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IWB-3600 +  and IWB-3500 +

ASME Section III +  and ASME Section XI +

Iron +, Nickel +, Copper +, Carbon +  and Lead +

BWRVIP-26 +, BWRVIP-74 +  and BWRVIP-05 +

10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 54.3 +, 10 CFR 54.21 +, 10 CFR 54.4#a +, 10 CFR 54.4#b +, 10 CFR 50.49#e +, 10 CFR 50.49#f +, 10 CFR 50.54#d +, 10 CFR 54.21#d +, 10 CFR 54.21#a3 +, 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 50.55a#g +, 10 CFR 50.55a#a3i +  and 10 CFR 50.21#c2 +

05000277  +  and 05000278  +

NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +  and NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +

ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +, ML022590519 +  and ML022590519 +

LRA B.2.7 +  and LRA B.4.2 +

ML20058K266 +, 05000278/LER-1999-001, Forwards LER 99-001-00 Re 990312 ESF Actuation of Rcics Due to High Steam Flow Signal During Sys Restoration.Rept Submitted Per 10CFR50.73(a)(2)(iv) +, ML20248H145 +, ML20210N071 +, ML20036A070 +, ML020370579 +  and ML020250415 +

Westinghouse +, Foxboro +, Limitorque +, Valcor +, General Electric +, Target Rock +  and Static O-Ring +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG/CR-6583 +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +  and NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +

Regulatory Guide 1.190 +, Regulatory Guide 1.99 +, Regulatory Guide 1.89 +  and Regulatory Guide 1.154 +

Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Safety Relief Valve +, Control Rod +  and Main Steam +

Safe Shutdown +, Anticipated operational occurrence +, Hydrostatic +, Incorporated by reference +, Aging Management +, Stress corrosion cracking +, License Renewal +, Power Uprate +  and Thermal fatigue +