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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
- EPID:L-2017-DTP-0006 + (Regulatory Audit Plan Regarding Zionsolutions Response to Request for Additional Information Related to Partial Site Release and Recent Site Survey Activities)
- EPID:L-2024-LNE-0003 + (Regulatory Path to Reauthorize Power Operations)
- 10 CFR 76.60, Regulatory Requirements Which Apply + (Regulatory requirements which apply)
- Rei-Mei Shieh + (Rei-Mei Shieh)
- Reinaldo Picon-Colon + (Reinaldo Picon-Colon)
- Reinaldo Rodriguez + (Reinaldo Rodriguez)
- 10 CFR 25.29 + (Reinstatement of access authorization)
- 10 CFR 52.13, Relationship to Other Subparts + (Relationship to other subparts)
- 10 CFR 52.43, Relationship to Other Subparts + (Relationship to other subparts)
- 10 CFR 52.73, Relationship to Other Subparts + (Relationship to other subparts)
- 10 CFR 52.133, Relationship to Other Subparts + (Relationship to other subparts)
- 10 CFR 52.153, Relationship to Other Subparts + (Relationship to other subparts)
- NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements + (Relaxation in Arbitrary Intermediate Pipe Rupture Requirements)
- TSTF-237 + (Relaxation of Reactor Coolant Pump Flywheel Examinations)
- NRC Generic Letter 90-03, Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components" + (Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2, "Vendor Interface for Safety-Related Components")
- TSTF-334 + (Relaxed Surveillance Frequency for Excess Flow Check Valve Testing)
- CAC:MF8938 + (Relaxed Surveillance Frequency for Excess Flow Check Valve Testing)
- MD 3.4, Release of Information to the Public + (Release of Information to the Public)
- 10 CFR 35.75, Release of Individuals Containing Unsealed Byproduct Material Or Implants Containing Byproduct Material + (Release of individuals containing unsealed byproduct material or implants containing byproduct material)
- 10 CFR 50.83, Release of Part of a Power Reactor Facility Or Site for Unrestricted Use + (Release of part of a power reactor facility or site for unrestricted use)
- NRC Generic Letter 77-07, Reliability Of Standby Diesel Generator Units + (Reliability Of Standby Diesel Generator Units)
- NRC Generic Letter 79-17, Reliability of Onsite Diesel Generators at Light Water Reactors + (Reliability of Onsite Diesel Generators at Light Water Reactors)
- Reliable Testing Services + (Reliable Testing Services)
- Reliance Electric + (Reliance Electric)
- Relief Request + (Relief Request)
- EPID:L-2020-LRM-0005 + (Relief Request #1 for Four RHR Valves (E1150F006A/B/C/D))
- EPID:L-2019-LLR-0029 + (Relief Request (19-ON-002) Alternative to Extend Code Case N-770-2, Inspection Item B Examination Frequency)
- EPID:L-2024-LLR-0052 + (Relief Request (RR) 14. Limited Coverage Exams Due to Impractical Inservice Inspection Requirements - Fourth Ten-Year Inservice Inspection Program Interval)
- EPID:L-2024-LLR-0004 + (Relief Request (RR) 7, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) Extension of Inspection Interval for Reactor Pressure Vessel Welds from 10 to 20 Years)
- EPID:L-2019-LLR-0007 + (Relief Request 14-RS-1 to Implement Code Case OMN-13)
- EPID:L-2018-LLR-0127 + (Relief Request 14R-OB, Revision 1, Associated with Pressure Testing of Containment Atmospheric Control Penetration Piping)
- EPID:L-2020-LLR-0055 + (Relief Request 3IIR-7, Proposed Alternative to Deter Examinations Beyond the 1 Year Code Allowable)
- EPID:L-2024-LLR-0019 + (Relief Request 4A-01- Request for an Alternative to the Requirements of the ASME Code for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld)
- EPID:L-2023-LLR-0022 + (Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2))
- EPID:L-2020-LLR-0152 + (Relief Request 4RR-02, Revision 1 (PLA-7895))
- EPID:L-2023-LLR-0014 + (Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061)
- EPID:L-2024-LLR-0028 + (Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112)
- EPID:L-2018-LLR-0028 + (Relief Request 58 - Unit 2 Impractical Examinations for the Third 10-Year Inservice Inspection Interval)
- EPID:L-2018-LLR-0120 + (Relief Request 62 - Third and Fourth 10-Year Inservice Inspection (ISI) Intervals, Proposed Alternative - Pressurizer Heater Sleeve Repairs)
- EPID:L-2019-LLR-0068 + (Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval)
- EPID:L-2022-LRM-0008 + (Relief Request 67 - Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection)
- EPID:L-2022-LLR-0011 + (Relief Request 69, Unit 2, Extension Request for Relief from Containment Tendon Inspections)
- EPID:L-2024-LLR-0080 + (Relief Request 73 - Proposed Alternative for Pressurizer Lower Shell Temperature Nozzle Life of Repair)
- EPID:L-2021-LLR-0082 + (Relief Request ANO2-R&R-012: Support the Repair of the Reactor Vessel Closure Head Penetration 46)
- EPID:L-2021-LLR-0084 + (Relief Request ANO2-RR-21-002, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46)
- EPID:L-2018-LLR-0130 + (Relief Request Alternative Requirements for the Repair and Examination of Reactor Vessel Head Penetrations for the Fourth Inservice Inspection Interval)
- EPID:L-2021-LLR-0066 + (Relief Request Associated with Excess Flow Check Valves)
- EPID:L-2023-LLR-0046 + (Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations)
- EPID:L-2019-LLR-0081 + (Relief Request Associated with the Third Ten-Year Lnservice Inspection Program Interval)
- EPID:L-2019-LLR-0011 + (Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds)
- EPID:L-2024-LLR-0031 + (Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds)