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 Issue dateTitle
ML20095K41326 December 1995Rev 3 to Decommissioning Plan
ML20081E93214 March 1995Forwards 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
ML20086S2479 February 1995Decommissioning Plan for Fort St Vrain Nuclear Generating Station
ML20086S25630 March 1994Forwards Summary of Radiation Exposures Received for 1993
ML20058Q37921 December 1993Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station
ML20095L06730 April 1992Suppl to Applicants Environ Rept - Post Operating License Stage - Decommissioning
ML20095E96017 April 1992Rev to Fort St Vrain Proposed Decommissioning Plan
ML20091D76311 October 1991Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp
ML20082C50231 July 1991Suppl to Applicants Environ Rept - Post Operating License Stage - Decommissioning
ML20087E68915 January 1991Forwards Results of Final Structural Evaluation of Prestressed Concrete Reactor Vessel During Decommissioning & Prestressing Tendons Detensioned
ML20245L40631 August 1989Safety Analysis Rept for Reactor Defueling
ML20235T45124 February 1989Safety Evaluation Re Facility Core Support Flow Vent Sys. Continued Operation of Facility W/Current Core Support Flow Sys Configuration Acceptable
ML20154E7908 September 1988Forwards 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
ML20155B8412 September 1988Operational Safety Team Insp Rept 50-267/88-200 on 880509-20.Major Areas Inspected:Operations,Maint, Surveillance,Mgt Oversight,Safety Review & QA Programs
ML20154P14627 May 1988Responds 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
ML20148H69218 March 1988Forwards 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
ML20150C45410 March 1988Safety 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
ML20195H87314 January 1988Final Rept on Fort St Vrain 871002-03 Fire
ML20236B21822 July 1987Forwards 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
ML20235F5152 July 1987Safety Evaluation Re Safe Emergency Shutdown of Reactor Sys. Operation at 82% Acceptable
ML20216E23024 June 1987Responds to Listed Questions Re Tech Spec Changes Proposed in Concerning Analysis of Firewater Cooldown for 82% Power Operation,Per 870622 Telcon
ML20215J54022 June 1987Draft Safety Evaluation Re Safe Emergency Shutdowns.Facility Operation at 82% Power Acceptable
ML20235G1144 June 1987Draft Fort St Vrain Safe Shutdown from 82% Power, Technical Evaluation Rept
ML20234C6094 June 1987Fort St Vrain Safe Shutdown from 82% Power, Technical Evaluation Rept
ML20209B72117 April 1987Forwards 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
ML20205T3981 April 1987Responds 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
ML20211B56913 February 1987Responds 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
ML20207P99313 January 1987SAR for Tech Spec Limiting Condition for Operation 4.3.1 Change Permitting Safe Shutdown Cooling W/Evaporator- Economizer-Superheater
ML20207P44431 December 1986Monthly Operating Rept for Dec 1986
ML20207J77930 December 1986Safety Evaluation Supporting Util 840813 Response Re Dynamic Loading of Cracked Fuel Element
ML20211A9048 October 1986Responds 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
ML20211C83030 September 1986Monthly Operating Rept for Sept 1986
ML20207J7939 July 1986Fort St Vrain Fuel Element Dynamic Response
ML20198A02712 May 1986Responds 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
ML20211E08420 February 1986Issue a to Fort St Vrain:Delayed Firewater Cooldown;Effect of Liner Cooling on Orifice Valve Temps
ML20153H07319 February 1986Safety Evaluation Supporting Bldg 10 & Walkover Structure Design,Per FSAR Requirements for Category 1 Bldgs.Lack of Clearance Between Structures Should Be Addressed by Util
ML20136F21031 December 1985Issue B to Sar,Steam Line Rupture Detection/Isolation Sys
ML20138P33120 December 1985Forwards 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
ML20205C84510 September 1985Forwards 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
ML20127N65514 June 1985Responds 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
ML20101U04131 January 1985Control Rod Sys Operability Evaluation
ML20095J44113 August 1984Forwards 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
ML20078E78127 September 1983Forwards LERs 79-035/01X-1,81-008/03X-2,81-030/03X-2 & 81-055/03X-1
ML20080H06816 September 1983Masonry Wall Design,Fort St Vrain Nuclear Plant, Technical Evaluation Rept
ML20063E34424 August 1982Responds to IE Bulletin 80-11, Masonry Wall Design, Per NRC 820721 Request.Responses to Questions 2,4 & 14 Re Stack Bonding & Modeling Techniques Encl
ML20003G36423 December 1980Provides 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
ML19331C99130 June 1980Responds 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
ML19208B21613 September 1979LER 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
ML19253B4784 September 1979Discusses 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
ML20062C70630 October 1978Forwards 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