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List of results
- ML21228A207 + (Attachment 5 - License for Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste)
- LR-N08-0224, Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0 + (Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0)
- ML083100828 + (Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0)
- ML19024A475 + (Attachment 5 - List of Regulatory Commitments)
- ML20178A675 + (Attachment 5 - Marked-up Technical Specification Pages)
- ML22153A181 + (Attachment 5 - Non-Proprietary Version of Licensing Summary Report)
- ML022620500 + (Attachment 5 - Non-proprietary Responses to NRC Requests for Additional Information (Reference Letter from Us NRC to J. L. Skolds, Dated 08/12/2002))
- ML091250566 + (Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Introduction Through Chapter 2, Section 2.5.7)
- ML091250569 + (Attachment 5 - Point Beach, Units 1 and 2, License Amendment Request 261, Extended Power Uprate, Licensing Report, Chapter 2, Section 2.5.8 Through Appendices)
- ML18169A229 + (Attachment 5 - Proposed SPS Emergency Plan Changes)
- ML18068A691 + (Attachment 5 - Proposed TS Bases Changes (for Information Only))
- ML22181B135 + (Attachment 5 - Replacement for Attachment 5, Cross-Reference of TSTF-505 and Callaway Technical Specifications, of ULNRC-06688)
- ML20307A331 + (Attachment 5 - Standardized Radiological Emergency Plan Revision EP-DR-1000, Revision 0, Dresden Station Radiological Emergency Plan)
- ML12030A269 + (Attachment 5 - State of New York� Letter to NRC Staff Dated October 21, 2009)
- ML100321316 + (Attachment 5 - Summary of Regulatory Commitments)
- ML061240266 + (Attachment 5 - Table La - Removed Details for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues)
- ML021220088 + (Attachment 5 - Table R - Relocated Specifications and Removed Details North Anna, Units 1 and 2, Amendments 231 and 212)
- ML15090A639 + (Attachment 5 - Technical Evaluation Report)
- ML16068A139 + (Attachment 5 - Technical Information for Proposed Initiating Conditions and Emergency Action Levels)
- ML13254A119 + (Attachment 5 - Updated Evacuation Time Estimates for LaSalle County Station Plume Exposure Pathway and ETE Review Criteria Checklist)
- ML14217A497 + (Attachment 5 - W3F1-2014-0005 - Waterford Steam Electric Station, Unit 3, List of Regulatory Commitments)
- ML14170A044 + (Attachment 5 - WBN Unit 2 TS and Tsb Through Developmental Revision I, and Trm and Trmb Through Developmental Revision D)
- RC-15-0020, Attachment 5 - Westinghouse LTR-PAFM-12-86 Flaw Tolerance Evaluation to Support Re-Categorization of V.C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements + (Attachment 5 - Westinghouse LTR-PAFM-12-86 Flaw Tolerance Evaluation to Support Re-Categorization of V.C. Summer Unit 1 Steam Generator Nozzle to Safe End Dissimilar Metal Weld Inspection Requirements)
- ML14316A208 + (Attachment 5 - Westinghouse WCAP-17651-NP, Revision 0, Palisades Nuclear Power Plant Reactor Vessel Equivalent Margins Analysis)
- ML091810623 + (Attachment 5 Affidavit of Richard A. Plasse, Jr)
- ML15286A365 + (Attachment 5 Case Oct 9 2015 NOV FPL DERM-5)
- ML16315A289 + (Attachment 5 EPRI RETRAN-3D Computer Code Manuals, NP-7450(A))
- RA-16-003, Attachment 5 EPRI RETRAN-3D Computer Code Manuals, NP-7450(A) + (Attachment 5 EPRI RETRAN-3D Computer Code Manuals, NP-7450(A))
- ML100740171 + (Attachment 5 Total Outside Tank Activity)
- ML18198A119 + (Attachment 5 to 18-233, ANP-3467NP, Rev. 0, North Anna Fuel-Vendor Independent Small Break LOCA Analysis Licensing Report)
- ML082520028 + (Attachment 5 to AEP-NRC-2008-17, ALION-REP-AEP-4459-03, Revision 0, Summary Report for Impact of Chemical Effects on Containment Sump Strainer Head Loss - D. C. Cook Units 1 and 2)
- ML100710753 + (Attachment 5 to DCL-10-028, Summary Statement of Diablo Canyon Power Plant PRA Model Capability for Use in TS 3.8.1 Completion Time Extension Submittal)
- DCL-13-016, Attachment 5 to DCL-13-016 - WCAP-17706-NP, Revision 0, Westinghouse Setpoint Methodology as Applied to the Diablo Canyon Power Plant + (Attachment 5 to DCL-13-016 - WCAP-17706-NP, Revision 0, Westinghouse Setpoint Methodology as Applied to the Diablo Canyon Power Plant)
- ML22242A293 + (Attachment 5 to Enclosure 1 - Criticality Safety Evaluation Report)
- ML22285A122 + (Attachment 5 to Enclosure 1: ANP-3947NP, Callaway Unit 1 License Amendment Request Inputs for Use of Framatome Fuel, Revision 3, Dated October 2022)
- ML13323A554 + (Attachment 5 to GNRO-2013/00088, EN-IC-S-022-G Rev. 0 Instrument Performance Monitoring and Drift Trending Analysis)
- ML13275A008 + (Attachment 5 to NRC Staffs Answer to Riverkeeper, Inc. Consolidated Motion for Leave to File Amended Contention RK-EC-8A, and Amended Contention RK-EC-8A)
- ML13099A019 + (Attachment 5 to SBK-L-13061, Holtec Non-Proprietary Licensing Report HI-2114996, Rev. 3, Licensing Report for Seabrook Spent Fuel Pool and New Fuel Vault Analyses)
- ML023040128 + (Attachment 5 to Safety Evaluation of Amendment of 149 - Table Lr - Less Restrictive - Relocated Details)
- ML110950125 + (Attachment 5 to W3F1-2011-0021, List of Regulatory Commitments)
- ML12181A346 + (Attachment 5 to W3F1-2012-0049, List of Regulatory Commitments)
- ML042440429 + (Attachment 5 to W3Fl-2004-0073, Additional Information Regarding EPU Spent Fuel Pool Cooling Analysis)
- ML13133A346 + (Attachment 5 to ZS-2013-0176 - Annual Report on the Meteorological Monitoring Program 2012)
- ML061370696 + (Attachment 5 to the NRC Staffs Answer to New England Coalitions Request for Leave to File New Contentions)
- ML18218A171 + (Attachment 5, ANP-3676NP, Revision 0, Surry Fuel-Vendor Independent Small Break LOCA Analysis, Licensing Report)
- DCL-14-051, Attachment 5, Areva Calculation No. 32-9221082-001 Diablo Canyon, Unit 2 Pressurizer Spray Nozzle Laminar Flaw Analysis - Non-Proprietary + (Attachment 5, Areva Calculation No. 32-9221082-001 Diablo Canyon, Unit 2 Pressurizer Spray Nozzle Laminar Flaw Analysis - Non-Proprietary)
- ML14120A041 + (Attachment 5, Byron Station, Units 1 and 2 - Calculation 19-AN-28, Revision 001B Calc. for Second-Level & Third-Level Undervoltage Relays)
- ML102170295 + (Attachment 5, Continuum Dynamics, Inc., CDI Report No. 10-12NP, Design and Stress Evaluation of Nine Mile Point Unit 2 Steam Dryer Modifications for EPU Operation)
- ML14164A064 + (Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76)
- ML14164A065 + (Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160)
- ML023050110 + (Attachment 5, Draft RAI, South Texas TS for Loss of Power Instrumentation)
- ML15351A360 + (Attachment 5, Final Integrated Plan)