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- ML20205F054 + (Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,(Required Actions Based On...Atws Events),Item 1.2, `Post-Trip Review, Data & Info Capabilities for VC Summer Nuclear Station Unit 1)
- ML20128G460 + (Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2, `Post-Trip Review:Data & Info Capabilities for Crystal River Nuclear Plant,Unit 3, Technical Evaluation Rept)
- ML20138P656 + (Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2, `Post-Trip Review:Data & Info Capabilities for Hope Creek Nuclear Station,Unit 1, Technical Evaluation Rept)
- ML20138K872 + (Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2 `Post-Trip Review:Data..., Technical Evaluation Rept)
- ML20138P808 + (Draft Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review:Data & Info Capabilities, for Rancho Seco Nuclear Generating Station, Technical Evaluation Rept)
- ML20128D111 + (Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, Post-Trip Review:Data & Info Capabilities for Jm Farley..)
- ML17254A637 + (Draft Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28,Item 1.2,`Post-Trip Review:Data & Info Capabilitiesfor Robert Emmet Ginna Nuclear Plant,Unit 1, Technical Evaluation Rept)
- ML20128D838 + (Draft Review of Licensee & Applicant Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review:Data & Info Capabilities, for Peach Bottom Atomic Power Station,Units 2 & 3, Technical Evaluation Rept)
- ML20148M628 + (Draft Review of Literature Re Transportation Risk Study)
- ML20125C260 + (Draft Review of Methods & Criteria for Dynamic Combinations in Piping Sys,Final Rept,FY79)
- ML20093H138 + (Draft Review of Millstone-3 Probabilistic Safety Study)
- ML20199L730 + (Draft Review of Operating Experience History Through 1984 of Haddam Neck for NRC Isap)
- ML13310A252 + (Draft Review of Operating Experience History of San Onofre 1 Through 1980 for NRC Sep)
- ML20134G452 + (Draft Review of Operating Experience History Through 1984 of Millstone 1 for NRC Integrated Safety Assessment Program)
- ML20080G313 + (Draft Review of Operating Experience for South Texas 1 & 2, 1991-1992.Related Info Encl)
- ML20205K263 + (Draft Review of Rept, Shipping Container Response to Severe Highway & Railroad Accident Conditions)
- ML20133A910 + (Draft Review of Risk Based Evaluation of Integrated Safety Assessment Program (Isap) Issues for Millstone Unit 1)
- ML20113E569 + (Draft Review of Seabrook Station Probabilistic Safety Assessment)
- ML20082B202 + (Draft Review of Seabrook Units 1 & 2 Emergency Feedwater Sys Reliability Analysis)
- ML20209E033 + (Draft Review of Selected Aspects of Swedish Mitigation Concept for BWR & PWR Plants)
- ML20136B485 + (Draft Review of Swedish Nuclear Power Program QA Activities. Related Documentation Encl)
- ML13098A134 + (Draft Review of Tennessee Valley Authority Commitment Related to Core Plate Bolt Stress Analysis)
- ML20090L851 + (Draft Review of Us Testing Field & Lab Const Test Data on Soils Used as Fill. Related Info Encl,Including Oversized Drawing & Bechtel Meeting Notes)
- ML20101R104 + (Draft Review of Vogtle Units 1 & 2 Auxiliary Feedwater Sys Reliability Analysis, Technical Evaluation Rept)
- ML20038C113 + (Draft Review of YAEC-1263, Seismic Response Spectra for Yankee Rowe Nuclear Power Station. Rept Does Not Adequately Incorporate Uncertainty in Zonation Seismicity Parameters & Upper Magnitude cut-off)
- ML20128C294 + (Draft Review:Geology)
- ML20073E309 + (Draft Revised Administrative Procedures,Including RRF-AP-2, RRF-AP-3,RRF-AP-4,RRF-AP-5,RRF-AP-6,RRF-AP-7,RRF-AP-8, RRF-AP-9,RRF-AP-10,RRF-AP-11,RRF-AP-12,RRF-AP-13,RRF-AP-14, RRF-AP-15 & RRF-AP-16)
- ML20199J283 + (Draft Revised Directive 8.12, Decommissioning Financial Assurance Instrument Security Program)
- ML17290A005 + (Draft Revised Model Safety Evaluation of TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B)
- ML19347C314 + (Draft Revised Notice of ACRS 800710-12 Meeting.Meeting Items Revised to Permit Discussion of Recent Operating Experience at Nuclear Facilities Which Represent Substantive Safety Issues Possibly Impacting Public Health & Safety)
- ML20042B930 + (Draft Revised Tech Spec 5.2-1 Re Design of Reactor Core)
- ML20136F262 + (Draft Revised Use of Past Earthquake Experience Data to Show Seismic Ruggedness of Certain Classes of Equipment in Nuclear Power Plants)
- ML20065A370 + (Draft Revision 1 to Analysis of Nominal Heat Removal Capacity of Crbr in Natural Circulation Mode)
- ML20040H232 + (Draft Revision 1 to Reg Guide 1.23, Meteorological Measurement Programs for Nuclear Power Plants)
- ML20052F247 + (Draft Revision 1 to Rept & Safety Evaluation of Browns Ferry Unit 3 Partial Scram Failure of 800628)
- ML20085H763 + (Draft Revision 1 to Temporary Instruction 2515/194 (April 6, 2020 Public Meeting))
- ML18047A511 + (Draft Revision 10 to Inservice Testing of Plant Valves)
- ML20010G737 + (Draft Revision 1B to Emergency Procedure Guidelines,Bwr 1 Through 6. One Oversize Drawing Encl.Aperture Card Will Be Available in PDR)
- ML21334A357 + (Draft Revision 2 - Fy 2021-2026 Inclusive Diversity Strategic Plan (1))
- ML21326A168 + (Draft Revision 2 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material, for ACMUI Review)
- ML19331D614 + (Draft Revision 2 to Corporate Operations Manual,Part IV - Functional Manuals,Section I - Nuclear QA Manual)
- ML032340563 + (Draft Revision 2 to Ice Condenser Utility Group Topical Report No. ICUG-001: Application of the Active Ice Mass Management Concept to the Ice Condenser Ice Mass Technical Specification)
- ML19260E299 + (Draft Revision 2, Inservice Insp & Testing,Proposed Tech Spec Surveillance Requirements,Pcrv Auxiliary Sys 11, for Inservice Insp Requirements)
- ML21340A251 + (Draft Revision 4 to Certificate of Compliance (CoC) Number 9355 for the 435-B Package, Package Identification Number USA/9355/B(U)-96)
- ML20058H520 + (Draft Revision 4 to Chemistry Instruction:Development & Use of Calibr Curves for Chloride Determinations Utilizing Chloride Electrodes Safety-Related. No Date)
- ML20030E050 + (Draft Revision 5 to QA Program Description for Design, Const & Operation of TVA Nuclear Power Plants)
- ML19338G026 + (Draft Revision 9 to QA Program Manual)
- ML18026A335 + (Draft Revision a to Process Control Program for Radwaste Solidification Sys)
- ML083440209 + (Draft Revision of Digital Instrumentation and Control Project Plan for Review and Comment)
- ML103340448 + (Draft Revision to FSME Procedure SA-800 Providing NRC Predecisional Documents to Agreement States, Organization of Agreement States, Inc., and Appropriate Working Groups of the Conference of Radiation Control Program Directors, Inc)
- ML100900172 + (Draft Revision to Zone-Of-Influence Values in NRC Staff Safety Evaluation on NEI 04-07, Pressurized Water Reactor Sump Performance Evaluation Methodology for Certain Jacketed Insulations and Guidance for Installation of Sure-Hold Bands)