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Issue date | Title | Topic | |
---|---|---|---|
ML20100J282 | 30 September 1984 | Rev 1 to Palo Verde Nuclear Generating Station Cycle 1 Core Protection Sys & Control Element Assembly Calculator Data Base Listing | |
ML20100M126 | 31 January 1984 | Interim Rept on Palo Verde Nuclear Generating Station Reactor Coolant Pumps | |
ML20106A605 | 30 April 1983 | Errata & Addenda Sheet 10,replacing Page 4-11 to, LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | |
ML20106A648 | 31 January 1985 | Errata & Addenda Sheet 13,replacing Pages v/vi,3-2,4-3, 4-15 & 4-16 to, LOCA Anaysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | Fuel cladding |
ML20106F636 | 31 October 1984 | Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Callaway & Wolf Creek Plants | Safe Shutdown Earthquake Pressure boundary leak |
ML20111C117 | 31 January 1985 | Rev 1 to Comprehensive Vibration Assessment Program for Palo Verde Nuclear Generating Station Unit 1 (Sys 80 Prototype),Evaluation of Predictions & Pre-Core Hot Functional Measurement & Insp Programs | Flow Induced Vibration |
ML20111C133 | 28 February 1985 | Nonproprietary Rev 1-NP to, Response to NRC Questions on Core Protection Calculator Software,Palo Verde Nuclear Generating Station,Unit 1 | |
ML20127K138 | 30 June 1985 | Nuclear Physics Methodology for Reload Design | |
ML20128E074 | 31 July 1992 | Nonproprietary Pvngs,Unit 1 EOC 3 Exam Rept | |
ML20128Q275 | 31 May 1985 | Revised Nomad Code & Model | |
ML20129E988 | 30 May 1985 | VEPCO Reactor Sys Transient Analysis Using Retran Computer Code | Boric Acid |
ML20133H359 | 31 July 1985 | Statistical DNBR Evaluation Methodology | |
ML20134N294 | 31 July 1985 | Rev 00 to Functional Design Requirement for Control Element Assembly Calculator | Anticipated operational occurrence |
ML20134N302 | 31 July 1985 | Rev 00 to Functional Design Requirement for Core Protection Calculator | Anticipated operational occurrence |
ML20135A557 | 31 August 1985 | B&W Owners Group Cavity Dosimetry Program | |
ML20135H949 | 31 August 1985 | Rev 1 to Reload Nuclear Design Methodology | Boric Acid Shutdown Margin |
ML20138M421 | 30 September 1985 | Justification for Raising Setpoint for Reactor Trip on High Pressure, Transient Assessment Program | |
ML20138P154 | 2 July 1985 | Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation, Topical Rept | |
ML20140A682 | 31 December 1985 | Reactor Vessel Fluence & Ref Temp for Pressurized Thermal Shock Evaluations | |
ML20140D889 | 31 October 1984 | VEPCO Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs | Power change |
ML20150E666 | 29 February 1988 | Charging Pump Gas Binding & Cracked Block Evaluation Rept | Boric Acid Finite Element Analysis |
ML20151Z052 | 31 January 1986 | Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure | |
ML20151Z064 | 31 January 1986 | Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines | |
ML20154J983 | 30 April 1988 | RCS Flow Anomaly Investigation Rept | |
ML20154M242 | 30 September 1988 | Simulate-3 Validation & Verification | |
ML20155G710 | 31 May 1988 | End-Of-Cycle 1 Surveillance Fuel Exam Rept | |
ML20155J491 | 31 May 1986 | Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block | Anticipated operational occurrence |
ML20155J505 | 31 May 1986 | Rev 1 to Functional Design Requirements for Control Element Assembly Calculator | Anticipated operational occurrence |
ML20155J523 | 31 May 1986 | Rev 1 to Functional Design Requirement for Core Protection Calculator | Anticipated operational occurrence |
ML20203G548 | 31 March 1986 | Relaxed Power Distribution Control Methodology & Associated Fq Surveillance Tech Specs | Power change |
ML20205F271 | 31 August 1985 | Errata & Addenda Sheet 14,replacing Pages v/vi,3-2,4-3,4-10, 4-15 & 4-16 to, LOCA Analysis Rept for Dresden Units 2,3 & Quad Cities 1,2 Nuclear Power Stations | Fuel cladding |
ML20207H976 | 30 November 1986 | Nonproprietary Resistance Temp Detector Bypass Elimination Licensing Rept for Byron 1 & 2 & Braidwood 1 & 2 | Hydrostatic Nondestructive Examination |
ML20207L778 | 6 October 1988 | Nonproprietary WCAP 11936, McGuire Unit 2 Evaluation for Tube Vibration Induced Fatigue | Finite Element Analysis Flow Induced Vibration |
ML20207L926 | 30 September 1988 | Nonproprietary Addendum 2 to COBRA-NC,Analysis for Main Steamline Break in Catawba Unit 1 Ice Condenser Containment (Response to NRC Questions) | |
ML20210A605 | 5 September 1986 | Addendum a to Vol II of Nusco 140-2, Nusco Thermal Hydraulic Model Qualification | |
ML20210E487 | 31 December 1985 | Comprehensive Vibration Assessment Program for Palo Verde Generating Station Unit 2 (Sys 80 Nonprototype-Category 1), Evaluation of Pre-Core Hot Functional Insp Program, Preliminary Rept | |
ML20235M221 | 13 July 1987 | Nonproprietary Rev 01-NP to Modified Statistical Combination of Uncertainties | |
ML20235M911 | 20 February 1989 | Nonproprietary Catawba Unit 1 Evaluation for Tube Vibration Induced Fatigue | Flow Induced Vibration |
ML20236B621 | 30 June 1987 | Structural & Seismic Evaluation of Palo Verde Charging Pump Block | |
ML20237C409 | 30 November 1987 | Nonproprietary Rev 2 to Byron/Braidwood T-Hot Reduction Final Licensing Rept | Boric Acid Loop seal Turbine Missile Fuel cladding Flow Induced Vibration |
ML20237J313 | 31 August 1984 | Rev 1 to Final Rept on Palo Verde Nuclear Generating Station Reactor Coolant Pumps | Hydrostatic Nondestructive Examination Liquid penetrant Coast down |
ML20238E734 | 31 August 1984 | Nonproprietary Rept on Palo Verde Nuclear Generating Station LPSI Pumps Failure to Start. Related Documentation Encl |