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A list of all pages that have property "Title" with value "PWR Std Problem 1". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML22039A142  + (PWR Owners Group, Transmittal of the Response to Request for Additional Information, RAIs Associated with WCAP-17096, Revision 3, Reactor Internals Acceptance Criteria Methodology and Data Requirements (PA-MSC-1567))
  • ML21099A173  + (PWR Owners Group, Transmittal of the Response to Request for Additional Information, RAIs 1-12 and 14 Associated with WCAP-17096, Revision 3, Reactor Internals Acceptance Criteria Methodology and Data Requirements (PA-MSC-1567))
  • ML23074A057  + (PWR Owners Group, Transmittal of the Responses to the NRC Request for Additional Information Associated with Topical Report PWROG-21001-P/NP, Revision 0,Hydrogen-Based Transient Cladding Strain Limit (PA Asc 1671))
  • ML23074A056  + (PWR Owners Group, Transmittal of the Responses to the NRC Request for Additional Information Associated with Topical Report PWROG-21001-P/NP, Revision 0,Hydrogen-Based Transient Cladding Strain Limit (PA Asc 1671))
  • ML24256A224  + (PWR Owners Group, Transmittal of the Responses to the Request for Additional Information, RAIs Associated with Topical Report PWROG-22021-P/NP, Revision 0, Justifications for the Proposed Changes to the Quadrant Power Tilt Ratio Technical s)
  • ML18143B745  + (PWR Owners Group: Submittal of Volume 1 and 4 RAI Responses for Topical Report WCAP-17788P/WCAP17788NP)
  • ML20072R473  + (PWR Pressure Vessel Integrity During Overcooling Accidents: a Parametric Analysis)
  • ML18067A229  + (PWR Pressure Vessel Nozzle Appendix G Evaluation)
  • ML20059N744  + (PWR RCS License Renewal Industry Rept)
  • ML20138Q267  + (PWR Radwaste Mgt Sys - Students Manual)
  • ML21285A046  + (PWR Reactor Internals Aging Management Strategies - 2021 Updates to MRP-231 for SLR)
  • ML21301A235  + (PWR Reactor Internals Aging Management Strategies - 2021)
  • ML13310A270  + (PWR Reactor Physics Methodology Using CASMO-3/SIMULATE-3)
  • ML20133D250  + (PWR Safety & Relief Valve Adequacy Rept for Georgia Power Co,Alvin W Vogtle Unit 1 & Unit 2,Original Issue)
  • ML17256A543  + (PWR Safety & Relief Valve Adequacy Rept for Rochester Gas & Electric Corp,Re Ginna Unit 1)
  • ML20054M492  + (PWR Safety & Relief Valve Adequacy Rept for AL Power Co, Joesph M Farley Unit 1 & Unit 2)
  • ML20054M017  + (PWR Safety & Relief Valve Adequacy Rept for Beaver Valley Unit 1)
  • ML18139B925  + (PWR Safety & Relief Valve Adequacy Rept for North Anna Units 1 & 2)
  • ML20054L667  + (PWR Safety & Relief Valve Adequacy Rept for Surry Units 1 & 2)
  • ML18139C010  + (PWR Safety & Relief Valve Test Program,Porv Block Valve Adequacy Rept for Vepco,North Anna Unit 1 & Unit 2)
  • ML20070V248  + (PWR Severe Accident Delineation and Assessment)
  • ML20126H938  + (PWR Std Problem 2)
  • ML20204B846  + (PWR Steam Generator Tube Integrity Program, Monthly Rept for Jul 1978.Topics Discussed Include,Chemical Defecting, Fatigue Testing & NDT)
  • ML19289C757  + (PWR Steam Generator Tube Integrity Program. Dec 1978 Monthly Progress Rept.Phase I Topical Rept Is Being Edited & Progress Was Made in All Phase II Tasks Except Stress Corrosion Cracking)
  • ML19263E674  + (PWR Steam Generator Tube Integrity Program, Monthly Progress Rept for Apr 1979)
  • ML19211D458  + (PWR Steam Generator Tube Integrity Program - Surry Reactor Program)
  • ML19294B342  + (PWR Steamline Break Analysis Assuming Concurrent Steam Generator Tube Rupture)
  • ML032030535  + (PWR Sump Performance Evaluation Methodology: Velocity Calculation, Draft, Attachment 4)
  • ML20138Q170  + (PWR Technology Manual - Westinghouse Design)
  • ML20024B217  + (PWR Technology,Tmi Unit 2, Vol 4, Safety Analysis)
  • ML20040D258  + (PWR Training Simulator Comparison W/Retran for Reactor Trip from Full Power, Informal Rept)
  • ML19341D000  + (PWR Training Simulator:Evaluation of Thermohydraulic Models for Main Steam Supply Sys)
  • ML15226A229  + (PWR Vessel Internals Program Plan for Aging Management of Reactor Internals)
  • ML20055D278  + (PWR Vessel License Renewal Industry Rept)
  • ML25259A244  + (PWROG Affidavit for 9-30-25 Closed Meeting Prop Presentation Slides)
  • ML20267A201  + (PWROG Benchmark - IDHEAS Versus HRA Calculator)
  • ML22196A391  + (PWROG Comments on U.S. NRC Level 3 Probabilistic Risk Assessment (PRA) Project, Volume 3x: Overview of Reactor, At-Power, Level 1, 2, and 3 PRAs for Internal Events and Internal Floods (ADAMS Accession No. ML22067A210))
  • ML21172A189  + (PWROG Evaluation of the Potential Non-Conservative Fracture Toughness in BWRVIP-100, Rev. 1-A)
  • ML21287A183  + (PWROG Generic Risk Informed Process for Evaluations (RIPE-G) Public Meeting - Final - 14 October 2021 - Non-proprietary (Slides))
  • ML21145A116  + (PWROG Lessons Learned from Derecho ASP)
  • ML21146A047  + (PWROG Lessons Learned from Derecho ASP - NRC Public Meeting: May 27, 2021)
  • ML24173A122  + (PWROG Materials Committee Update - Presentation 3)
  • ML19170A291  + (PWROG Meeting Compliance Presentation for 6-20-19- Final)
  • ML18232A074  + (PWROG Meeting Requests and Comments on PWROG-15060 Draft SE)
  • ML21152A028  + (PWROG Presentation Expanding RIPE Concept to Deal with Generic Issues for June 2, 2021 ACRS Meeting)
  • ML24067A323  + (PWROG Presentation Slides for March 11, 2024 NRC Public Meeting with PWROG Executive Committee)
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