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List of results

• ML22287A143  + (Attachment 4 - Safety Analysis Report on the HI-STAR Atb 1T Non-Fuel Waste Transport System)
• ML20307A330  + (Attachment 4 - Standardized Radiological Emergency Plan Revision EP-AA-1004, Revision 39, Radiological Emergency Plan Annex for Dresden Station)
• ML14170A043  + (Attachment 4 - TRM Bases Developmental Revision D Changes (Mark-Up) for WBN Unit 2)
• ML12018A215  + (Attachment 4 - TVA Calculation EPM-LCP-072489, Cooling and Heating Load Analysis, Main Control Room HVAC, Revision 14 (Letter Item 4, Sser 23 Appendix Hh Item Number 108))
• ML061240264  + (Attachment 4 - Table L - Less Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues)
• ML021220067  + (Attachment 4 - Table L - Less Restrictive Changes North Anna, Units 1 and 2, Amendmends 231 and 212)
• ML042470019  + (Attachment 4 - Table of Where ANSI N18.7 Requirements Are Addressed by NQA-1-1994 Standards And/Or the New QA Topical Report)
• ML051360011  + (Attachment 4 - Tentative Meeting Topics for June 8-9, 2005, Public Meeting on NEI 04-01)
• RS-22-091, Attachment 4 - Transware Enterprises Inc. Affidavits  + (Attachment 4 - Transware Enterprises Inc. Affidavits)
• ML13254A118  + (Attachment 4 - Updated Evacuation Time Estimates for Dresden Nuclear Power Station Plume Exposure Pathway and ETE Review Criteria Checklist)
• ML14316A207  + (Attachment 4 - Westinghouse, WCAP-15353, Supplement 2-NP, Revision 0, Palisades Reactor Pressure Vessel Fluence Evaluation)
• ML20101N176  + (Attachment 4 Affidavit (Non-Proprietary))
• ML091810622  + (Attachment 4 Affidavit of Nathan E. Goodman)
• ML20247J599  + (Attachment 4 Basis and History)
• ML15286A367  + (Attachment 4 Case Oct 9 2015 AO Turkey Point Dec 23 2014ML15035A227)
• ML18213A533  + (Attachment 4 William Nuttle Expert Report)
• RS-14-039, Attachment 4 and 5 to RS-14-039, HI-2104790, Rev. 1, Nuclear Group Computer Code Benchmark Calculations, and HI-2125245, Rev. 4, Licensing Report for Quad Cities Criticality Analysis for Inserts-Non Proprietary Version  + (Attachment 4 and 5 to RS-14-039, HI-2104790, Rev. 1, Nuclear Group Computer Code Benchmark Calculations, and HI-2125245, Rev. 4, Licensing Report for Quad Cities Criticality Analysis for Inserts-Non Proprietary Version)
• ML023050002  + (Attachment 4 for 10/30/02, Meeting with NEI SGMP Responses to NRC RIS 2000-22 & NRC Lessons Learned Report on Indian Point 2 & Steam Generator Issues)
• ML090580620  + (Attachment 4 from Board Ordered the Staff to Update the Milestones Page on the Commissions Web Site Re Prairie Island License Renewal. Hearing File Index - Initial Disclosures)
• ML14330A250  + (Attachment 4 to 1CAN111401, ANP-3300, Revision 1, Pressure-Temperature Limits at 54 Efpy)
• ML100710751  + (Attachment 4 to DCL-10-028, History DCPP PRA Model Development and Update)
• ML12170A838  + (Attachment 4 to DCL-12-050, Scm 36-01, Rev. 0, Process Protection System (PPS) Replacement Software Configuration Management Plan (SCMP) Nuclear Safety Related)
• DCL-13-016, Attachment 4 to DCL-13-016, WCAP-17696-NP, Revision 0, Westinghouse Setpoint Calculations for the Diablo Canyon Power Plant Digital Replacement Process Protection System.  + (Attachment 4 to DCL-13-016, WCAP-17696-NP, Revision 0, Westinghouse Setpoint Calculations for the Diablo Canyon Power Plant Digital Replacement Process Protection System.)
• ML13267A133  + (Attachment 4 to DCL-13-016, WCAP-17696-NP, Revision 0, Westinghouse Setpoint Calculations for the Diablo Canyon Power Plant Digital Replacement Process Protection System)
• ML22118B015  + (Attachment 4 to Email Dated 4/14/22 from Sburns (Nwp) to Ngarcia Santos (NRC) Courtesy Review - Summary Combined Comments from Nwp on Draft Certificate of Compliance No. 9279, Revision 10)

• ULNRC-06723, Attachment 4 to Enclosure 1 - Holtec Affidavit for Withholding  + (Attachment 4 to Enclosure 1 - Holtec Affidavit for Withholding)

• ULNRC-06768, Attachment 4 to Enclosure 1: Framatome Affidavits for Withholding from Public Disclosure  + (Attachment 4 to Enclosure 1: Framatome Affidavits for Withholding from Public Disclosure)
• ML13323A553  + (Attachment 4 to GNRO-2013/00088, JC-Q1B21-N694-1 Rev. 1 Drywell High Pressure RCIC Isolation Setpoint Calculation)
• LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)  + (Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index))
• ML110050399  + (Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index))
• ML13275A016  + (Attachment 4 to NRC Staffs Answer to Riverkeeper, Inc. Consolidated Motion for Leave to File Amended Contention RK-EC-8A, and Amended Contention RK-EC-8A)
• ML13011A307  + (Attachment 4 to Opening Brief of Petitioner - Petition to Intervene and Request for Hearing by Friends of the Earth)
• ML18059B048  + (Attachment 4 to Procedure EM-09-13,Rev 1, ISI Pressure Testing Program Procedure)
• ML023040118  + (Attachment 4 to Safety Evaluation of Amendment No. 149 - Table L - Less Restrictive Changes)
• ML021400043  + (Attachment 4 to Supplement Dated May 10, 2002 to License Amendment Request Dated December 11, 2002 Conversion to Improved Technical Specifications (ITS))
• ML042440425  + (Attachment 4 to W3FI-2004-0073, Additional Information Regarding EPU Steam Generator Pressure - Low Setpoint Development)
• ML061370690  + (Attachment 4 to the NRC Staffs Answer to New England Coalitions Request for Leave to File New Contentions)
• ML20116A573  + (Attachment 4, Application of PRA to STP Improved Tss, Inadvertently Ommitted from Original Submittal)
• ML14171A238  + (Attachment 4, Areva Calculation No. 32-9221080-001 Diablo Canyon, Unit 2 Pressurizer Safety/Relief Nozzles Laminar/Planar Flaw Analysis - Non Proprietary)
• DCL-14-051, Attachment 4, Areva Calculation No. 32-9221080-001 Diablo Canyon, Unit 2 Pressurizer Safety/Relief Nozzles Laminar/Planar Flaw Analysis - Non Proprietary  + (Attachment 4, Areva Calculation No. 32-9221080-001 Diablo Canyon, Unit 2 Pressurizer Safety/Relief Nozzles Laminar/Planar Flaw Analysis - Non Proprietary)
• ML030590156  + (Attachment 4, Barrier Integrity Action Plan)
• ML14120A040  + (Attachment 4, Braidwood Station, Units 1 and 2 - Calculation 19-AN-29, Revision 002B, Second-Level Undervoltage Relay Setpoint)
• L-2003-222, Attachment 4, Calculation Note CN-CI-02-56 Rev. 00 Section XI Flaw Evaluation of Florida Power and Light Units 1& 2 Hot Leg Instrumentation Nozzles - J Weld  + (Attachment 4, Calculation Note CN-CI-02-56 Rev. 00 Section XI Flaw Evaluation of Florida Power and Light Units 1& 2 Hot Leg Instrumentation Nozzles - J Weld)
• RS-12-457, Attachment 4, Cameron International Corporation Affidavit Supporting Withholding of Information in Attachment 3 (Non-Proprietary)  + (Attachment 4, Cameron International Corporation Affidavit Supporting Withholding of Information in Attachment 3 (Non-Proprietary))
• ML061250124  + (Attachment 4, Diablo Canyon Power Plant Chemical Analysis Procedure, CAP A-8 Offsite Dose Calculation Procedure, Revision 29)
• ML14164A062  + (Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4A and 4B, Cover - Cl 3-73)
• ML14164A063  + (Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4B and 4C, Cl 3-74 - Cl 3-151)
• ML021770316  + (Attachment 4, E-Mail from South Texas Project Response ILRT Extension RAIs Dated May 22, 2002)
• ML021140089  + (Attachment 4, Faxed on March 25, 2002 (Docket No. 50-416). Draft Questions Re Grand Gulf Nuclear Station License Amendment Request Re Appendix K Measurement Uncertainty Recovery 1.7% Power Uprate)
• ML15160A612  + (Attachment 4, File No. 1400187.301, Revision 1, Finite Element Model Development and Thermal Mechanical Stress Analyses for the Unit 2 N1 Nozzle)
• ML20267A391  + (Attachment 4, Framatome Document No. 51-9292503-002, Palisades CEDM Nozzle Idtb Repair - Life Assessment Summary)