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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML19337B631  + (Primary Reactor Containment Integrated Leakage Rate Test Rept)
• ML20054B521  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20044H192  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20064N424  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20066G525  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20101U376  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20100G057  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20117E004  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20112F768  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20125D094  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20151N300  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20247E827  + (Primary Reactor Containment Integrated Leakage Rate Test, Final Rept)
• ML20245G894  + (Primary Reactor Containment Integrated Leakage Rate Test,Final Rept)
• ML20002B672  + (Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors, 10CFR50 Final Rule.Amend Permits Greater Flexibility for Leak Testing in Case of Frequent Air Lock Use)
• ML20088A519  + (Primary Reactor Containment Structural Integrity Test & Integrated Leakage Rate Test, Jan 1984 Final Rept)
• ML20054B505  + (Primary Reactor Containment Structural Integrity Test, Final Rept)
• ML20266C449  + (Primary Sampling Sys Ps.Sheet A01)
• ML20266C445  + (Primary Sampling Sys Ps.Sheet A01)
• ML20266D916  + (Primary Sampling System Flow Diagram, as-built.Sheet 1 of 1)
• ML20260D481  + (Primary Sampling System RHR Sample Select Valves Logic Diagram System:Ps. Actual Drawing NUMBER:5Z-32-9-Z-41514 1)
• ML20260D486  + (Primary Sampling System RHR Smpl Containment Isolation Valve Logic Diagram System:Ps. Actual Drawing NUMBER:5Z-32-9-Z-41515 1)
• ML20260D499  + (Primary Sampling System Rc Smpl Containment Isolation Valves Logic Diagram System:Ps. Actual Drawing NUMBER:5Z-32-9-Z-41518 1)
• ML20260D496  + (Primary Sampling System SI Acc Smpl Cntmt Isol Valve Logic Diagram System:Ps. Actual Drawing NUMBER:5Z-32-9-Z-41517 1)
• ML20261D486  + (Primary Service Water System)
• ML20261D483  + (Primary Service Water System)

• ML20266C057  + (Primary Steam)

• ML19241B222  + (Primary Sys Cooldown charts,790413-25)
• ML19256F853  + (Primary Sys Perturbations Induced by Once-Through Steam Generators. Feedwater Transient Summary Encl)
• ML20209G689  + (Primary Sys Release Due to Pressurizer Degas Relief Valve Lifting, Technical Review Rept.No Further Action Necessary at Present)
• ML20261J989  + (Primary System Control Transmitter:Midland Public Warning System Control Equipment Installation. Sheet 2)
• ML20070C103  + (Primary System Fission Product Release and Transport.A State-Of-The-Art Report to the Committee on the Safety of Nuclear Installations)
• ML18348A756  + (Primary System Pressure Increase to 2, 100 Psia)
• Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600  + (Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600)
• ML19219A182  + (Primary Water Stress Corrosion Cracking Initiation Testing of Alloys 600/182 and Alloys 690/152/52 - 2019 Progress Report)
• RIS 2008-25, Primary Water Stress Corrosion Cracking of Dissimilar Metal Butt Welds in Pressurized Water Reactor Primary Coolant System Piping Welds  + (Primary Water Stress Corrosion Cracking of Dissimilar Metal Butt Welds in Pressurized Water Reactor Primary Coolant System Piping Welds)
• Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600  + (Primary Water Stress Corrosion Cracking of Inconel 600)
• ML14052A382  + (Primary Water System (System 081) Transition from ASME Section III to ASME Section XI)
• 05000416/LER-2020-005-01, Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram  + (Primary Water System Flow Lowered Causing Turbine Trip and Subsequent Reactor Scram)
• 05000416/LER-2020-006-02, Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram  + (Primary Water Tank Low Level Causing Turbine Trip and Subsequent Reactor Scram)
• ENS 48378  + (Primary and Backup Meteorological Towers Out of Service)
• ENS 51223  + (Primary and Backup Meteorological Towers to Be Removed from Service for Upgrade)
• ENS 51669  + (Primary-Secondary Containment Pressure Differential Exceeded Due to Ccp Exhaust Fan Trip)
• ML19310H422  + (Prime Health Services - Monroe, LLC 13-32773-01)
• IR 015000035/2023002  + (Prime Inspections, Inc - NRC Form 591M, Inspection Report 150-00035/2023-002)
• ML18199A584  + (Prime NDT Services, Inc. - NRC Inspection 03020982/2018001 and Notice of Violation)
• ML18269A093  + (Prime NDT Services, Inc. - NRC Inspection No. 03020982/2018001)
• ML18269A231  + (Prime NDT Services, Inc. Telephone Record with S. Courtemanche Re Reply Letter Dated 08/29/2018 to EA-18-082)
• IR 07200202/2010001  + (Princeton Community Hospital, NRC Form 591M Part 1, Inspection Report 03010772/2021001)
• ML21118A067  + (Princeton Community Hospital, NRC Form 591M Part 1, Inspection Report 03010772/2021001)
• IR 07200201/1980001  + (Princeton Community Hospital, NRC Form 591M Part 1, Inspection Report 03010772/2018001)
• ML24078A276  + (Princeton Community Hospital; NRC Form 591M Part 1, Inspection Report 03010772/2023001)