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List of results

• ML022030209  + (Reactor Vessel Head Degradation Lessons Learned Task Force Public Meeting Summaries - June 12 and June 19 Meetings; Memo to William F. Kane, Deputy. Memo to William F. Kane, Deputy Executive Director for Reactor Programs)
• ML030280708  + (Reactor Vessel Head Degradation Lessons Learned Task Force: Transcript of Public Meeting Held on Nov 20, 2002 in Oak Harbor, Oh)
• ML030280448  + (Reactor Vessel Head Degradation Lessons-Learned Task Force Report Executive Summary - Handout Provided at Public Meeting on November 20, 2002)
• ML030280481  + (Reactor Vessel Head Degradation Lessons-Learned Task Force - Public Meeting, November 20, 2002 (Presentation Slides))
• ML022810466  + (Reactor Vessel Head Degradation Lessons-Learned Task Force - Meeting Notice)
• RNP-RA/02-0122, Reactor Vessel Head Inspection Plan for Refueling Outage 21  + (Reactor Vessel Head Inspection Plan for Refueling Outage 21)
• NL-03-098, Reactor Vessel Head Inspection Results, Spring 2003 Refueling Outage  + (Reactor Vessel Head Inspection Results, Spring 2003 Refueling Outage)
• NL-02-162, Reactor Vessel Head Inspection Results; Indian Point 2, Fall 2002 Refueling Outage  + (Reactor Vessel Head Inspection Results; Indian Point 2, Fall 2002 Refueling Outage)
• ML030510264  + (Reactor Vessel Head Inspection Status, San Onofre Nuclear Generating Station Unit 3)
• ML040550033  + (Reactor Vessel Head Inspections, Calvert Cliffs Nuclear Power Plant, Inc)
• 05000335/FIN-2007003-01  + (Reactor Vessel Head Lift Practices)
• 05000369/FIN-2007003-02  + (Reactor Vessel Head Lift Practices Related to Design and Licensing Basis)
• ENS 41128  + (Reactor Vessel Head Nozzle Cracking)
• 05000339/LER-2001-003, Reactor Vessel Head Nozzle Through-Wall Leakage Due to Lack of Weld Fusion During Original Fabrication  + (Reactor Vessel Head Nozzle Through-Wall Leakage Due to Lack of Weld Fusion During Original Fabrication)
• ENS 40728  + (Reactor Vessel Head Nozzle Weld Area Flaw)
• ENS 42917  + (Reactor Vessel Head Nozzle Weld Area Flaw)
• ENS 50962  + (Reactor Vessel Head Penetration Flaw Identified During Inservice Inspection)
• L-05-091, Reactor Vessel Head Penetration Inspection 60-Day Report for 2R11  + (Reactor Vessel Head Penetration Inspection 60-Day Report for 2R11)
• ENS 52297  + (Reactor Vessel Head Penetration Nozzle Flaw)
• ML15147A155  + (Reactor Vessel Head Penetration Photographs Associated with Omaha Public Power District (OPPD) Relief Request RR-14)
• ENS 56165  + (Reactor Vessel Head Penetration Repair Degraded)
• ENS 51410  + (Reactor Vessel Head Penetration Repair Did Not Meet Acceptance Criteria)
• RC-12-0154, Reactor Vessel Head Penetration Weld Repair Under WCAP-15987  + (Reactor Vessel Head Penetration Weld Repair Under WCAP-15987)
• ML17334A175  + (Reactor Vessel Head Removal & Replacement)
• ML030770256  + (Reactor Vessel Head Replacement Project)
• ENS 43675  + (Reactor Vessel Head Vent May Not Be Isolable During a Fire)

• ML18086B242  + (Reactor Vessel Head Vent Operation)
• ML17319A962  + (Reactor Vessel Head Vent Operation)

• ML20037D461  + (Reactor Vessel Head Vent Operation, Revision 0)
• ML18086A750  + (Reactor Vessel Head Vent Operation. Revision 0.One Oversize Drawing Encl.Aperture Card Is Available in PDR)
• ML20263F718  + (Reactor Vessel Head Vent System)
• ML20263A270  + (Reactor Vessel Head Vent System)
• ML20266E675  + (Reactor Vessel Head Vent System Flow Diagram)
• ML17256A895  + (Reactor Vessel Head Vent System Piping Plan,Elevation & Details at El 250 Ft 6 Inches & Above)
• ML021550483  + (Reactor Vessel Head and Penetration Nozzle Condition Report)
• ML023650517  + (Reactor Vessel Head and Penetration Nozzle Condition Report)
• CP-202000263, Reactor Vessel Head, Bottom Mounted Instrumentation, and Hot Leg Ultrasonic Testing Examinations Relief Request  + (Reactor Vessel Head, Bottom Mounted Instrumentation, and Hot Leg Ultrasonic Testing Examinations Relief Request)
• EPID:L-2020-LLR-0063  + (Reactor Vessel Head, Bottom Mounted Instrumentation, and Hot Leg Ultrasonic Testing Examinations Relief Request)
• ML17345A420  + (Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation, Ltr Rept)
• ML20196C128  + (Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation)
• ML20034B937  + (Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation)
• ML20005G421  + (Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation)
• ML20055G994  + (Reactor Vessel Inservice Exam Rept (1990))
• ML20261D406  + (Reactor Vessel Inservice Insp)
• ML20262H355  + (Reactor Vessel Instrumentation P&I Diagram)
• ML20266H286  + (Reactor Vessel Instrumentation P&I Diagram, as Built)
• ML20265B240  + (Reactor Vessel Instrumentation.Sheet 1)
• ML040850115  + (Reactor Vessel Integrity Database Update for the Perry Nuclear Power Plant)
• ML18059A698  + (Reactor Vessel Integrity Project Plan)
• 2CAN071603, Reactor Vessel Internals Aging Management Program Plan for License Renewal Application  + (Reactor Vessel Internals Aging Management Program Plan for License Renewal Application)
• ML15135A358  + (Reactor Vessel Internals Aging Management Program and Inspection Plan for License Renewal Commitment No. 13)
• ML092720461  + (Reactor Vessel Internals Aging Management Program Inspection Plan)