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| 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| ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and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 | |
| ML18058B896 | 17 June 1993 | Svc Water Sys - Evaluation of Pipe Wall Thinning Down Stream of Valve CV-0826. | Consumers Energy Hoang P | |
| ML18058B897 | 22 June 1993 | Svc Water Sys - Evaluation of Pipe Wall Thinning Down Stream of Valve Mv SW 136. | Consumers Energy Hoang P | |
| ML18058B894 | 1 July 1993 | Forwards Request for Relief from ASME Code Requirements for 4-inch & 16-inch Svc Water Piping,Proposed Temporary non-code Repair Alternative to Codes IWA-4000 Repair & IWA-7000 Replacement Requirements & Supporting Calculations | Consumers Energy Slade G | Office of Information Resources Management |
| ML18059B126 | 31 December 1993 | 1993 Annual Rept of Facility Changes,Tests & Experiments. | Consumers Energy | |
| ML18066A465 | 17 May 1999 | Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl | Consumers Energy Haskell N | Office of Information Resources Management |
| ML043570017 | 14 December 2004 | from NMC Re Technical Evaluation of Proposed Method of Class 3 Pipe Leak Operability Determinations | Nuclear Management Co | NRC Region 3 |
| ML060300256 | 25 January 2006 | IR 05000255-05-012; on 10/01/2005 - 12/31/2005; Palisades Nuclear Plant; Operator Performance During Non-routine Evolutions and Events; Operability Evaluations | Christine Lipa NRC/RGN-III/DRP/RPB4 | Harden P Nuclear Management Co |
| PNP 2012-087, Proposed Alternative - Request for Relief from Immediate ASME Code Flaw Repair of Service Water System Manual Valve MV-SW136 | 30 October 2012 | Proposed Alternative - Request for Relief from Immediate ASME Code Flaw Repair of Service Water System Manual Valve MV-SW136 | Entergy Vitale A | Office of Nuclear Reactor Regulation Document Control Desk |
| PNP 2013-082, Relief Request Number 4-17, Proposed Alternative, Request for Relief from Immediate ASME Code Flaw Repair of Service Water System Manual Valve MV-SW135 | 3 December 2013 | Relief Request Number 4-17, Proposed Alternative, Request for Relief from Immediate ASME Code Flaw Repair of Service Water System Manual Valve MV-SW135 | Entergy Vitale A | Office of Nuclear Reactor Regulation Document Control Desk |
| ML16120A419 | 18 April 2016 | Final Safety Analysis Report Update, Revision 32, Chapter 6 - Engineered Safeguards Systems - References | Entergy | Office of Nuclear Reactor Regulation |
| CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 | 17 November 2017 | Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 | Entergy Halter M | Office of Nuclear Reactor Regulation Document Control Desk |
| ML21125A320 | 14 April 2021 | 5 to Updated Final Safety Analysis Report, Chapter 6, References | Entergy | Office of Nuclear Reactor Regulation |
| ML21125A292 | 14 April 2021 | 5 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safeguards Systems, Sections | Entergy | Office of Nuclear Reactor Regulation |
| ML23107A048 | 31 March 2023 | 6 to Updated Final Safety Analysis Report, Chapter 6, References | Holtec Decommissioning International | Office of Nuclear Reactor Regulation |
| ML23107A015 | 31 March 2023 | 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safeguards Systems | Holtec Decommissioning International | Office of Nuclear Reactor Regulation |