Semantic search
Jump to navigation
Jump to search
| Issue date | Title | From | To | |
|---|---|---|---|---|
| NRC Generic Letter 1990-05 | 15 June 1990 | NRC Generic Letter 1990-005: Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping | Partlow J Office of Nuclear Reactor Regulation | |
| ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability | Partlow J Office of Nuclear Reactor Regulation | |
| ML20086G289 | 27 November 1991 | Requests Relief from ASME Code Requirements to Permit Use of Temporary non-code Repair on Class 3 Piping,Per Requirements of Generic Ltr 90-05.On 911124,leak Discovered on 30-inch Diameter concrete-lined Pipe in Unit 1 | Exelon Creel G | Office of Information Resources Management |
| ML20092E013 | 11 September 1995 | Submits Supplemental Info Re Request for Temporary Relief from ASME Boiler & Pressure Vessel Code Section XI Requirement IAW-5250 | Exelon Denton R | Office of Information Resources Management |
| ML20133B013 | 19 December 1996 | Requests Temporary Relief from ASME Boiler & Pressure Vessel Code Section XI Requirement IWA-5250,to Delay Repair of Weld on Safety Injection Recirculation Piping Until Next Outage of Sufficient Duration | Exelon Cruse C | Office of Information Resources Management |
| ML20134G529 | 7 February 1997 | Safety Evaluation Re Request Relief from ASME Code Requirement for Calvert Cliffs Nuclear Power Plant,Unit 1 | NRC (Affiliation Not Assigned) | |
| ML20248B734 | 27 May 1998 | Rev 1 to ES199800777, Engineering Evaluation | Exelon | |
| ML20248B725 | 27 May 1998 | Requests Temporary Relief from ASME Boiler & Pressure Vessel Code Section XI Requirement IAW-5250,as Allowed by 10CFR50.55a(a)(3) | Exelon Cruse C | Office of Information Resources Management |
| ML13346A630 | 8 November 2013 | Calculation M-93-038, Impact of Pipe Clamp on Calvert Cliffs Nuclear Power Plant Component Cooling Water Piping Stress | Calvert Cliffs Morgan M | Office of Nuclear Reactor Regulation |
| RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 24 September 2014 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | Exelon James Barstow | Office of Nuclear Reactor Regulation Document Control Desk |
| RS-16-041, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1. | 28 January 2016 | Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1. | Exelon David Gudger | Office of Nuclear Reactor Regulation Document Control Desk |
| RA-16-059, Proposed Alternative to Utilize Code Case N5134, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | 14 June 2016 | Proposed Alternative to Utilize Code Case N5134, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 | Exelon James Barstow | Office of Nuclear Reactor Regulation Document Control Desk |
| ML18354A431 | 19 December 2018 | Submittal of Relief Requests Associated with the Fifth Lnservice Inspection (ISI) Interval | Exelon James Barstow | Office of Nuclear Reactor Regulation Document Control Desk |