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- ML20128J299 + (Attachment 6: HI-STORM 100 FSAR Proposed Changed Pages)
- ML19289A615 + (Attachment 6: HI-STORM FW FSAR (Proposed Rev. 5.H), Changed Pages)
- ML22192A222 + (Attachment 6: HI-STORM FW FSAR Proposed Revision 10B, Changed Pages (non-proprietary))
- ML23006A270 + (Attachment 6: HI-STORM FW FSAR Proposed Revision 10G, Changed Pages (Non-Proprietary))
- ML21288A528 + (Attachment 6: HI-STORM FW FSAR Proposed Revision 10A, Changed Pages)
- ML20225A196 + (Attachment 6: HI-STORM FW FSAR Proposed Revision 7 Revised Pages (non-proprietary))
- ML24263A286 + (Attachment 6: HI-STORM Umax Amendment 5 Summary of Proposed Changes)
- ML20104C054 + (Attachment 6: Holtec International - Affidavit)
- ML25216A290 + (Attachment 6: Holtec International - Affidavit Pursuant to 10CFR2.390)
- ML22028A378 + (Attachment 6: Holtec International, HI-STORM 100 Amendment 16 Certificate of Compliance Reorganization Matrix)
- ML18213A536 + (Attachment 6: Larry Brand Expert Report)
- ML18213A535 + (Attachment 6: Larry Brand Expert Report Addendum)
- ML13095A470 + (Attachment 6: Letter (NL-13-047), Entergys Response to State of New York Department of States January 16, 2013 Letter (February 19, 2013))
- ML18270A327 + (Attachment 6: No Significant Hazards Consideration)
- ML12347A253 + (Attachment 6: Nttp 2.3 Seismic Peer Review Report Oconee Nuclear Station Units 1,2 and 3)
- ML22028A191 + (Attachment 6: Proposed Changes to CoC)
- ML15099A065 + (Attachment 6: Rev. 4 to Diablo Canyon Power Plant Units 1 & 2, Process Protection System (PPS) Replacement Conceptual Design Document)
- ML18152A932 + (Attachment 6: Second Level Undervoltage Time Delay Relays 162-153 and 162-154 Uncertainty Analysis)
- LR-N25-0074, Attachment 6: Site Specific Information in Support of Cobalt Absorber (Coba) Assemblies in Salem Generating Station, Units 1 and 2 + (Attachment 6: Site Specific Information in Support of Cobalt Absorber (Coba) Assemblies in Salem Generating Station, Units 1 and 2)
- ML18053A177 + (Attachment 6A - Quad Cities - Marked-up Emergency Plan EP-AA-1000 Pages)
- ML20343A197 + (Attachment 6A Technical Recommendations)
- ML18053A178 + (Attachment 6B - Quad Cities Clean Emergency Plan EP-AA-1000 Pages)
- ML23286A147 + (Attachment 7 - 00172-17-11-051-002 - One-Line Diagram ARC Main One-Line Diagram)
- ML14357A362 + (Attachment 7 - 1200-09-02 Rev. 0, Shine Target Solution Qualification Program)
- ML22152A232 + (Attachment 7 - Abnm Nuclear Medicine Certificate Effective 10/05/2012 to Present)
- ML19150A406 + (Attachment 7 - Affidavit (Non-Proprietary))
- ML20052D793 + (Attachment 7 - Affidavit Pursuant to 10CFR2.390 (Non-Proprietary))
- ML23348A309 + (Attachment 7 - Affidavit of Kimberly Manzione)
- ML22332A455 + (Attachment 7 - BWRVIP-135, Revision 4: BWR Vessel Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations (Non-Proprietary Version))
- ML063110190 + (Attachment 7 - Calculation No. H-1-CG-MDC-1795, Revision 4, Control Rod Drop Accident Radiological Consequences)
- ML15348A441 + (Attachment 7 - Cover Page of ENTR00689 WCAP-12191, Revision 5, Contains Westinghouse Designated Proprietary Information Subject to Nondisclosure Agreement Full Text Copyrighted)
- ML15072A388 + (Attachment 7 - EP-AA-1008, Revised Radiological Emergency Plan Annex Information for Limerick Generating Station)
- RA-15-019, Attachment 7 - EP-AA-1008, Revised Radiological Emergency Plan Annex Information for Limerick Generating Station + (Attachment 7 - EP-AA-1008, Revised Radiological Emergency Plan Annex Information for Limerick Generating Station)
- NMP1L3209, Attachment 7 - EP-AA-1014, Addendum 3, Revision 0, James A. FitzPatrick Nuclear Power Plant Emergency Action Levels + (Attachment 7 - EP-AA-1014, Addendum 3, Revision 0, James A. FitzPatrick Nuclear Power Plant Emergency Action Levels)
- ML100321324 + (Attachment 7 - GEH Nuclear Energy Affidavit Supporting Withholding)
- ML19037A301 + (Attachment 7 - HI-2177535 HI-STORE Emergency Response Plan Rev 3 - Non-Proprietary)
- ML22331A010 + (Attachment 7 - HI-2177597, HI-STORE CTF Thermal Evaluation)
- ML23013A345 + (Attachment 7 - HI-STORM 100 Amendment 16 Certificate of Compliance Appendix A-100U, Changed Pages (Non-Proprietary))
- ML23125A245 + (Attachment 7 - HI-STORM Umax FSAR Proposed FSAR Revision 4.1)
- ML22269A414 + (Attachment 7 - LaSalle County Station-Development of Evacuation Time Estimates)
- ML12030A267 + (Attachment 7 - NRC General Counsel Memorandum to the NRC Commissioners Dated January 10, 2012)
- ML22153A183 + (Attachment 7 - Non-Proprietary Version of SBLOCA Summary Report)
- ML22181B137 + (Attachment 7 - Proposed Operating License Changes (Mark-up))
- RS-14-042, Attachment 7 - UHS Calculation LSCS Design Analysis L-002457, Revision 8, Part 2 of 2 + (Attachment 7 - UHS Calculation LSCS Design Analysis L-002457, Revision 8, Part 2 of 2)
- ML14066A176 + (Attachment 7 - UHS Calculation LSCS Design Analysis L-002457, Revision 8, Part 1 of 2)
- RS-14-042, Attachment 7 - UHS Calculation LSCS Design Analysis L-002457, Revision 8, Part 1 of 2 + (Attachment 7 - UHS Calculation LSCS Design Analysis L-002457, Revision 8, Part 1 of 2)
- ML13254A121 + (Attachment 7 - Updated Evacuation Time Estimates for Oyster Creek Nuclear Generating Station Plume Exposure Pathway and ETE Review Criteria Checklist)
- ML021300491 + (Attachment 7 E-mailed on April 30, 2002 (Docket No. 50-298). E-mail from Mohan Thadani Re Draft RAI GL 96-06)
- ML061450154 + (Attachment 7 Request 4 - Level 1 and 2 Vibration Acceptance Criteria Support Documents)
- ML11326A069 + (Attachment 7 to DCL-11-072, PG&E Calculation No. 9000019634, Design Basis Dose Consequences and Recirculation Loop Margin Leakage Rates)
- ML22285A124 + (Attachment 7 to Enclosure 1: ANP-3943NP, Callaway Small Break LOCA Analysis with Gaia Fuel Design, Revision 1, Dated October 2022)