Maintenance of Water Purity in Boiling Water Reactors
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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 14, Initial Test Program
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
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-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 5 - Reactor Coolant System and Connected Systems
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
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-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 7.0 - Instrumentation and Control Systems
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
NRC Generic Letter 79-05, Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
PLA-2776, Forwards 10CFR50.59 Rept Summarizing 1985 Approved Safety Evaluations for Determining Unreviewed Safety Question
HBL-87-015, Forwards Proposed Rev 2 to Safstor Tech Specs.Rev Includes Changes to Chemistry Limits on Spent Fuel Storage Pool & Requirements for Surveillance Program for Boral Matl of Spent Fuel Assembly Containers
HBL-88-047, Replacement Pages for Proposed Safstor Tech Specs,Rev 0
U-600384, Forwards Response to 851029 Request for Addl Info Re Initial Plant Test Program
NG-86-0207, Annual Rept of Facility Changes,Tests,Experiments & Safety & Relief Valve Failures & Challenges for 1985
RBG-34273, Application for Amend to License NPF-47,changing Tech Spec Surveillance Requirement 4.4.4.c to Remove 31-day Administrative Limit for Loss of Continuous Conductivity Monitoring of RCS
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
HBL-87-066, Forwards Rev 3 to Proposed Tech Specs for Safstor.Revs Reflect Util 870821 Response to NRC Request for Addl Info
AECM-81-235, Forwards Proposed FSAR Changes in Response to NRC Questions. Changes Will Be Incorporated Into Forthcoming FSAR Amend 50
LG-18-117, 10 CFR 50.59 and 10 CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2016 Through June 30, 2018
GO2-81-424, Forwards Responses to Chemical Engineering Branch Questions, Per 810804 Request for Addl Info.Responses Will Be Incorporated Into FSAR Amend 21
NRC-16-0034, 0 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System
RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
RBG-27108, Forwards Suppl Rept of Safety Evaluations for Documents Only Changes Included in USAR for Mar 1986 - Feb 1987
U-602836, Forwards Rev 7 to Clinton Power Station Usar.Attached Clinton Power Station 10CFR50.59 Rept Identifies All Safety Evaluations for Implemented Changes Affecting USAR for Period of 950430-970630
AECM-86-0362, Forwards Rept of 10CFR50.59 Safety Evaluations,Jan-June 1986,Grand Gulf Nuclear Station, Discussing Changes,Tests & Experiments