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| from | MONTHYEARML0525101172005-09-080Issue date: 8 September 2005
Title: 4 of Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 (Formerly Draft Regulatory Guide DG-1125)
ML0524202332005-09-010Issue date: 1 September 2005
Title: Summary of Meeting with Electric Power Research Institute, Southern Nuclear Operating Company and Westinghouse on Mitigation of Primary Water Stress Corrosion Cracking
ML0521305622005-08-170Issue date: 17 August 2005
Title: 3 of Regulatory Guide 1.84, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III (Formerly Draft Regulatory Guide DG-1124)
ML0521405012005-08-170Issue date: 17 August 2005
Title: Of Regulatory Guide 1.193, ASME Code Cases Not Approved for Use (Formerly Draft Regulatory Guide DG-1126)
ML0509002902005-04-140Issue date: 14 April 2005
Title: Notice of Meeting Between NRC Staff, Pacific Northwest National Laboratory Staff, and Industry Representatives on Non-Destructive and Destructive Examinations of Nozzles Salvaged from the Discarded North Anna 2 Vessel Head
ML0509402592005-04-040Issue date: 4 April 2005
Title: Evaluation of Code Cases in Supplement 12 to the 1998 Edition and Supplement 1 Through Supplement 6 to the 2001 Edition
ML0408503462004-04-300Issue date: 30 April 2004
Title: Draft Regulatory Guide DG-1125, (Proposed Revision 14 of Regulatory Guide 1.147), Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1
ML0408502992004-04-300Issue date: 30 April 2004
Title: Draft Regulatory Guide DG-1124, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III
ML0408502362004-04-300Issue date: 30 April 2004
Title: Draft Regulatory Guide DG-1126 (Proposed Revision 1 to Regulatory Guide 1.193) ASME Code Cases Not Approved for Use
ML0410301072004-04-090Issue date: 9 April 2004
Title: Expert Panel Review
ML0405004662004-02-110Issue date: 11 February 2004
Title: Notice of Meeting Between NRC Staff and Industry Representatives on Corrosion of Reactor Pressure Boundary Materials in Boric Acid Solutions, and on Examinations of Nozzles Removed from Discarded North Anna 2 Reactor Vessel Head
ML0319001292003-07-080Issue date: 8 July 2003
Title: Review of NRC Draft NUREG Report Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Criteria in the PTS Rule (10CFR50.61, NEI Project Number 689
ML0315306512003-04-170Issue date: 17 April 2003
Title: April 17, 2003 - RIC 2003 Presentation - T9 - Edwin M. Hackett - Operating Experience Assessments
ML0311103992002-10-290Issue date: 29 October 2002
Title: E-mail from J. Hixon to J. Hopkins, Regarding NRC Request for Weld Data Sheets for RVCH
ML0311103902002-10-120Issue date: 12 October 2002
Title: E-mail from J. Hixon to A. Mendiola, Regarding Another Weld Data Sheet for the Davis Besse Reactor Head
ML0311103842002-10-120Issue date: 12 October 2002
Title: E-mail from J. Hixon to Gfd, Regarding Another Weld Data Sheet for the Davis Besse Reactor Head
ML0311103832002-10-120Issue date: 12 October 2002
Title: E-mail from J. Hixon to D. Jackson, Regarding Davis Besse Cladding Update
ML0311103812002-10-110Issue date: 11 October 2002
Title: E-mail from J. Hixon to D. Dawes, Regarding Besse Head Cladding
ML0311103772002-10-080Issue date: 8 October 2002
Title: E-mail from J. Hixon to W. Cullen, Regarding Ian Barnes Contact Info
ML0311103582002-08-160Issue date: 16 August 2002
Title: E-mail from W. Cullen to S. Long, Regarding Origin of Anl Results
ML0311103552002-08-140Issue date: 14 August 2002
Title: E-mail from W. Cullen to S. Long, Regarding SDP Thought
ML0212202532002-05-080Issue date: 8 May 2002
Title: 05/23-24/2002 Public Meeting on Status of Pressurized Thermal Shock Rule, 10 CFR 50.61, Technical Basis Re-evaluation Project
ML0315304022002-05-050Issue date: 5 May 2002
Title: NRC Assessment of Margin Available at Davis Besse
ML0609406041998-07-220Issue date: 22 July 1998
Title: Confirmatory Action Letter 97-7-001 Technical Evaluation
2005-09-08 |
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