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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- 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)
- ML22349A648 + (PWROG Risk Management Committee Meeting Dec 2022)
- ML18072A215 + (PWROG Shield Implementation Concerns Revision a)
- ML24051A015 + (PWROG Slides Public Meeting SCC Rev 0 for Transmission)
- ML18019A215 + (PWROG-14001-NP-A ,Revision 1, PRA Model for the Generation III Westinghouse Shutdown Seal)
- ML15149A280 + (PWROG-14083-NP, Revision 1, NextEra Energy, Seabrook Unit 1, Summary Report for Applicant/Licensee Action Items 1, 2, and 7)
- ML15149A282 + (PWROG-15023-NP, Revision 1, Seabrook Station, Unit 1, Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability)
- ML15170A378 + (PWROG-15039-NP, Revision 0, Waterford Unit 3 Summary Report for the Fuel Design / Fuel Management Assessments to Demonstrate MRP-227-A Applicability)
- ML15149A283 + (PWROG-15042-P, Revision 0, Appendix a, NextEra Energy, Seabrook, Unit 1, Summary Report for the Cold Work Assessment (Non-Proprietary). Application for Withholding Proprietary Information from Disclosure and Affidavit)
- ML15170A379 + (PWROG-15054-NP, Revision 1, Waterford, Unit 3, RAI Response for Applicant Action Items 1, 2, and 7)
- ML18246A003 + (PWROG-15060-P, Pump Suction Gas Accumulation Operability Criteria Guidance Draft Safety Evaluation Review Meeting)
- ML15223A436 + (PWROG-15066-NP, Revision 0, Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program)
- ML17075A195 + (PWROG-15105-NP PA-MSC-1288 PWR Rv Internals Cold-Work Assessment, Materials Committee)
- ML19158A230 + (PWROG-15109 Draft SE)
- EPID:L-2018-TOP-0009 + (PWROG-15109 Draft SE)
- ML19072A095 + (PWROG-17011 Draft SE)
- ML19198A050 + (PWROG-17011 Final SE)
- ML19042A138 + (PWROG-17011-NP, Revision 2, Update for Subsequent License Renewal: WCAP-14535A, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination and WCAP-15666-A, Extension of Reactor Coolant Pump Motor Flywheel Examination)
- ML20294A541 + (PWROG-17018 TR -A Verification Review Form1)
- ML18170A114 + (PWROG-17033-NP, Revision 1, Update for Subsequent License Renewal: WCAP-13045, Compliance to ASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems.)
- ML18114A185 + (PWROG-17034-NP, Rev. 0, Evaluation of the WCAP-10325-P-A Westinghouse LOCA Mass & Energy Release Methodology)
- ML19226A255 + (PWROG-17090, Rev 0, Draft Safety Evaluation)
- EPID:L-2018-TOP-0017 + (PWROG-17090, Rev 0, Draft Safety Evaluation)
- ML18114A183 + (PWROG-17090-NP, Revision 0, Generic Rotterdam Forging and Weld Initial Upper-Shelf Energy Determination)
- ML19338G221 + (PWROG-18029-NP, Rev. 0, Component Reliability Data Issues for Discussion with NRC Research)
- ML20279A597 + (PWROG-18029-NP, Revision 1, Component Reliability Data Issues for Discussion with NRC Research)
- ML20294A657 + (PWROG-18034 TR - a Topical Report Verification Review Determination)
- ML21243A572 + (PWROG-18068 TR Acceptance Review Form)
- ML20294A116 + (PWROG-18068, Use of Direct Fracture Toughness for Evaluation of RPV Integrity)
- ML21209A933 + (PWROG-18068-NP, Rev. 1, Use of Direct Fracture Toughness for Evaluation of RPV Integrity)
- ML23180A190 + (PWROG-18068-NP, Revision 1, Markup June 2023)
- ML25105A085 + (PWROG-18068-NP, Revision 1-A, Use of Direct Fracture Toughness for Evaluation of RPV Integrity (Non-proprietary))
- ML20149K671 + (PWROG-19047-NP, Revision 0, North Anna, Units 1 and 2, Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis)
- ML21264A535 + (PWROG-19047-NP-A, Rev 0, North Anna Units 1 and 2 Reactor Vessels Low Upper-Shelf Fracture Toughness Equivalent Margin Analysis)
- ML21084A099 + (PWROG-20015-NP, Revision 1, Alternate 10 CFR 50.69 Defense-in-Depth Categorization Process)
- ML20290B122 + (PWROG-20016 TR Acceptance Review Form to Vendor)
- ML21313A374 + (PWROG-20016-P/NP, Revision Rev. 0, PWROG-Regulatory Relaxation for PWR Loose-Part Detection Systems - Comment Resolution Table)
- ML21007A218 + (PWROG-20025-NP, Revision 0, Methodology for Adjusting Reactor Pressure Vessel Embrittlement Predictions Using Heat-Specific Surveillance Data)
- ML23160A028 + (PWROG-20037-NP Revision 0 PRA Upgrade/Maintenance and Newly Developed Methods Examples)