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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

• 05000327/FIN-2005011-01  + (Reliance on 20-foot Separation Zones for Fire Protection in Unit 1 480V Board Room 1B)
• 05000327/FIN-2005011-05  + (Reliance on Local Manual Operator Actions for Appendix R Fires)
• ML022800336  + (Reliant Energy, Leak Test Certificates Missing as Enclosures to Ltr Dtd 09/30/2002)
• ML063550348  + (Relicensing)
• ML11290A231  + (Relicensing - Indian Point Nuclear Generating Station F/NER/200900619)
• ML023380455  + (Relicensing Report for the Reactor Critical Facility at Rensselaer Polytechnic Institute)
• ML19196A064  + (Relied Request ISIR-4-10 Regarding Fourth Inservice Inspection Program Interval)
• ML12109A249  + (Relief (Alternative) Request 12 Concerning the Fourth 10-Year Inservice Testing Program)
• ML030700021  + (Relief ,Third 10-Year Interval Inservice Inspection Program Plan Relief RR-29 and RR-30 for Brunswick Units 1 & 2)
• ML020250222  + (Relief - Inservice Inspection Program Relief Request 2IR-13 (Tac No. MB1800))
• ML091240156  + (Relief 06-CN-003 for Use of Polyethylene Material in Buried Service Water Piping)
• ML082240386  + (Relief 06-CN-003, Use of Polyethylene Material in Nuclear Safety-Related Piping Applications)
• ML092570541  + (Relief 08-CN-001 Regarding Third 10-Year Interval Inservice Inspection)
• ML092530620  + (Relief 08-MN-005, for Control Rod Drive Mechanism (CRDM) Canopy Seal Welds)
• ML092300045  + (Relief 09-CN-002 Regarding Weld Buildup on Reactor Vessel Hot Leg Nozzles)
• ML110800426  + (Relief 09-MN-002, Revision 1, for a Proposed Alternative to Delay the Update to the Code of Record for the Fourth 10-Year Inservice Inspection (ISI) Interval)
• ML101580422  + (Relief 09-MN-005 for Alternative Leakage Testing for Various American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Class 1 Piping and Components During the Third 10-Year Inservice)
• ML100620018  + (Relief 09-MN-007 for Reactor Vessel Core Flood Nozzle Weld Examinations During the Third 10-Year Inservice Inspection)
• ML11187A001  + (Relief 10-CN-001, Alternative Requirements for Temporary Acceptance of a Through-Wall Flaw in Boric Acid Tank Nozzle Weld)
• ML110550770  + (Relief 10-MN-001 for a Proposed Alternative to to Delay the Update to the Code of Record During the Fourth 10-Year Inservice Inspection (ISI) Interval)
• ML11160A144  + (Relief 10-MN-002, Extension of Volumetric Inspection of Steam Generator Primary Manway Studs for One Operating Cycle Beyond the Third 10-Year Inservice Inspection Interval End Date)
• ML21293A096  + (Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46)
• ML030150218  + (Relief ASME Boiler & Pressure Vessel Code Concerning Inservice Inspection Program Reactor Pressure Vessel Examination)
• ML020720229  + (Relief Code, Relief Request for Alternate ASME Code, Section XI, Risk-Informed Inservice Inspection Program)
• ML060970124  + (Relief E-2, 4-th 10-year Pump and Valve Inservice Testing Program)

• ML033440009  + (Relief Inservice Testing Program Relief Request PR-3)

• ML070160009  + (Relief Letter 2007-01-08)
• ML18346A314  + (Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067))
• ML18122A152  + (Relief RR-RBS-ISI-015 from the Requirements of the ASME Code Regarding Reactor Vessel Weld Inspections)
• 3F0808-03, Relief Request 07-001-SS, Revision 1, Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on Three Areas 120 Degrees Apart on the Inside Surface..  + (Relief Request #07-001-SS, Revision 1, Alternate Examination Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on Three Areas 120 Degrees Apart on the Inside Surface..)
• EPID:L-2020-LRM-0005  + (Relief Request #1 for Four RHR Valves (E1150F006A/B/C/D))
• ML072760048  + (Relief Request (12R-49), Regarding Inservice Inspection Program Alternative Method)
• RA-19-0027, Relief Request (19-ON-002) Alternative to Extend Code Case N-770-2, Inspection Item B Examination Frequency  + (Relief Request (19-ON-002) Alternative to Extend Code Case N-770-2, Inspection Item B Examination Frequency)
• EPID:L-2019-LLR-0029  + (Relief Request (19-ON-002) Alternative to Extend Code Case N-770-2, Inspection Item B Examination Frequency)
• ML083570013  + (Relief Request (ISIR-26) Reactor Pressure Vessel Shell-to-Flange Weld Examination)
• ML040830703  + (Relief Request (PRR) No. 39, Alternative Contingency Repair Plan for Reactor Pressure Vessel Nozzle Safe-End and Dissimilar Metal Piping Welds Using ASME Code Cases N-638 and N-504-2 with Exceptions)
• ML092110684  + (Relief Request (PRR)-19, Jet Pump Instrumentation Nozzle Weld, RPV-N9A-1 Repair Plan - Change in Commitment Schedule to Submit Stress Analysis Report)
• ML091270162  + (Relief Request (PRR)-19, Jet Pump Instrumentation Nozzle Weld, RPV-N9A-1 Repair Plan)
• ML033240525  + (Relief Request (PRR)-29, Relief from System Hydrostatic Test Requirements for Small Bore (≪ 1-inch), ASME Code Class 1 Reactor Coolant Pressure Boundary (RCPB) Vent, Drain and Branch (Vtdb) Lines and Connections)
• ML030650597  + (Relief Request (PRR)-30, Relief from ASME Code, Section XI, Appendix Viii, Supplement 10, Performance Demonstration for Ultrasonic Examination Systems.)
• ML031260438  + (Relief Request (PRR)-31- Alternative Contingency Repair Plan for Generic Letter 88-01, Reactor Pressure Vessel Nozzle-to-Safe-End Welds, Using ASME Code Cases N-638, 2142-1, 2143-1, & N-504-1)
• ML032870331  + (Relief Request (PRR)-36, Alternative Contingency Repair Plan for Generic Letter 88-01, Reactor Pressure Vessel Nozzle-to-End Cap Weld, Using ASME Code Cases N-638 and N-504-2 with Exceptions)
• ML032940103  + (Relief Request (PRR)-36, Alternative Contingency Repair Plan for Generic Letter 88-01, Reactor Pressure Vessel Nozzle-to-End Cap Weld, Using ASME Code Cases N-638 and N-504-2 with Exceptions - Revision 1)
• ML032870323  + (Relief Request (PRR)-38 - Relief from ASME Code, Section XI, Appendix Viii, Supplement 11, Qualification Requirements for Full Structural Overlaid Wrought Austenitic Piping Welds)
• ML092370549  + (Relief Request (PRR)19, Install a Weld Overlay on Jet Pump Instrumentation Nozzle Weld RPV-N9A-1- Pilgrim Nuclear Power Station)
• RA-23-0018, Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1  + (Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1)
• ML23285A074  + (Relief Request (RA-23-0018) to Utilize Code Case N-853 with Deviations)
• ML24233A308  + (Relief Request (RA-24-0152) to Utilize a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI)
• ML050250215  + (Relief Request (RR) 02-003 Request for Additional Information)
• ML042160288  + (Relief Request (RR) 03-001)
• ML042720426  + (Relief Request (RR) 03-002, Request for Additional Information - Response)