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| Issue date | Title | |
|---|---|---|
| NRC-2018-0180, Opportunity to Review and Comment on an NRC Information Collection Request for Info Pursuant to 10 CFR 50.54(f) Recomms 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-chi Event | 27 December 2018 | Opportunity to Review and Comment on an NRC Information Collection Request for Info Pursuant to 10 CFR 50.54(f) Recomms 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-chi Event |
| ML19010A086 | 27 December 2018 | NRR E-mail Capture - Opportunity to Review and Comment on an NRC Information Collection Request for Info Pursuant to 10 CFR 50.54(f) Recomms 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-chi Event |
| ML103260157 | 11 November 2010 | Report of Emergency Plan Change |
| ML102920053 | 12 October 2010 | Revisions to Emergency Plan Manual as Listed |
| ML101380329 | 6 May 2010 | Procedure Transmittal of Revisions to the Emergency Plan Manual |
| ML091600467 | 1 June 2009 | and Rancho Seco Independent Spent Fuel Storage Installation - 2008 Annual Financial Report |
| ML083190249 | 5 November 2008 | Rancho Seco Independent Spent Fuel Storage Installation Proposed License Amendment No. 3 |
| ML081770333 | 17 June 2008 | & ISFSI - 2007 Annual Financial Report |
| ML071000434 | 2 April 2007 | Response to NRC Request for Additional Information |
| ML062220351 | 3 August 2006 | Historical Site Assessment, Revision 1 |
| ML061460157 | 30 April 2006 | License Termination Plan, Chapter 8, Supplement to the Environmental Report |
| ML061430214 | 30 April 2006 | Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station License Termination Plan, Rev. 0. Chapter 6. Compliance with the Radiological Criteria for License Termination Through End |
| ML051020434 | 7 April 2005 | Radionuclides for Consideration During Rancho Seco Site Characterization or Final Status Surveys |
| ML042290216 | 29 July 2004 | ISFSI Proposed License Amendment No. 2 for the Storage of Greater than Class C Waste |
| ML003729742 | 30 June 2000 | Encl 1 - Materials License for 06/30/00 - Ltr s Redeker, Sacramento Municipal Utility District (Smud) Issuance of Materials License SNM-2510 for the Rancho Seco Independent Spent Fuel Storage Installation (ISFSI) (TAC No. L10017) Scan No. S |
| ML20155D480 | 27 October 1998 | Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode |
| Information Notice 1997-78, Crediting of Operator Actions in Place of Automatic Actions & Modifications of Operator Actions, Including Response Times | 23 October 1997 | Crediting of Operator Actions in Place of Automatic Actions & Modifications of Operator Actions, Including Response Times |
| Information Notice 1997-71, Inappropriate Use of 10 CFR 50.59 Regarding Reduced Seismic Criteria for Temporary Conditions | 22 September 1997 | Inappropriate Use of 10 CFR 50.59 Regarding Reduced Seismic Criteria for Temporary Conditions |
| Information Notice 1997-53, Circuit Breakers Left Racked Out in Non-Seismically Qualified Positions | 18 July 1997 | Circuit Breakers Left Racked Out in Non-Seismically Qualified Positions |
| Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes | 19 May 1997 | Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes |
| Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head | 16 May 1997 | Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head |
| Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation | 9 May 1997 | Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation |
| Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities | 7 May 1997 | Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities |
| ML20138F532 | 28 April 1997 | Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application |
| Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake | 25 April 1997 | Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake |
| ML20137W815 | 20 March 1997 | Amend 1 to Post Shutdown Decommissioning Activities Rept |
| Information Notice 1997-05, Offsite Notification Capabilities | 27 February 1997 | Offsite Notification Capabilities |
| ML20129E715 | 14 October 1996 | Defueled SAR for Rancho Seco |
| Information Notice 1996-09, Damage in Foreign Steam Generator Internals | 12 February 1996 | Damage in Foreign Steam Generator Internals |
| NRC Generic Letter 1995-10 | 15 December 1995 | NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation |
| 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 |
| Information Notice 1994-32, Revised Seismic Estimates | 29 April 1994 | Revised Seismic Estimates |
| Information Notice 1993-53, Effect of Hurricane Andrew on Turkey Point Nuclear Generating Station and Lessons Learned | 29 April 1994 | Effect of Hurricane Andrew on Turkey Point Nuclear Generating Station and Lessons Learned |
| ML20217A571 | 28 August 1990 | Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage |
| NRC Generic Letter 1990-05 | 15 June 1990 | NRC Generic Letter 1990-005: Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping |
| Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves | 8 March 1990 | Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves |
| NRC Generic Letter 1989-21 | 19 October 1989 | NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements |
| NRC Generic Letter 1989-18 | 6 September 1989 | NRC Generic Letter 1989-018: Resolution of Unresolved Safety Issue A-17, Systems Interactions in Nuclear Power Plants. |
| NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 | 6 July 1989 | Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 |
| ML20245A190 | 9 June 1989 | Amend 110 to License DPR-54,revising Tech Specs by Removing Tabular Listing of Snubbers as Suggested by Generic Ltr 84-13 |
| ML20235N381 | 24 February 1989 | Advises of Intent to Use General Funds in Event of Retrospective Premium Assessment.Official Statement,Dtd 881027,which Includes Projection of District Finances on Page A-7 Encl |
| NL-89-046, Forwards Rept of 1988 Annual Emergency Exercise Conducted on 881003.Exercise Included Util & Offsite Agency Participation & Was Evaluated by NRC & FEMA | 23 January 1989 | Forwards Rept of 1988 Annual Emergency Exercise Conducted on 881003.Exercise Included Util & Offsite Agency Participation & Was Evaluated by NRC & FEMA |
| Information Notice 1988-25, Minimum Edge Distance for Expansion Anchor Bolts | 16 May 1988 | Minimum Edge Distance for Expansion Anchor Bolts |
| ML20151W740 | 26 April 1988 | Responds to Re Concerns of 750801 Oroville Earthquake & 860721 Bishop Earthquake W/Respect to Safety of Facility.Allegations Provided No Basis for Safety Concern W/Respect to Seismic Design of Plant |
| ML20151C364 | 24 March 1988 | Insp Rept 50-312/87-44 on 871205-880203.Violation Noted. Major Areas Inspected:Operational Safety Verification,Maint, Surveillance & Followup Items |
| ML20151W768 | 18 February 1988 | Discusses Failure of Smud to Keep Pledge to Ratepayers to Go Beyond Minimal Get by Commitment of Mgt in Past to Be Thorough & Complete in Exploring All Possible Problems at Facility |
| 05000312/LER-1987-029, Forwards Proposed Alarm Sys Mods NFPA 72D Compliance, Ensuring That Plant Fire Protection & Detection Sys Meet NFPA Requirements,Per LER 87-29 Commitments.Corrective Actions Re Tech Spec Violation Also Encl | 2 January 1988 | Forwards Proposed Alarm Sys Mods NFPA 72D Compliance, Ensuring That Plant Fire Protection & Detection Sys Meet NFPA Requirements,Per LER 87-29 Commitments.Corrective Actions Re Tech Spec Violation Also Encl |
| Information Notice 1987-56, Improper Hydraulic Control Unit Installation at BWR Plants | 4 November 1987 | Improper Hydraulic Control Unit Installation at BWR Plants |
| ML20235Z581 | 31 August 1987 | Rev 2 to Wire & Cable Program Rept |
| ML20237J604 | 31 July 1987 | Rev 1 to Wire & Cable Program Rept |