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Issue date | Title | |
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ML20095K413 | 26 December 1995 | Rev 3 to Decommissioning Plan |
ML20081E932 | 14 March 1995 | Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning for Period 941116- 950215,per Condition (b)(2) of NRC 921123 Order Approving Decommissioning Plan & Authorizing Decommissioning of Fsv |
ML20086S247 | 9 February 1995 | Decommissioning Plan for Fort St Vrain Nuclear Generating Station |
ML20086S256 | 30 March 1994 | Forwards Summary of Radiation Exposures Received for 1993 |
ML20058Q379 | 21 December 1993 | Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station |
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 |
ML20091D763 | 11 October 1991 | Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp |
ML20082C502 | 31 July 1991 | Suppl to Applicants Environ Rept - Post Operating License Stage - Decommissioning |
ML20087E689 | 15 January 1991 | Forwards Results of Final Structural Evaluation of Prestressed Concrete Reactor Vessel During Decommissioning & Prestressing Tendons Detensioned |
ML20245L406 | 31 August 1989 | Safety Analysis Rept for Reactor Defueling |
ML20235T451 | 24 February 1989 | Safety Evaluation Re Facility Core Support Flow Vent Sys. Continued Operation of Facility W/Current Core Support Flow Sys Configuration Acceptable |
ML20154E790 | 8 September 1988 | Forwards Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Sufficient Justification Exists to Warrant Continued Operation of Plant W/Existing Pump Design Configurations |
ML20155B841 | 2 September 1988 | Operational Safety Team Insp Rept 50-267/88-200 on 880509-20.Major Areas Inspected:Operations,Maint, Surveillance,Mgt Oversight,Safety Review & QA Programs |
ML20154P146 | 27 May 1988 | Responds to IE Bulletin 85-001 & Generic Ltr 88-03 Re Steam Binding Concerns.Steam Bindings Precluded at Plant for Feedwater Pumps,Condensate Pumps & Fire Water Pumps Due to Existing Design,Configuration & Procedural Requirements |
ML20148H692 | 18 March 1988 | Forwards Safety Evaluation Re Core Support Floor Casing Leak.Table Depicting Effects of Variations in Primary Coolant Activity Concentrations & Release Rates on Offsite Doses & 10CFR20 Limits Also Encl |
ML20150C454 | 10 March 1988 | Safety Evaluation Concluding That Seismic Analysis Methods for Bldg 10 & Walkover Structure Conservative.Gaps Provided Adequate to Accommodate Relative Motions Which Occur Between Subj Structures & Walkover Structure & Turbine Bldg |
ML20195H873 | 14 January 1988 | Final Rept on Fort St Vrain 871002-03 Fire |
ML20236B218 | 22 July 1987 | Forwards Rev 5 to Updated FSAR for Fort St Vrain.Rev Includes Effects of Changes Made to Facility or Procedures, Safety Evaluations & Analyses of New Safety Issues Performed by or on Behalf of Util Per NRC Request |
ML20235F515 | 2 July 1987 | Safety Evaluation Re Safe Emergency Shutdown of Reactor Sys. Operation at 82% Acceptable |
ML20216E230 | 24 June 1987 | Responds to Listed Questions Re Tech Spec Changes Proposed in Concerning Analysis of Firewater Cooldown for 82% Power Operation,Per 870622 Telcon |
ML20215J540 | 22 June 1987 | Draft Safety Evaluation Re Safe Emergency Shutdowns.Facility Operation at 82% Power Acceptable |
ML20235G114 | 4 June 1987 | Draft Fort St Vrain Safe Shutdown from 82% Power, Technical Evaluation Rept |
ML20234C609 | 4 June 1987 | Fort St Vrain Safe Shutdown from 82% Power, Technical Evaluation Rept |
ML20209B721 | 17 April 1987 | Forwards Comments on Tech Spec Upgrade Program for Limiting Condition for Operations (Lcos) for safety-related Cooling functions,marked-up Redrafted LCOs & List of NRC Comments Addressed in Encl 1,for Review within 75 Days of Ltr Date |
ML20205T398 | 1 April 1987 | Responds to 870309 Telcon Request for Written Discussion Explaining How Facility Definition of safety-related Equipment Meets Intent of Generic Ltr 83-28,Item 2.2 |
ML20211B569 | 13 February 1987 | Responds to 861020 Telcon Requesting Submittal of Ltr Describing Overall Status of Inservice Insp & Testing Program & Program Plan.Forwards,For Info,Draft Portions of Program Plan & Program Development Schedule |
ML20207P993 | 13 January 1987 | SAR for Tech Spec Limiting Condition for Operation 4.3.1 Change Permitting Safe Shutdown Cooling W/Evaporator- Economizer-Superheater |
ML20207P444 | 31 December 1986 | Monthly Operating Rept for Dec 1986 |
ML20207J779 | 30 December 1986 | Safety Evaluation Supporting Util 840813 Response Re Dynamic Loading of Cracked Fuel Element |
ML20211A904 | 8 October 1986 | Responds to NRC Tech Spec Upgrade Program Questions Re Use of non-safety Grade Equipment for DHR & Helium Circulator Drive.Use of non-safety Grade Boiler Feed Pumps to Provide Primary Coolant Circulation Approved |
ML20211C830 | 30 September 1986 | Monthly Operating Rept for Sept 1986 |
ML20207J793 | 9 July 1986 | Fort St Vrain Fuel Element Dynamic Response |
ML20198A027 | 12 May 1986 | Responds to NRC 860219 Questions Re Bldg 10 & Walkover Structure.Walkover Structure & Bldg 10 Designed Such That Structural Elements Will Not Impact on Adjacent Bldgs During Seismic Event |
ML20211E084 | 20 February 1986 | Issue a to Fort St Vrain:Delayed Firewater Cooldown;Effect of Liner Cooling on Orifice Valve Temps |
ML20153H073 | 19 February 1986 | Safety Evaluation Supporting Bldg 10 & Walkover Structure Design,Per FSAR Requirements for Category 1 Bldgs.Lack of Clearance Between Structures Should Be Addressed by Util |
ML20136F210 | 31 December 1985 | Issue B to Sar,Steam Line Rupture Detection/Isolation Sys |
ML20138P331 | 20 December 1985 | Forwards Response to 851101 Request for Addl Info Re App R Safe Shutdown Model.Steps Included in Fire Protection Shutdown Procedure for Operators to Properly Position motor- Operated Valves |
ML20205C845 | 10 September 1985 | Forwards Info Supporting 850830 Request to Operate at 8% Power to Facilitate Core Dryout for 45 Days,Per 850826,0903 & 04 Telcons.Moisture Removal Needed to Maintain Conditions Prescribed in FSAR & Tech Specs |
ML20127N655 | 14 June 1985 | Responds to Concerns Raised During 850516 Meeting in Bethesda,Md Re Review of Emergency Electric Power Sys. Response Addresses Independence of Redundant Emergency Power Trains,Rapid Transfer Sys Testing & Switchgear Control Sys |
ML20101U041 | 31 January 1985 | Control Rod Sys Operability Evaluation |
ML20095J441 | 13 August 1984 | Forwards Response to Nrc/Lasl Concerns Re Cracked Fuel Element Integrity. Issues Raised by Lasl Pose No Problem W/ Regard to Fuel Elements W/Cracked Webs |
ML20078E781 | 27 September 1983 | Forwards LERs 79-035/01X-1,81-008/03X-2,81-030/03X-2 & 81-055/03X-1 |
ML20080H068 | 16 September 1983 | Masonry Wall Design,Fort St Vrain Nuclear Plant, Technical Evaluation Rept |
ML20063E344 | 24 August 1982 | Responds to IE Bulletin 80-11, Masonry Wall Design, Per NRC 820721 Request.Responses to Questions 2,4 & 14 Re Stack Bonding & Modeling Techniques Encl |
ML20003G364 | 23 December 1980 | Provides Supplemental Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety Related Piping Sys. Util Completed Field Audit of All Accessible safety-related Piping Equal to or Greater than 2-1/2 Inches in Diameter |
ML19331C991 | 30 June 1980 | Responds to IE Bulletin 79-14, Updating 791015 Commitment to Rept Discrepancies & Corrective Actions Re Seismic Review for as-built safety-related Piping Sys.Summary of Corrective Actions for 800414-0613 Encl |
ML19208B216 | 13 September 1979 | LER 79-035/01T-0:on 790831,field Audit Analysis Indicated Inconsistencies in Hangers of as-built safety-related Piping.Caused by Design & Installation Inconsistencies. Remaining Hangers Being Analyzed |
ML19253B478 | 4 September 1979 | Discusses Completed Field Audit & Preliminary Engineering Analysis of Random Sample of as-built safety-related Piping in Response to 790801 Ltr.Submits Proposal for Concurrence Re Returning of Reactor to Power Operation |
ML20062C706 | 30 October 1978 | Forwards First Part of Ga'S Response to 780919 NRC Questions Re Addl Info on H-451 Graphite.Responses to Remaining Questions Will Be Submitted 781124 |