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List of results

• ML17229A585  + (Rev 0 to ADM-29.01, IST Program for Pumps & Valves)
• ML20155C958  + (Rev 0 to ADN-BFN-1006V0, Procedure for Compliance with USNRC Regulatory Guide 1.150)
• ML20248B922  + (Rev 0 to AES 98033327-1-1, Updated Probabilistic Operational Assessment for SONGS Unit 2,Second Mid Cycle Operating Period,Cycle 9)
• ML20086T103  + (Rev 0 to ALPHA-510, Panda Facility Characterization Heat Loss & Selected Sys Lines Pressure Loss Test Plan & Procedure)
• ML20096F405  + (Rev 0 to ALPHA-520, Panda Transient Tests M3 & M4 Integral Sys Test Procedure)
• ML20096F431  + (Rev 0 to ALPHA-521, Panda Transient Tests M7 Integral Sys Test Procedure)
• ML20096F441  + (Rev 0 to ALPHA-527, Panda Transient Tests M2,M10A & M10B Integral Sys Test Procedure)
• ML20096F470  + (Rev 0 to ALPHA-528, Panda Transient Tests M9 Integral Sys Test Procedure)
• ML20096F451  + (Rev 0 to ALPHA-529, Panda Transient Tests M6/8 Integral Sys Test Procedure)
• ML20113B386  + (Rev 0 to ALPHA-608, Panda Transient Tests M2 Integral Sys Test Apparent Test Results)
• ML20113E730  + (Rev 0 to ALPHA-609, Panda Steady-State Tests Data Transmittal Rept)
• ML20135D259  + (Rev 0 to ANO Unit 2 Projected End of Cycle 12 Circumferential Crack Population)
• ML20153H165  + (Rev 0 to ANO Units 1 & 2 Technical Requirements Manual)
• ML20129A649  + (Rev 0 to ANO-1 Cycle 14 Colr)
• ML20198T112  + (Rev 0 to AP-404, Loss of Decay Heat Removal)
• ML20198T135  + (Rev 0 to AP-520, Loss of RCS Coolant or Pressure)
• ML20134A590  + (Rev 0 to AP600 Engineering Data Base Access & Control)
• ML20134A606  + (Rev 0 to AP600 Plant Instrumentation & Control Sys)
• ML20134A615  + (Rev 0 to AP600 Quality Assurance Procedures Supporting NRC Review of AP600 SSAR Sections 18.2 & 18.8)
• ML20140D069  + (Rev 0 to AP600 Shutdown Evaluation Rept)
• ML20059G508  + (Rev 0 to APA-ZZ-01003, Odcm)
• ML20197H321  + (Rev 0 to AR-490, Reactor Coolant Sys Boration)
• ML20077F596  + (Rev 0 to AS-50092, QA Program for Simplified Bwr)
• ML20097G085  + (Rev 0 to ASME Code Case N-481 Evaluation of Arkansas Nuclear One Unit 1 Reactor Coolant Pumps)
• ML20141D987  + (Rev 0 to ASME Code Evaluation of Braidwood Unit 2 Nozzle F to Include Effects of Proposed Grindouts)

• ML20079G422  + (Rev 0 to ASME Code Section XI Inservice Insp & Testing Program)

• ML20154Q751  + (Rev 0 to ASME Section XI Preservice Insp Plan)
• ML20205P461  + (Rev 0 to ASME Section XI Pump & Valve Test Programs - Units 1 & 2,Second 10-Yr Interval)
• ML20206N885  + (Rev 0 to ASME Section XI Sys Pressure Test Program,Second Insp Interval)
• ML20245B297  + (Rev 0 to ASNT-CP-IRRSP-1A, Asnt Certification Program for Industrial Radiographer Radiation Safety Personnel)
• ML19354D503  + (Rev 0 to ATWS Mitigation Sys Design for Zion Station Units 1 & 2)
• ML20155C075  + (Rev 0 to Abnormal Operating Procedures 18038-2, Operation from Remote Shutdown Panels)
• ML20077F861  + (Rev 0 to Abnormal Procedure AP-530, Natural Circulation)
• ML20210B114  + (Rev 0 to Acceptance Test Procedure 1CP-AT-27-1, Condenser Vacuum & Waterbox Priming)
• ML20134L238  + (Rev 0 to Accident Analysis)
• ML20202A833  + (Rev 0 to Accident Analysis Methods for Application to Salem Nuclear Units)
• ML20129D596  + (Rev 0 to Action Plan 10, Review of Operation of Porv)
• ML20129E164  + (Rev 0 to Action Plan 16, Rept on Main Steam Header Pressure)
• ML20129D607  + (Rev 0 to Action Plan 18, Startup Feed Valve SP-7A Problem Analysis)
• ML20129D574  + (Rev 0 to Action Plan 1C, Auxiliary Feed Pump Turbine Manual/Auto-Essential Control Problem)
• ML20129D635  + (Rev 0 to Action Plan 26, Inadvertent Auxiliary Feedwater Pump 1 Suction Supply Transfer from Condensate Storage Tank to Svc Water Supply)
• ML20116C129  + (Rev 0 to Action Plan to Address Fuel Loading Incident at Plant)
• ML20129D523  + (Rev 0 to Action Plans 5,6 & 7, Low Steam Generator Level Trip of Steam & Feedwater Rupture Control Sys)
• ML20116B601  + (Rev 0 to Addendum a to Piping Stress Rept, for Unit 1)
• ML20096D490  + (Rev 0 to Addendum to Plant-Unique Analysis Rept (Dtd 821001) on Safety Relief Valve Actuation Concurrent W/Loca (Cases C3.2 & C3.3))
• ML20100K827  + (Rev 0 to Adequacy of TMI-1 Once-Through Steam Generator Return to Svc Safety Assessment After 1984 Tech Spec Eddy Current Test Exam)
• ML20082E622  + (Rev 0 to Administrative Change Notice 01 to ES03.03, Cable & Raceway Control & Tracking Sys)
• ML20082E600  + (Rev 0 to Administrative Change Notice 02 to ES03.03, Cable & Raceway Control & Tracking Sys)
• ML20082D972  + (Rev 0 to Administrative Change Notice 03 to ES03.03, Cable & Raceway Control & Tracking Sys)
• ML20138J056  + (Rev 0 to Administrative Control Procedure ACP 6.15, Consisting of Nuclear Engineering & Operations Procedure Neo 8.02, Post-Trip & Transient Review)
• ML20206Q373  + (Rev 0 to Administrative Controls Procedure ACP 8.09, Millstone Licensed Operator Requalification Programs)