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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

• ML24311A222  + (Alternative Request to Extend Inservice Testing Interval for Essential Service Water Valves Fourth 10-Year Inservice Testing Program Interval)
• ML24344A274  + (Alternative Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case OMN-32)
• RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests  + (Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests)
• ML21049A024  + (Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves)
• ML20248H378  + (Alternative Requests RR 4-19 and RR-4-21 Related to the In-Service Testing Program (Epids L-2020-LLR-0077 and L-2020-LLR-0078))
• ML18252A003  + (Alternative Requests RR-04-27 and IR-3-38 for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography)
• ML19338G372  + (Alternative Requests RR-05-01 and RR-05-02 for the Fifth 10-Year Inservice Inspection Interval)
• ML18290A602  + (Alternative Requests Related to the Fifth and Fourth 10-Year Interval Pump, Valve, and Snubber Inservice Testing Programs, Respectively (EPID L-2018-LLR- 0012 Through EPID L-2018-LLR-0022))
• ML093570173  + (Alternative Requests for Fifth 10-Year Pump and Valve Inservice Testing Program-R.E. Ginna Nuclear Power Plant)
• ML080240322  + (Alternative Requests for Use of ASME Code Cases N-756 and N-757 Withdrawal of Code Case N-756)
• ML073170675  + (Alternative Requests for Use of ASME Code Cases N-756 and N-757 Request for Additional Information)
• ML072070354  + (Alternative Requests for Use of ASME Section III, Division 1, Code Cases N-756 and N-757)
• ML20121A193  + (Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves)
• ML21090A246  + (Alternative Requirements for ASME Section XI Examination Coverage of Weldolet Branch Connection Welds, Vogtle Electric Generating Plant, Units 3 and 4)
• ML21203A317  + (Alternative Requirements for ASME Section III Remediation of Containment Vessel Unistrut Welding)
• ML22118A072  + (Alternative Requirements for Inservice Test Interval Code Edition (VEGP-IST-ALT-01R2))
• ML12223A197  + (Alternative Requirements for Performing System Leakage Tests on the ASME Code Class 1 Piping and Component Segments)
• ML25016A030  + (Alternative Risk-Informed, Technology-Inclusive Approaches to Advanced Reactor Regulation (FW-B) White Paper Discussion Slides)
• RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information  + (Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information)
• ML19241A689  + (Alternative Shutdown Capability Conceptual Design Description)
• 05000244/FIN-2015008-01  + (Alternative Shutdown Procedure Deficiencies for Postulated Spurious Operations)
• ML20032C385  + (Alternative Site Study:Nrc Staff Testimony Related to Alternative Sites to Seabrook Units 1 and 2,PUBLIC Service Company of New Hampshire)
• ML19248C524  + (Alternative Sites Analysis,Reconnaissance Level Info for Following Ny Locations:Susquehanna River,Mohawk River Valley,Northern NY,mid-Hudson, & Lower Hudson)
• ML19318B553  + (Alternative Siting Requirements & Practices for Nuclear Power Plants, Prepared for Aif,Natl Environ Studies Project)
• ML113110084  + (Alternative Source Term Draft Request for Additional Information)

• NL-16-0388, Alternative Source Term License Amendment Request  + (Alternative Source Term License Amendment Request)

• ML033090251  + (Alternative Source Term Request for Additional Information)
• L-2007-085, Alternative Source Term and Conforming Amendment  + (Alternative Source Term and Conforming Amendment)
• ML062830385  + (Alternative Source Term- Proposed License Amendment)
• ML051890013  + (Alternative Testing of Containment Following Repairs to the Torus)
• ML15082A409  + (Alternative Use of Weld Overlay as Repair and Mitigation Technique)
• Information Notice 1989-13, Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites  + (Alternative Waste Management Procedures in Case of Denial of Access to Low-Level Waste Disposal Sites)
• ML100070480  + (Alternative Weld Repair Method for Reactor Vessel Head Relief Request Acceptance Review (ME2608))
• ML070600246  + (Alternative for Application of Pressurizer Nozzle Full - Structural Weld Overlays)
• ML070790240  + (Alternative for Application of Pressurizer Nozzle Full)
• ML18124A305  + (Alternative for ISI-09 Regarding Reactor Pressure Vessel Shell Welds Fourth Ten-Year Inservice Inspection Interval)
• ML23073A191  + (Alternative for Inservice Inspections of Pressurizer and Steam Generator Weld Examinations)
• ML19296A629  + (Alternative for Managing Wastes from Reactors & Post-Fission Operations in LWR Fuel Cycle, Vol 1 Re Alternatives for Back End of LWR Fuel Cycle Types & Properties of LWR Fuel Cycle Wastes)
• ML16326A044  + (Alternative for Pump and Valve Inservice Testing Program)
• ML16313A042  + (Alternative for Reactor Pressure Vessel Attachments B-N-2 and B-N-3 Weld Examinations)
• ML17090A168  + (Alternative to ASME Code Requirements for Weld Overlay Repair)
• ML081360646  + (Alternative to ASME Code, Section XI, Structural Weld Overlay of Pressurizer Surge Nozzle Weld, Alternative Request No. 2-RR-4-8, Revision 1)
• ML21069A064  + (Alternative to ASME Section XI Code Requirements to Defer Repair of Emergency Service Water System Socket Weld)
• NG-07-0176, Alternative to ASME Section XI Requirements to Use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energy Center  + (Alternative to ASME Section XI Requirements to Use Code Cases N-504-2 and N-638-1 for Weld Overlay Repairs at the Duane Arnold Energy Center)
• NG-10-0559, Alternative to ASME Section XI Requirements to Use Structural Weld Overlay Repairs as an Alternative Repair Technique at the Duane Arnold Energy Center  + (Alternative to ASME Section XI Requirements to Use Structural Weld Overlay Repairs as an Alternative Repair Technique at the Duane Arnold Energy Center)
• JPN-04-002, Alternative to Appendix Viii, Supplement 4 Requirements for Reactor Vessel Pressure Retaining Weld Inspection  + (Alternative to Appendix Viii, Supplement 4 Requirements for Reactor Vessel Pressure Retaining Weld Inspection)
• ML22227A068  + (Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves)
• ML19128A326  + (Alternative to Depth Sizing Qualification Examination of Welds)
• ML18192A104  + (Alternative to Examination of Reactor Pressure Vessel Flange Threads)
• ML16013A348  + (Alternative to Inservice Inspection)
• ML15104A192  + (Alternative to Inservice Inspection Regarding Reactor Closure Head Closure Head Nozzle and Partial Penetration Welds)