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
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
ET-NRC-93-3905, Forwards Responses to NRC 930218,0312,0413 & 28 RAIs on AP600
NSD-NRC-97-5501, Forwards W Responses to FSER Open Items on AP600.Summary of Responses Provided in Table 1,including FSER Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column
NSD-NRC-97-5366, Discusses Svc Level C Capacity of Containment Vessel,Which Is Covered Under Open Items 708,1485 & 3269.Adequate Margin Exists in Current AP600 Containment Design
LIC-97-0122, Forwards Response to Supplemental RAI Re Resolution of USI A-46 for Fcs.Rev 1 to Calculation FC06313 & Rev 1 to Calculation FC06314,also Encl
RBG-23815, Forwards Proprietary Natural Circulation Equation Development, Per a Notafrancesco 850905 Request.Encl Addl Info Addresses Natural Circulation Model Used in Hydrogen Deflagration Analysis.Encl Withheld (Ref 10CFR2.790)
NSD-NRC-97-5124, Forwards Draft SSAR Markups Re Structural Related Issues. Changes Will Be Included in Rev 13 of SSAR
NSD-NRC-97-4981, Forwards Responses to Resolve Dser Open Items,Rais & Telcon Item Re AP600 Containment Structural Issues
NSD-NRC-96-4641, Forwards Response to Request for Addl Info for Use of ASME Boiler & Pressure Vessel Code Case N-284,Rev 1 on AP600 Design
NRC-96-4617, Forwards Info Provided to Address NRC Open Issues Related to AP600 Steel Containment.Draft Rev of Subsection 3.8.2 of Ssar,Draft Rev of Chapter 42 of AP600 PRA & Responses to NRC Requests for Addl Info Also Encl
RBG-18-089, Forwards Response to Request for Addl Info Re Combustible Gas Control Sys.Based on Evaluation,Util Will Select Suitable Equipment Protection Measures Appropriate for Equipment Location & Degraded Core Thermal Environ
NRC-95-4555, Requests Approval of Use of ASME B&PV Code Case N-284,Rev 1 for Const of Components in Nuclear Power Facility
NRC-94-4291, Forwards Responses to NRC RAIs on AP600 from NRC 940415, 0523,0601,08 & 15 Ltrs
NRC-94-4237, Forwards Responses to NRC RAIs on AP600 from Ltrs of 940428, 29,0502,05,16 & 26.Revs of Responses Previously Submitted Also Provided
NRC-94-4181, Submits Responses to NRC Requests for Addl Info Re AP600
NRC-94-4099, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs of 940113 & 26
NRC-94-4087, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 940126.Listing of NRC Requests for Addl Info Responded to Ltr Contained in Attachment a
LD-92-091, Forwards Responses to 920409 Request for Addl Info Re Sys 80+ Severe Accident Design Features
LD-92-063, Forwards Info to Supplement 920325 Responses to NRC Request for Addl Info Re Analysis of Ruptured Reactor Coolant Pump Seal Cooler Tube & Single Failure Assumptions for Analysis of moderate-energy-line Break
NSD-NRC-97-5064, Consolidates Responses & Resolutions of Items Associated W/ SSAR Section 3.8.2 & Confirms Completion of Submittal of Final Documentation Related to SSAR Section 3.8.2 for Application for AP600 Design Certification
NSD-NRC-97-5137, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 970416-30,including Info Re SSAR Open Items 292,277,300 & 304
ET-NRC-93-3924, Forwards Responses to Request for Addl Info on AP600,per NRC 930312 & 0413 Ltrs
NRC-94-4110, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from Ltrs of 940126,27 & 0316.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
GO2-83-863, Forwards Addl Info Re Containment Out-of Roundness Per NRC 830722 Meeting
CLI-09-07, Staff Assessment of the Oyster Creek 3-D Finite Element Analysis of the Drywell Shell
ET-NRC-92-3777, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 920923 & 1001 Ltrs.Transmittal Partial Response to Ltrs.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a