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| Issue date | Title | |
|---|---|---|
| ML25140A065 | 20 May 2025 | Enclosure 2: Clinch River Nuclear Site, Construction Permit Application Enclosure 4, Exemptions and Variances |
| ML19030A420 | 18 January 2019 | Part 03 Environmental Report (Rev. 2) - Part 03 - Environmental Report - Chapter 03 - Plant Description |
| ML18290A685 | 9 November 2018 | Clinch River Nuclear Site Early Site Permit Application Safety Evaluation with No Open Items, Section 2.4 (Redacted Version) |
| ML17289A625 | 8 November 2018 | Clinch River Nuclear Site Early Site Permit Application Safety Evaluation with No Open Items, Section 11.2 & 11.3 |
| ML18003A447 | 15 December 2017 | Part 03 Environmental Report (Rev. 1) - Part 3 - Er - Chapter 3 - Plant Description |
| NRC Generic Letter 1994-02 | 11 July 1994 | NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors |
| NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
| NRC Generic Letter 1990-06 | 25 June 1990 | NRC Generic Letter 1990-006: Resolution of Generic Issue, Power-Operated Relief Valve and Block Valve Reliability, and Generic Issue 94, Additional Low-Temp. Overpressure Protection for Light-Water Reactors, Pursuant to 10 CFR 50354 (F) |
| NRC Generic Letter 1988-11 | 12 July 1988 | NRC Generic Letter 1988-011: NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations |
| ML20023D407 | 31 May 1983 | Amend 77 to PSAR |
| ML20064N271 | 15 February 1983 | Forwards Revised PSAR Section 3.1,incorporating Final Principal Design Criteria.Info Will Be Included in Next PSAR Rev |
| ML20064N233 | 15 February 1983 | Forwards Addl Info on Crbr Instrumentation & Controls Discussed in 830201 Telcon W/Nrc & Revised Responses to NRC Questions CS421.15,19 & 46.Revised Pages Will Be Included in Next PSAR Amend |
| ML20027D666 | 3 November 1982 | Forwards marked-up PSAR Pages & Responses to Action Items 46 & 51 Re Separation of Primary & Secondary Reactor Shutdown Sys Redundant Channels,In Response to 820921-22 Instrumentation (Chapter 7) Working Meeting Request |
| ML20054L535 | 1 July 1982 | Response to NRDC & Sierra Club 820611 Petition to Commission to Exercise Inherent Supervisory Authority to Delineate Scope of LWA Proceeding.Petition Raises No Issue Requiring Immediate Intervention.Certificate of Svc Encl |
| ML20054H826 | 30 June 1982 | SITE-SUITABILITY Report in the Matter of the Clinch River Breeder Reactor Plant.Docket No. 50-537 |
| ML20054F709 | 14 June 1982 | Forwards Responses to NRC Feb,Mar & Apr Requests for Addl Info,To Be Incorporated Into Amend 69 to PSAR |
| ML20054F313 | 11 June 1982 | Petition to Exercise Inherent Supervisory Authority to Delineate Scope of LWA Proceeding.Limits on Scope of LWA Proceeding Re Contentions 1,2 & 3 Prevent Compliance W/Nepa. Portions of Transcripts & Certificate of Svc Encl |
| ML20079F666 | 1 June 1982 | Forwards Responses to NRC 820226,0311,15,23 & 0409 Requests for Addl Info.Responses Will Be Incorporated Into Amend 69 to PSAR |
| ML20052F332 | 7 May 1982 | Responds to 820309 Request for Addl Info Re Equipment Qualification.Encl Responses to Questions CS 270.1,CS 270.2, CS 270.4 - CS 270.9 Will Be Incorporated Into PSAR Amend 69 by 820521 |
| ML20054B749 | 15 April 1982 | Statement of Position Re NRDC Contentions 1,2 & 3 |
| ML20054C611 | 9 April 1982 | Forwards Request for Addl Info Re Instrumentation & Control Sys & Proposed Agenda for Future Branch Meetings |
| ML20050A558 | 31 March 1982 | Amend 67 to PSAR |
| ML20052C824 | 9 March 1982 | Discusses Design Criteria Proposal as Compared W/General Design Criteria in 10CFR50 App a |
| ML20049J580 | 9 March 1982 | Forwards Request for Addl Info Re Equipment Qualification. Info Should Be Provided in 60 Days |