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Issue date | Title | |
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ML040340070 | 31 January 2004 | NUREG/CR-6839 Fort Saint Vrain Gas Cooled Reactor Operational Experience. |
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 |
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 |
Information Notice 1997-05, Offsite Notification Capabilities | 27 February 1997 | Offsite Notification Capabilities |
ML20129C042 | 20 September 1996 | Forwards Quarterly Submittal of 10CFR50.59 Rept of Changes, Tests & Experiments for Facility Decommissioning,Covering Period of 960601-0831 |
Information Notice 1996-09, Damage in Foreign Steam Generator Internals | 12 February 1996 | Damage in Foreign Steam Generator Internals |
ML20095K413 | 26 December 1995 | Rev 3 to Decommissioning Plan |
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 |
ML20086S247 | 9 February 1995 | Decommissioning Plan for Fort St Vrain Nuclear Generating Station |
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 |
Information Notice 1994-32, Revised Seismic Estimates | 29 April 1994 | Revised Seismic Estimates |
ML063530662 | 24 February 1994 | Letter Submitting Response to Nrc'S Request for Additional Information Regarding Model No. TN-FSV Packaging |
ML20064N761 | 31 December 1993 | Annual Radioactive Effluent Release Rept Jan-Dec 1993. W/ |
ML20058Q379 | 21 December 1993 | Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station |
ML20058Q370 | 21 December 1993 | Forwards Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station. Rev Reflects Changes Discussed in 930304,0609,0909 & 1209 Quarterly Repts of Changes,Tests & Experiments,Per 921123 Decommissioning Order |
ML20118B214 | 25 September 1992 | Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions |
ML20095L067 | 30 April 1992 | Suppl to Applicants Environ Rept - Post Operating License Stage - Decommissioning |
ML20095E960 | 17 April 1992 | Rev to Fort St Vrain Proposed Decommissioning Plan |
ML20094L283 | 19 March 1992 | Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning |
ML20086D689 | 15 November 1991 | Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station |
ML20082L931 | 30 August 1991 | Proposed Tech Specs Re Decommissioning |
ML20082H885 | 16 August 1991 | Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response |
ML20091C414 | 2 August 1991 | Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header |
ML20082C502 | 31 July 1991 | Suppl to Applicants Environ Rept - Post Operating License Stage - Decommissioning |
ML20077B902 | 26 April 1991 | Responds to NRC Request for Addl Info Re Proposed Decommissioning Plan.Vols I & II of Activation Analysis, Encl |
ML20072V529 | 12 April 1991 | Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization |
ML20070V687 | 20 March 1991 | Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room |
ML20072S052 | 15 March 1991 | Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station |
ML20066J117 | 15 February 1991 | Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION |
ML20087E689 | 15 January 1991 | Forwards Results of Final Structural Evaluation of Prestressed Concrete Reactor Vessel During Decommissioning & Prestressing Tendons Detensioned |
ML20066A378 | 21 December 1990 | Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration |
ML20058N107 | 10 August 1990 | Issue 56 to AOP-I, Discussion of Fire |
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 |
ML20043A949 | 11 May 1990 | Forwards Issue 59 to AOP-K-1, Environ Disturbances - Earthquake. |
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 |
ML19351A327 | 13 October 1989 | Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features |
ML20247G781 | 14 September 1989 | Proposed Tech Specs,Documenting Design Features for Defueling Phase of Operation |
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. |
ML20245L406 | 31 August 1989 | Safety Analysis Rept for Reactor Defueling |
ML20246E562 | 24 August 1989 | Forwards Clearer Copy of Ltr P-89314 & SAR Re Extended Operation of Cycle 4 |
ML20246D923 | 18 August 1989 | Summary of 890718 Meeting W/Util to Discuss Defueling of Plant.List of Attendees,Agenda & Viewgraphs Encl |
ML20245J823 | 31 May 1989 | SAR for Cycle 4 Extended Operation |