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| Issue date | Title | |
|---|---|---|
| 3F0817-03, Rev. 0, Defueled Safety Analysis Report | 31 August 2017 | Rev. 0, Defueled Safety Analysis Report |
| ML12122A071 | 14 May 2012 | Enclosure 1: April 2012 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 |
| ML11256A074 | 20 July 2011 | License Amendment Request #310, Revision 1, Departure from a Method of Evaluation for the Auxiliary Building Overhead Crane, Revisions to Associated Commitments, and Response to Request for Additional Information |
| ML101060347 | 9 April 2010 | 5.2.2.4.4. Quality Control and Nondestructive Testing |
| ML102910700 | 1 December 2009 | Email - from: Williams, Charles R. (Charles.Williams@Pgnmail.Com) to Lake, Louis; Thomas, George; Nausdj@Ornl.Gov; Carrion, Robert Dated Tuesday, December 01, 2009 2:27 PM Subject: Draft Refute 8.4 for Review Attachments: Fm 8.4.pptx; Selec |
| ML090080055 | 16 December 2008 | License Renewal Application. Cover Page to Section 3.2 |
| ML083370315 | 17 November 2008 | Response to Request for Additional Information on License Amendment Request #303, Revision 0: Revision to Final Safety Analysis Report Sections 5.4.3, Structural Design Criteria, and 5.4.5.3, Missile Analysis. |
| 3F0208-05, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. | 29 February 2008 | Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. |
| ML20197B291 | 11 December 1997 | Generic Operability Evaluation for Large Bore Safety Related Piping at Crystal River-3 |
| ML20199D575 | 30 October 1997 | Overview of Safety Related Large Bore Piping & Piping Support Design & Construction Currently Existing at Crystal River-3 Nuclear Power Plant, Rev 0 |
| 3F0897-01, Forwards Response to RAI on Resolution of USI A-46,stating That Anchorage Calculations for Tanks & Heat Exchangers to Confirm Engineering Judgement of Anchorage Adequacy Will Be Completed Prior to Restart But No Later than 971201 | 1 August 1997 | Forwards Response to RAI on Resolution of USI A-46,stating That Anchorage Calculations for Tanks & Heat Exchangers to Confirm Engineering Judgement of Anchorage Adequacy Will Be Completed Prior to Restart But No Later than 971201 |
| ML20137R279 | 27 March 1997 | Twentieth Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App FF |
| ML20136C941 | 29 February 1996 | Plant Status Rept,Crystal River,Unit 3 |
| 3F0894-02, Provides Response to NRC Request for Addl Info Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue,Per GL 87-02 | 15 August 1994 | Provides Response to NRC Request for Addl Info Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue,Per GL 87-02 |
| 3F0988-16, Forwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe Breaks | 27 September 1988 | Forwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe Breaks |
| ML20215D674 | 12 June 1987 | Suppl 4 to Petition for Immediate Action to Relieve Undue Risk Posed by Nuclear Power Plants Designed by B&W.Ucs Reply to Responses from NRC & B&W Owners Group.* Certificate of Svc Encl |
| ML20211D993 | 21 March 1986 | Transient Assessment Program Rept for Rancho Seco Trip,Loss of Integrated Control Sys Power on 851226,Transient Assessment Program RS-86-01 |
| ML20137E719 | 13 January 1986 | Evaluation of RCS Components & Component Supports for Optimized Reactor Coolant Pump Support Configuration Loadings |
| 3F0385-14, Documents Results of Assessment of Impact of Capacity Re IE Bulletin 79-02 Wej-it Concrete Anchors Installed on Large Bore safety-related Piping Sys.Followup to Outstanding Issues Identified in Insp Rept 50-302/84-32 Provided | 14 March 1985 | Documents Results of Assessment of Impact of Capacity Re IE Bulletin 79-02 Wej-it Concrete Anchors Installed on Large Bore safety-related Piping Sys.Followup to Outstanding Issues Identified in Insp Rept 50-302/84-32 Provided |
| ML19274G122 | 13 July 1979 | Forwards Supplemental Response to IE Bulletin 79-02, Revision 1.All Pipe Hangers Will Be Upgraded to Appropriate or Greater Safety Factor,Prior to Facility Entering Mode 2 Status |
| ML19308D698 | 27 June 1977 | Investigation on Structural Safety of Spent Fuel Pool Due to Installation of High Capacity Fuel Racks. |