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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

• ML20246E463  + (Lessons Learned from the Special Inspection Program for Emergency Operating Procedures.Conducted March-October 1988)
• ML20125D296  + (Lessons Learned from the Special Inspection Program for Emergency Operating Procedures.Conducted October 1988 - September 1991)
• ML25241A297  + (Lessons Learned from the Standard Design Approval Review of the NuScale Power, LLC, US460 Design)
• ML20072N710  + (Lessons Learned from the Three Mile ISLAND-UNIT 2 Advisory Panel)
• ML24047A185  + (Lessons Learned from the U.S. NRC Staffs Review of Framatome Topical Report, ANP-10339P, Arita - Artemis/Relap Integrated Transient Analysis Methodology)
• ML24116A202  + (Lessons Learned in Applying Systems-Theoretic Process Analysis (Stpa) to a Nuclear Facility Case Study Presentation at 2024 INL Digital Engineering Conference)
• ML20042D544  + (Lessons Learned in Process Control at the Halden Reactor Project)
• ML17353A035  + (Lessons Learned to Be Communicated to Applicants to Optimize License Renewal Application Reviews)
• ML073190162  + (Lessons Learned to Improve Inspections, Tests, Analyses, and Acceptance Criteria Submittal)
• Information Notice 2025-01, Lessons Learned with Implementing ASME Code Case N-752  + (Lessons Learned with Implementing ASME Code Case N-752)
• ML090960436  + (Lessons from Regulatory Audits of the Pilot Plants That Are Transitioning to a Fire Protection Licensing Basis Based on the National Fire Protection Association (NFPA) Standard NFPA 805 as Allowed by 10 CFR 5.48 (C))
• RIS 2008-19, Lessons-Learned from Recent 10 CFR Part 70 License-Transfer Application Reviews  + (Lessons-Learned from Recent 10 CFR Part 70 License-Transfer Application Reviews)
• ML25027A297  + (Lessons-Learned from the First Use of Regulatory Guide 4.26 in the Assessment of Volcanic Hazards at a Proposed Nuclear Power Reactor Site.Msg)
• ML22320A029  + (Lester Estelle)
• ML20262K262  + (Letdown & Regenerative Heat Exchanger Piping - Sections. Sheet 2 of 2.No Revision Date)
• ML20260F061  + (Letdown Chiller HX Temp Control Valve Logic Diagram SYSTEM-CV. Actual Drawing NUMBER:6R-17-9-Z-42419 1)
• ML20261M419  + (Letdown Chiller HX Temp Control Valve Logic Diagram System: Cv)
• ML20260E454  + (Letdown HX CCW Valve Logic Diagram System:Cc. Actual Drawing NUMBER:6R-20-9-Z-42060 1)
• ML20261L785  + (Letdown HX CCW Valve Logic Diagram System:Cc)
• ML20260F164  + (Letdown HX Outlet Control Logic Diagram System:Cv. Actual Drawing NUMBER:6R-17-9-Z-42445 1)
• ML20261M346  + (Letdown HX Outlet Control Logic Diagrm System:Cv)
• ML20265A591  + (Letdown Heat Exchanger)
• ML20260F011  + (Letdown Isolation Valves Logic Diagram System:Cv. Actual Drawing NUMBER:5R-17-9-Z-42410 1)
• ML20265D491  + (Letdown Isolation Valves Logic Diagram System:Cv)
• ML20261M447  + (Letdown Isolation Valves Logic Diagram System:Cv)

• ML20260F191  + (Letdown Orifice Isolation Valves (Aovs) Logic Diagram System:Cv)

• ML20260F016  + (Letdown Orifice Isolation Valves Logic Diagram System:Cv. Actual Drawing NUMBER:5R-17-9-Z-42411 1)
• ML20265D496  + (Letdown Orifice Isolation Valves Logic Diagram System:Cv)
• ML20261M444  + (Letdown Orifice Isolation Valves Logic Diagram System:Cv)
• ML20260F154  + (Letdown Pressure Control Valve Logic Diagram System:Cv. Actual Drawing NUMBER:6R-17-9-Z-42442 1)
• ML20261M337  + (Letdown Pressure Control Valve Logic Diagram System:Cv)
• ML20260F066  + (Letdown Reheat HX Temp Control Valves Logic Diagram System:Cv. Actual Drawing NUMBER:6R-17-9-Z-42420 1)
• ML20261M423  + (Letdown Reheat HX Temp Control Valves Logic Diagram System: Cv)
• ML20260F003  + (Letdown Stop Valves Logic Diagram System:Cv. Actual Drawing NUMBER:5R-17-9-Z-42408 1)
• ML20265D480  + (Letdown Stop Valves Logic Diagram System:Cv)
• ML20261M454  + (Letdown Stop Valves Logic Diagram System:Cv)
• 05000413/FIN-2007007-06  + (Letdown Valve 2NV015B)
• ML20260F110  + (Letdown Valve to VCT or Hold Up Tank Logic Diagram System: Cv. Actual Drawing NUMBER:6R-17-9-Z-42434 1)
• ML20261M304  + (Letdown Valve to VCT or Hold Up Tank Logic Diagram System: Cv)
• ML20265D548  + (Letdown Valve to Vct or Hold Up Tank Logic Diagram System: Cv)
• ML20261C400  + (Letdown and Regenerative Heat Exchanger Piping, as-built)
• ML20260F117  + (Letdown to Demineralizers Diversion Valve Logic Diagram System:Cv. Actual Drawing NUMBER:6R-17-9-Z-42435 1)
• ML20265D552  + (Letdown to Demineralizers Diversion Valve Logic Diagram System:Cv)
• ML20261M307  + (Letdown to Demineralizers Diversion Valve Logic Diagram System:Cv)
• ML20080U416  + (Lets Do Business with NRC)
• ML20101K034  + (Lets Do Business with NRC)
• ML24303A099  + (Lett to R. Carter, Principal Chief Request to Initiate Section 106 Consultation for SLR of DNP Station)
• ML071560348  + (Letter & Encl. 1- Hope Creek Generating Station - Request for Additional Information Regarding Request for Extended Power Uprate)
• ML070730037  + (Letter & License Pgs - Issuance of Amendment Nos. 136 & 136 - Changes to TSs Re Control Room Envelope Habitability in Accordance w/TSTF-448, Rev. 3, Using Consolidated Line Item Improvement Process)
• ML100070715  + (Letter & Notice -Environmental Assessment and Finding of No Significant Impact)
• ML20009D235  + (Letter & SER Crystal River Unit 3 Nuclear Generating Plant - Corrected Safety Evaluation for Approval of Partial Site Release for Facility Operating License No. DPR-72)