Qualification Program,Addressing Mild Environs for Plant
PY-CEI-NRR-0248, Forwards Revised Conformance Statements for Reg Guides in FSAR Section 1.8,per 850206 & 0402 Commitments
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
LD-93-149, Forwards Markups of Sys 80+ Design Descriptions,Associated ITAAC & CESSAR-DC Pages from Meetings W/Nrc Staff on 931004
LD-82-008, Forwards Formal Response to Eg&G Comments on Revision 2 to CENPD-255,revised Section 3.11 to CESSAR-F & Revision 3 to Class IE Qualification of Class IE Electrical Equipment
LD-81-011, Forwards Amend 1 to CESSAR-F.Application to Review Amend & Responses to NRC 790323 Questions Encl
05000388/LER-1986-005-01, :on 860321 Differential Pressure Condition Detected,Causing Supply Dampers to Oscillate.Caused by Open Plenum Door & Exhaust Damper Linkage Binding.Linkage Reworked & Lubricated
GO2-81-255, Forwards marked-up Responses to NRC 801230 Questions Re Instrumentation & Controls Sys.Responses Will Be Incorporated Into FSAR Amend within 4 Months