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Iron +, Copper +, Carbon +, Oxygen +, Hydrogen +, Chlorine +, Lead +  and Aluminum +

BWRVIP-75-A +, BWRVIP-116 +, BWRVIP-25 +, BWRVIP-130 +, BWRVIP-74 +, BWRVIP-05 +, BWRVIP-27-A +, BWRVIP-48-A +  and BWRVIP-49-A +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.4 +, 10 CFR 54.29 +, 10 CFR 650 +, 10 CFR 50.55a +, 10 CFR 50.49#f +, 10 CFR 50.49#a +, 10 CFR 54.21#d +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 54.21#ci +, 10 CFR 54.21#a +  and 10 CFR 50.55a#g6iiA +

JAFP-06-0109, License Renewal Application, Amendment 10, RAI Responses +  and JPN-94-041, Forwards Completed Applicability Verification Forms Contained in App B to NEDO-32205, BWROG Topical Rept on Use Equivalent Margin Analysis,Rev 1, in Response to NRC Request for Info Re Util Response to GL 92-01,Rev 1 +

05000333  +  and 00333  +

Entergy +  and Peter Dietrich +

NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +  and NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds +

ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +, ML062160553 +  and ML062160553 +

General Electric +  and Limitorque +

NUREG/CR-6260 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +  and NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +

TAC:MA6215 +  and TAC:M93925 +

Regulatory Guide 1.160 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.89 +

70AHU-3A +, 70AHU-19A +, 70RWC-2B +, 27E-1 +, 70AHU-12A +, 70RWC-2A +, 72UC-12A +, 72UC-25 +, 72UC-26 +, 72UC-35 +, 27NV-A +, 16X-1A +, 16X-1B +, 16X-2A +  and 27PBC-1 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Circulating Water System +, Stator Cooling Water +, Residual Heat Removal Service Water +, Reactor Building Closed Loop Cooling +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Main Steam +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Loop seal +, Non-Destructive Examination +, Fire Barrier +, Coatings +, Operating Basis Earthquake +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, License Renewal +, Earthquake +, Fire Protection Program +, Dissimilar Metal Weld +, Power Uprate +, Eddy Current Test +  and Leak Before Break +