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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 | |
IR 05000327/1990035 | 30 October 1990 | Insp Repts 50-327/90-35 & 50-328/90-35 on 901016-19. Noncited Violations Noted.Areas Inspected:Isi Work | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) Blake J Coley J | |
ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and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 | |
ML20091Q866 | 31 January 1992 | Comment Opposing Draft NUREG-1022,Rev 1, Event Reporting Sys,10CFR50.72 & 50.73,Clarification of NRC Sys & Guidelines for Reporting | Duke Energy Tennessee Valley Authority Energy Northwest Rochester Gas and Electric PSEG Niagara Mohawk Reynolds N WINSTON & STRAWN TEXAS UTILITIES CO. Northeast Nuclear Energy | NRC OFFICE OF ADMINISTRATION (ADM) Meyer D |
ML20099E772 | 6 August 1992 | Forwards Temporary Request for Relief from ASME Code Requirements to Repair Class 3 Piping Leak on ERCW Sys.Util structural-integrity Evaluation Indicated That Flaw Satisfied Criteria of through-wall Flaw in GL 90-05 | Tennessee Valley Authority Joshua Wilson | Office of Information Resources Management |
ML20126D086 | 18 December 1992 | Forwards Request for Temporary Relief from ASME Code for Class 3 Piping Leak on Essential Raw Cooling Water Sys, Containment Spray Pump 1B-B Room Cooler.Relief Needed to Repair pin-hole Leak in Section of Discharge Piping | Tennessee Valley Authority Fenech R | Office of Information Resources Management |
ML20087D212 | 7 August 1995 | Forwards Request for Relief to Make Temporary Noncode Repair on Section of ASME Code Class 3 Piping within Facility ERCW Sys | Tennessee Valley Authority Shell R | Office of Information Resources Management |
ML20094D843 | 3 November 1995 | Submits Addl Info for Request for Relief from ASME Code for Replacement of Code Class 3 Piping | Tennessee Valley Authority Shell R | Office of Information Resources Management |
ML20101N014 | 3 April 1996 | Forwards Info Associated W/Analysis Performed for Canopy Seal Weld Repair on Facility During Cycle 7 Refueling Outage,As Requested During Telcon W/Nrc | Tennessee Valley Authority Shell R | Office of Information Resources Management |
ML20107M007 | 23 April 1996 | Forwards Request for Relief from ASME Code for Replacement of ASME Code Class 3 Piping.Tva Will Replace Piping Prior to start-up from Unit 1 Cycle 8 Refueling Outage & Perform Quarterly Exams to Ensure No Further Pipe Degradations | Tennessee Valley Authority Shell R | Office of Information Resources Management |
ML20129D266 | 18 October 1996 | Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units | Tennessee Valley Authority | |
ML20202A714 | 20 January 1999 | Provides Request for Relief for Delaying Repair on Section of ASME Code Class 3 Piping within Essential Raw Cooling Water Sys | Tennessee Valley Authority Salas P | Office of Information Resources Management |
ML20217F970 | 14 October 1999 | Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections | Tennessee Valley Authority | |
ML021020324 | 29 March 2002 | Unit 1 - Technical Specification (TS) Change No. 02-02, Steam Generator (SG) Alternate Repair Criteria (ARC) Deletion & SG Inspection Interval Revision | Tennessee Valley Authority Salas P | Office of Nuclear Reactor Regulation Document Control Desk |
ML022960514 | 10 October 2002 | Unit 1 - Technical Specification (TS) Change No. 02-02, Steam Generator (SG) Alternate Repair Criteria (ARC) Deletion and SG Inspection Interval Revision - Partial Withdrawal | Tennessee Valley Authority Salas P | Office of Nuclear Reactor Regulation Document Control Desk |
ML031750593 | 14 June 2003 | Request for Relief from American Society of Mechanical Engineers (ASME) Code for Replacement of ASME Code Class 3 Piping | Tennessee Valley Authority Salas P | Office of Nuclear Reactor Regulation Document Control Desk |
ML032300001 | 18 August 2003 | Relief, Essential Raw Cooling Water Flow Repair (Tac No. MB9643) | Howe A NRC/NRR/DLPM/LPD2 | Tennessee Valley Authority Scalice J |
ML033320222 | 25 November 2003 | Boiler and Pressure Vessel Code, Code Case N-513 - Evaluation Criteria for Temporary Acceptance of Flows | Tennessee Valley Authority Burzynski M | Office of Nuclear Reactor Regulation Document Control Desk |
ML042150438 | 6 October 2004 | Relief, Relief Request Re. Maximum Allowable Flaw Width When Planar Flaw Evaluation Rules May Be Applied | Marshall M NRC/NRR/DLPM/LPD2 | Tennessee Valley Authority Singer K |
ML043490647 | 2 December 2004 | Unit 2 - Technical Specifications Change 03-06 - Change Inspection Scope for Steam Generator Tubes | Tennessee Valley Authority Pace P | Office of Nuclear Reactor Regulation Document Control Desk |
ML050740025 | 9 March 2005 | Unit 2 - License Amendment Change No. SQN-TS-03-06 - Response to Request for Additional Information | Tennessee Valley Authority Pace P | Office of Nuclear Reactor Regulation Document Control Desk |
ML051160009 | 3 May 2005 | License Amendment, Revises Portions of Technical Specification Surveillance Requirement 4.4.5 to Eliminate the Requirement to Inspect a Portion of the Tube within the Tubesheet Region | Pickett D NRC/NRR/DLPM/LPD2 | Tennessee Valley Authority Singer K |
ML081010342 | 10 April 2008 | Notification of Inspection and Request for Information | NRC/RGN-II/DRS/EB3 Hopper G | Tennessee Valley Authority Campbell W |