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| Issue date | Title | |
|---|---|---|
| ML18043B161 | 26 March 2018 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident |
| ML20147A710 | 31 December 1996 | Technical Ltr Rept, Pacific Northwest Natl Lab Review of Main Yankee In-Situ Pressure Test Assessment, Rev 2 |
| DD-96-20, Responds to Petition Filed on 960120 on Behalf of Petitioner Re Plant Operated by Licensee.Nrr Denied Licensee Request for Immediate Action Suspending Operating License.Director'S Decision DD-96-20 & Notice Issuing Director'S Decision Encl | 20 November 1996 | Responds to Petition Filed on 960120 on Behalf of Petitioner Re Plant Operated by Licensee.Nrr Denied Licensee Request for Immediate Action Suspending Operating License.Director'S Decision DD-96-20 & Notice Issuing Director'S Decision Encl |
| Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites | 5 June 1995 | Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites |
| ML20149H127 | 14 November 1994 | S/G Insp Rept |
| ML20127P219 | 25 January 1993 | Application for Amend to License DPR-36,consisting of Proposed TS Change 177 to Allow Increase in Number of Spent Fuel Assemblies Stored in Spent Fuel Pool from 1,476 to 2,019.Rev 0 to Licensing Rept... Encl |
| ML20238B312 | 27 August 1987 | Submits Audit of Plant Changes (10CFR50.59) for Listed Seismic Upgrades.No Violations Identified.Table Listing Documents Reviewed During Audit Encl |
| NRC Generic Letter 1987-11 | 19 June 1987 | NRC Generic Letter 1987-011: Relaxation in Arbitrary Intermediate Pipe Rupture Requirements |
| ML20206B318 | 31 March 1987 | Seismic Margin Review of the Maine Yankee Atomic Power Station.Volume 2.Systems Analysis |
| ML20206B249 | 31 March 1987 | Seismic Margin Review of the Maine Yankee Atomic Power Station.Volume 1.Summary Report |
| ML20205M639 | 26 March 1987 | Safety Evaluation Accepting Upgraded Seismic Design Program Contingent on Licensee Commitment to Upgrade Items in Table 3 |
| NUREG-0098, Forwards Safety Evaluation Supporting Util Upgraded Seismic Margin Program.Concurs W/Plans for Future Plant Changes to Assure Existing Structures,Sys & Components Not Structurally Degraded by Change | 26 March 1987 | Forwards Safety Evaluation Supporting Util Upgraded Seismic Margin Program.Concurs W/Plans for Future Plant Changes to Assure Existing Structures,Sys & Components Not Structurally Degraded by Change |
| NRC Generic Letter 1986-10 | 24 April 1986 | NRC Generic Letter 1986-010: Implementation of Fire Protection Requirements |
| ML20141E037 | 31 March 1986 | Discusses Util Participation in Seismic Design Margins Program.Util Commitment to Ensure That Seismic Ruggedness of Existing Structures,Sys & Components Will Be Maintained During Future Plant Mods Noted.Description of Program Encl |
| ML20129H071 | 31 May 1985 | Forwards Response to 850211 Request for Addl Info on NUREG-0737,Item II.D.1 Re Performance Testing of Relief & Safety Valves |
| ML20129H742 | 14 May 1985 | Integrated Assessment of Auxiliary Feedwater Sys |
| ML20140E702 | 27 March 1985 | Forwards Branch Recommendation for Ground Motion Characterization for Plant Seismic Reanalysis.Appropriate Ground Motion Characterization Is NUREG/CR-0098 Response Spectrum |
| NRC Generic Letter 1984-01 | 5 January 1984 | NRC Generic Letter 1984-001: NRC Use of the Terms, Important to Safety and Safety Related |
| ML20126F966 | 13 March 1981 | Forwards Applicable PWR Encl to NRC Re Control of Heavy Loads.Bwr Encl Inadvertently Transmitted |
| NRC Generic Letter 1980-11 | 22 December 1980 | NRC Generic Letter 1980-113, Control of Heavy Loads. |
| ML18136A223 | 26 June 1979 | Submits Followup Questions from Subcommittee on Nuclear Regulation 790316 Hearing Re Shutdown of Five Nuclear Power Plants Due to Error in Seismic Design Analysis.Requests Comment |