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A list of all pages that have property "Title" with value "MRP-227 Rev 1-A Generic Resolution Final SE". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML071340397  + (MR-4-2007-0003, Partial Loss of Offsite Power at Diablo Canyon)
  • ML072270624  + (MR-I-07-0018: Dominion Promotes David Christian to President/Chief Nuclear Officer)
  • ML080510173  + (MR-I-08-0002, Exelon Nuclear Announces Management Change)
  • ML080650283  + (MR-I-08-0006, Exelon Nuclear Announces Management Change, 3/3/08)
  • ML081570317  + (MR-I-08-0007, Exelon Announces Management Changes at Peach Bottom, 6/4/08)
  • ML090750372  + (MR-I-2009-0002: Changes in Exelon Senior Management)
  • ML091310380  + (MR-I-2009-0003, Senior Management Changes for Constellation Energy Group Effective 06/01/09)
  • ML092230750  + (MR-II-09-0002 - Scana Senior Management Changes)
  • ML072600312  + (MR-III-07-0019 - Announcement of Duane Arnold Energy Center (DAEC) Management Change)
  • ML080530179  + (MR-III-08-0005 - Announcement of New Point Beach Plant Manager)
  • ML080860425  + (MR-III-08-0008: Announcement of New Perry Outages and Work Management Director)
  • ML083190324  + (MR-III-08-0014 - Engineering Director Changes)
  • ML090060882  + (MR-III-09-0001-Prairie Island Names New Engineering Director)
  • ML090900222  + (MR-III-2009-00004 - Management Changes at Prairie Island)
  • ML091820336  + (MR-III-2009-0005 - Fermi, Unit 2, Senior Management Changes)
  • ML23045A231  + (MRB and Impep Overview Briefing Sheet)
  • ML070240159  + (MRP 2007-003 Attachment 1, Implications of Wolf Creek Pressurizer Butt Weld Indications Relative to Safety Assessment and Inspection Requirements)
  • ML24122A730  + (MRP 2022-018 Current Knowledge State of Stainless Steel Stress Corrosion Cracking in Pressurized Water Reactor Environments)
  • ML22097A204  + (MRP 227 Rev 2 Completeness and Withholding Determinations)
  • ML22097A203  + (MRP 227 Rev 2 Completeness and Withholding Determinations)
  • ML21302A059  + (MRP 227 Rev 2 Completeness and Withholding Determinations)
  • ML18043B154  + (MRP-175 Revision 1 for SLR - Final Meeting Presentation)
  • ML21224A001  + (MRP-2021-012 - Transmit Closed Session Slides on MRP-232 Rev. 2 to Us NRC)
  • ML24304B022  + (MRP-227 R2 Draft EPRI-Industry Team Safety Evaluation Review - Comment Sheet-Oct28-24)
  • ML18275A069  + (MRP-227 Rev 1 Draft SE Transmittal Letter)
  • ML20141L315  + (MRP-227 Rev 1-A Generic Resolution Final SE)
  • ML23318A402  + (MRP-227 Rev 2 - Draft Conditions and Alais for Safety Evaluation)
  • ML20141L314  + (MRP-227, Rev 1-A Supplemental Information Final SE Transmittal Email)
  • ML22145A445  + (MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline - NRC 898, Completeness)
  • ML22145A444  + (MRP-227, Revision 2, PWR Internals Inspection and Evaluations Guideline - E-mail for Completeness Review)
  • ML24094A326  + (MRP-227, Revision 2, Subsequent RAI 4 - B&W-Designed PWR Internals Aging Management)
  • L-17-105, MRP-227-A Applicant Action Item 8: Revised Time-Limited Aging Analysis (Tlaa)Regarding Reactor Vessel Internals Loss of Ductility at 60 Years  + (MRP-227-A Applicant Action Item 8: Revised Time-Limited Aging Analysis (Tlaa)Regarding Reactor Vessel Internals Loss of Ductility at 60 Years)
  • ML16263A319  + (MRP-227-A Applicant/Licensee Action Item 7 Analysis, Topical Report, ANP-3479NP, Revision 0)
  • ML21019A003  + (MRP-228, Rev 4, Materials Reliability Program Inspection Standard for Pressurized Water Reactor Internals Nonproprietary)
  • ML20322A319  + (MRP-229, Rev 4)
  • ML21224A000  + (MRP-232 Rev 2 Aug 12 2021 Meeting Slides)
  • ML21180A028  + (MRP-232, Revision 2)
  • ML21180A031  + (MRP-232-NP, Revision 2, Materials Reliability Program: Aging Management Strategies for Westinghouse and Combustion Engineering PWR Internal Components)
  • ML14283A046  + (MRP-375, Technical Basis for Reexamination Interval Extension for Alloy 690 PWR Reactor Vessel Top Head Penetration Nozzles (EPRI 3002002441), Attachment 1)
  • ML18054A862  + (MRP-417)
  • ML24071A003  + (MRP-484, Timing for TS Rev Post Surv Cap Testing - NRC 897, Topical Report Withholding Determination)
  • ML24142A534  + (MRP-484: Timing Needed to Satisfy 10 CFR 50, Appendix H Requirements for Technical Specifications NRC –Epri MRP Public Meeting on May 23, 2024)
  • ML20262C936  + (MRS Facility Chtru Facility Foundation Plan and Details. Sheet 1 of 1)
  • ML20262C942  + (MRS Facility Chtru Facility Roof Plan and Sections.Sheet 1 of 1)
  • ML20262D163  + (MRS Facility Chtru Storage Facility Chtru Stor FAC Drain System Piping & Instrument Diagram.Sheet 1 of 1)
  • ML20262D167  + (MRS Facility Overall Site Control and Monitoring System Block Diagram.Sheet 1 of 1)
  • ML20262D461  + (MRS Facility R & H Buiding Remote Handled Equip Maintenance. Sheet 1 of 3)
  • ML20262D455  + (MRS Facility R & H Building Crane Maint Door Decon Cell)
  • ML20262D449  + (MRS Facility R & H Building Drum Preparation & Decon Cell)
  • ML20262D437  + (MRS Facility R & H Building High Activity Waste Cell)
  • ML20262D467  + (MRS Facility R & H Building Remote Handled Equip Maintenance.Sheet 2 of 3)