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List of results

• 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)
• ML093160585  + (Attachment 7 to Enclosure, Calculation GEN-PI-077, Rev. 0, FHA Analysis Titled, Fuel Handling Accident Dose Analysis - Ast)
• ML12157A180  + (Attachment 7 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment J Labeled GGNS Stormwater Permits)
• ML13275A014  + (Attachment 7 to NRC Staffs Answer to Riverkeeper, Inc. Consolidated Motion for Leave to File Amended Contention RK-EC-8A, and Amended Contention RK-EC-8A)
• ML023040151  + (Attachment 7 to Safety Evaluation of Amendment No. 149 - Table U - Unused Numbers)
• ML063460121  + (Attachment 7, Amergen Response to the Request for Additional Information Regarding the Oyster Creek Generating Station EAL Revision, EP-OC-1010)
• ML093080159  + (Attachment 7, Browns Ferry Unit 1 - Technical Specification Change 467, ANP-2833NP, Revision 0, Mechanical Design Report, Reload BFE1-9 ATRIUM-10 Fuel Assemblies)
• ML102710228  + (Attachment 7, CR-3 Work Request Form Nu 0368426 (Note: Some Information in This Record Was Received by the NRC with Information Already Removed))
• ML023050119  + (Attachment 7, Cooper Nuclear Station, Updated Version of Draft Response to RAIs (MSIV Leakage Path))
• ML021140040  + (Attachment 7, Faxed on March 26, 2002, (Docket Nos. 50-313 and 50-368). Moderate Susceptibility Plants)
• ML052570067  + (Attachment 7, Meeting Summary, Ventilation Systems Amendment)
• L-2010-078, Attachment 7, St. Lucie License Amendment Request Extended Power Uprate, Summary of Regulatory Commitments  + (Attachment 7, St. Lucie License Amendment Request Extended Power Uprate, Summary of Regulatory Commitments)
• ML101160207  + (Attachment 7, St. Lucie License Amendment Request Extended Power Uprate, Summary of Regulatory Commitments)
• ML051230038  + (Attachment 7, Steam Dryer Vibration Measurement, Test Specification, GE Report 26A6388, Revision 3, April 20, 2005)
• ML030660369  + (Attachment 7, Transcript)
• ML11257A050  + (Attachment 7, WCAP-17427-NP, Rev. 1, Watts Bar Nuclear Plant Unit 2 Common Q Post Accident Monitoring System Computer Security Assessment, Attachment 8, Application for Withholding Proprietary Information from Public Disclosure and Attachme)
• ML11207A444  + (Attachment 7- Crystal River Unit 3 Extended Power Uprate Technical Report)