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List of results

• ML041340545  + (Assessment Followup Letter - Waterford 3 Steam Electric Station)
• ML113550536  + (Assessment Followup Letter - Waterford Steam Electric Station, Unit 3)
• ML081350089  + (Assessment Followup Letter 05-12-2008)
• ML081350054  + (Assessment Followup Letter 05-12-2008)
• ML081350163  + (Assessment Followup Letter 05/13/2008)
• ML082030625  + (Assessment Followup Letter 06-17-2008)
• ML073040131  + (Assessment Followup Letter 10/31/07)
• IR 05000390/2020005  + (Assessment Followup Letter and Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2020005 and 05000391/2020005)
• ML15316A073  + (Assessment Followup Letter for Sequoyah Nuclear Plant Unit 1)
• ML15049A132  + (Assessment Followup Letter for the Monticello Nuclear Generating Plant and Deviation from the Reactor Oversight Process Action Matrix)
• ML13018A163  + (Assessment Followup Letter for the Perry Nuclear Power Plant and Deviation from the Reactor Oversight Process Action Matrix)
• ML071370192  + (Assessment Followup Letter to Dominion Energy Kewaunee Power Station)
• ML083360755  + (Assessment Followup Letter-Grand Gulf Nuclear Station)
• ML053110528  + (Assessment Followup Letter-Waterford 3 Steam Electric Station)
• ML101250591  + (Assessment Followup Ltr. - Callaway Plant)
• ML101250558  + (Assessment Followup Ltr. - Wolf Creek Generating Station)
• ML022120139  + (Assessment Letter - Fermi 2 Changes to Previously Announced NRC Safeguards Inspection)
• ML021280166  + (Assessment Manual -ODAM - for Assesment of Gaseous & Liquid Effluents at Cooper Nuclear Station)
• ML111520190  + (Assessment Meeting - NRC Slides)
• ML041050066  + (Assessment Meeting Licensee Slides)
• ML081060281  + (Assessment Meeting Slides)
• ML040980601  + (Assessment Meeting, Reactor Oversight Program - CY2003)
• PMNS20220349, Assessment Meetingsurry Power Station Annual Assessment Meeting  + (Assessment Meetingsurry Power Station Annual Assessment Meeting)
• PMNS20230430, Assessment Meetingsurry Power Station Annual Assessment Meeting  + (Assessment Meetingsurry Power Station Annual Assessment Meeting)
• ML101050524  + (Assessment Mtg. - Tritium Facts)

• ML20262G982  + (Assessment Option 1 Proposed Methodology)

• ML18172A190  + (Assessment Plan - Enclosure 1)
• ML18172A191  + (Assessment Plan - Enclosure 2)
• ML18172A185  + (Assessment Plan Package for PRE-GI-018)
• ML18172A189  + (Assessment Plan for PRE-GI-018, Proposed Generic Issue on High Energy ARC Faults Involving Aluminum)
• ML23122A101  + (Assessment Presentation 2022)
• ML17180B430  + (Assessment Related to Reduced Seismic Criteria Methodolgy of Licensee Listed Plants)
• IR 05000285/1989020  + (Assessment Rept 50-285/89-20 on 890417-21 & 0502.Concerns Noted Re Util Steps to Institutionalize Aspects of Safety Enhancement Program.Overall Improvement Demonstrated)
• ML20094M717  + (Assessment Rept QA Program,Performed During Mar & Apr 1981)
• ML20203L245  + (Assessment Rept of Engineering & Technical Work Process Utilized at De&S Bolton Ofc)
• ML20214G494  + (Assessment Rept of Selected TMI-1 Training Programs)
• ML18038A246  + (Assessment Rept on Need for Leakage Control Sys for Nine Mile Point Unit 2)
• ML20050C780  + (Assessment Rept,Spent Fuel Storage Rack)
• IR 05000269/1991201  + (Assessment Repts 50-269/91-201,50-270/91-201 & 50-287/91-201 on 910715-19.Areas Assessed:Procurement & commercial-grade Dedication Programs)
• IR 05000275/1991201  + (Assessment Repts 50-275/91-201 & 50-323/91-201 on 910325-29. Major Areas Assessed:Procurement Program Development, Procedures Review & Program Interfaces)
• ML20213H005  + (Assessment Study of RELAP-5 MOD-2 Cycle 36.01:BASED on the DOEL-2 Steam Generator Tube Rupture Incident of June 1979)
• ML20096D650  + (Assessment Study of RELAP5/MOD2 Cycle 36.04 Based on the Commissioning Test Reactor Trip at Full Load at the Phillipsburg 2 Nuclear Power Plant)
• ML20095B955  + (Assessment Study of RELAP5/MOD2 Cycle 36.05 Based on the TIHANGE-2 Reactor Trip of January 11,1983)
• ML20094R016  + (Assessment Study of RELAP5/MOD2 Cycle 36.05 Based on the Doel 4 Reactor Trip of November 22, 1985)
• ML20056A545  + (Assessment Study of RELAP5/MOD2 Cycle 36.04 Based on Pressurizer Safety and Relief Valve Tests)
• ML20095H696  + (Assessment Study of RELAP5/MOD2 Cycle 36.04 Based on the DOEL-4 Manual Loss of Load Test of November 23, 1985)
• ML20248A520  + (Assessment Study of RELAP5/MOD2, Cycle 36.04 Based on Spray START-UP Test for DOEL-4)
• ML20045D560  + (Assessment and Application of Blackout Transients at Asco Nuclear Power Plant with RELAP5/MOD2)
• ML20237E274  + (Assessment and Recommendations for FISSILE-MATERIAL Packaging Exemptions and General Licenses within 10CFR Part 71)
• ML22061A242  + (Assessment of 10 CFR 50.72(b) Reporting Criteria)
• ML081960078  + (Assessment of 3-Month Response/Proposed Alternate Course of Action to GL 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (TAC MD7857, MD7858, & MD7859))