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Issue date | Title | Topic | |
---|---|---|---|
ML20140E112 | 10 April 1997 | Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co | |
ML20134D166 | 30 January 1997 | Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2) | |
ML20137S611 | 31 December 1996 | Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996 | Incorporated by reference |
ML20134G640 | 29 October 1996 | Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E | |
ML20134G686 | 29 October 1996 | Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G | |
ML20134G727 | 29 October 1996 | Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J | |
ML20134G617 | 29 October 1996 | Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results | |
ML20134G632 | 26 October 1996 | Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D | |
ML20133D783 | 22 October 1996 | Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003 | |
ML20116A466 | 19 July 1996 | Fsv Final Survey Exposure Rate Measurements | |
ML20112C153 | 17 May 1996 | Fsv Final Survey Exposure Rate Measurements | |
ML20101G552 | 21 March 1996 | Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept | |
ML20095K975 | 15 December 1995 | Fort St Vrain Project Update Presentation to NRC, on 951207 & 15 | |
ML20137H353 | 31 December 1994 | Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses | |
ML20137S233 | 31 December 1994 | Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994 | Unanalyzed Condition Scaffolding |
ML20085H661 | 10 October 1991 | Assessment of Mgt Modes for Graphite from Reactor Decommissioning | Hydrostatic |
ML20091D767 | 1 October 1991 | Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change | |
ML20077P929 | 15 August 1991 | Final Rept, Verification of Fort St Vrain Activation Analysis | |
ML20072V503 | 12 April 1991 | Summary of Existing & Planned Work for Activation Verification,910415 | |
ML20029B673 | 5 March 1991 | Nonproprietary Estimated Blast Effect from Ft St Vrain Well 11 Analysis Methods Summary. | |
ML20059L592 | 13 September 1990 | Determination of Upper Bounds on Radiation Exposure Rates at Refueling Floor Above Defueled Region W/Crd Orifice Assemblies Radiation Shielding Removed | |
ML20042F907 | 1 May 1990 | Conceptual Plan & Cost Estimate for Early Dismantlement of Fort St Vrain Pcrv. | |
ML19332E818 | 1 December 1989 | Rev a to Fort St Vrain Site-Specific Decommissioning Cost Estimate Basis for Preliminary Decommissioning Plan. | Chernobyl Scaffolding |
ML19332C283 | 9 October 1989 | Fort St Vrain 3-D Neutron Source Analysis Using DIF3D. | |
ML19332E819 | 31 August 1989 | Rev a to Fort St Vrain Activation Analysis. | |
ML20245L406 | 31 August 1989 | Safety Analysis Rept for Reactor Defueling | Safe Shutdown Shutdown Margin Design basis earthquake Earthquake |
ML20246K132 | 31 July 1989 | Pcrv Tendon Surveillance Rept for Jul 1989.W/four Oversize Drawings | |
ML20245J326 | 14 June 1989 | Rev B to Evaluation of Cable/Equipment Separation for Bearing Water Pumps P-2101-S,P-2102 (Train B),P-2102-S (Train B) & P-2107 (Train B) for App R Requirements | Continuous fire watch Fire Protection Program Fire Watch |
ML20245C458 | 11 May 1989 | CRD Partial Scram Test Results & Max Daily Temp Rept, 890511-0531 | |
ML19332E821 | 23 February 1989 | Fort St Vrain Plateout Analysis for Decommissioning Study. | |
ML20206K111 | 21 November 1988 | Rev a to Engineering Evaluation of Interaction & Effects of Plant Protection Sys & Steam Line Rupture Detection/ Isolation Sys | Hot Short |
ML20154E098 | 31 August 1988 | Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings | |
ML20077B909 | 31 May 1988 | Vols I & II of Activation Analysis | |
ML20154A545 | 28 April 1988 | Integrated Sys Study of CRD Mechanism Rod Position Instrumentation | |
ML20154A550 | 28 April 1988 | Temp Prediction for CRD Mechanism Motors | |
ML20235A559 | 31 January 1988 | Pcrv Tendon Interim Surveillance Rept. W/Four Oversize Drawings | |
ML20148G794 | 22 January 1988 | Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities | Non-Destructive Examination |
ML20148G851 | 22 January 1988 | Helium Circulator Insp Schedule | |
ML20195H873 | 14 January 1988 | Final Rept on Fort St Vrain 871002-03 Fire | Safe Shutdown Stroke time Design basis earthquake Fire Protection Program |
ML20236J291 | 30 October 1987 | Preliminary Rept on Impact of Fort St Vrain 871002 Fire | |
ML20235H473 | 11 September 1987 | Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification for Returning to Power Operation | |
ML20235K272 | 11 September 1987 | Preliminary Rept of Helium Circulator S/N C-2101 Damage Including Licensing Assessment | Safe Shutdown Earthquake Grace period Power change |
ML20195G968 | 11 August 1987 | Analyses Re Fort St Vrain DBA-2 Core Damage Frequency | Mission time |
ML20235W609 | 31 July 1987 | Pcrv Tendon Interim Surveillance Rept | |
ML20234C109 | 25 June 1987 | Issue B to Effect of Firewater Cooldown Using EES Bundle on Steam Generator Structural Integrity | |
ML20214Q998 | 31 May 1987 | Verification Rept for Buckle Computer Program | |
ML20215J871 | 4 May 1987 | Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling | Safe Shutdown |
ML20214P338 | 30 April 1987 | Rev 3 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 4, Exemptions & Mods | Safe Shutdown Emergency Lighting Exemption Request Fire Watch Hourly Fire Watch |
ML20214P314 | 30 April 1987 | Rev 5 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 2, Electrical Reviews | Hot Short Safe Shutdown |
ML20214P306 | 30 April 1987 | Rev 7 to App R Evaluation - Fort St Vrain Nuclear Generation Station Rept 1, Shutdown Model | Safe Shutdown Exemption Request |