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AR 01162940 +, AR 01162977 +, AR 01162898 +, AR 01162729 +, AR 01162671 +, AR 01162731 +, AR 01162735 +, AR 01162739 +, AR 01162741 +, AR 01162745 +, AR 01162746 +, AR 01162828 +, AR 01162901 +, AR 01162909 +, AR 01162910 +, AR 01162911 +, AR 01162915 +, AR 01162918 +, AR 01162919 +, AR 01162922 +, AR 01162925 +, AR 01162927 +, AR 01162937 +, AR 01162944 +, AR 01162954 +, AR 01162958 +, AR 01162963 +, AR 01162965 +, AR 01162967 +, AR 01162969 +...

ASME Section XI +  and ASME Section III +

Iron +, Nickel +, Copper +, Carbon +, Oxygen +, Molybdenum +, Chloride +, Aluminum +  and Zinc +

10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.49 +, 10 CFR 50.60 +, 10 CFR 50.61 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 50.55a +, 10 CFR 54.3#a +, 10 CFR 50.49#f +, 10 CFR 50.49#a +, 10 CFR 54.37#b +, 10 CFR 50.61#b2 +, 10 CFR 50.61#b1 +, 10 CFR 54.21#c +, 10 CFR 54.21#b +, 10 CFR 50.55a#g6iiD +, 10 CFR 50.55a#b2xxiA +  and 10 CFR 50.71#e +

05000282  +  and 05000306  +

ML11235A622 +  and NUREG-1960, Supp 1, Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plants, Unit 1 and 2 +

Xcel Energy +  and Minnesota +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

ML24128A117 +, ML24128A117 +, ML24128A117 +, ML24128A117 +, ML24128A117 +, ML24128A117 +, ML24128A117 +, ML24128A117 +, ML24128A117 +, ML24128A117 +  and ML24128A117 +

NRC Bulletin 88-09 +  and NRC Bulletin 80-11 +

NUREG/CR-6260 +, NUREG-1960, Supp 1, Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plants, Unit 1 and 2 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +

Regulatory Guide 1.163 +, Regulatory Guide 1.127 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.89 +

Steam Generator +, Reactor Coolant System +, Service water +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Shield Building +  and Control Rod +

Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Anticipated operational occurrence +, Coatings +, Nondestructive Examination +, VT-2 +, Aging Management +, Stress corrosion cracking +, Eddy Current Testing +, Moisture barrier +, License Renewal +, Earthquake +, Fire Protection Program +, Backfit +, Power change +, Thermography +, Leak-Before-Break +, Spill +  and Pressure Temperature Limits Report +

WCAP-15338 +  and WCAP-15666 +

WCAP-15338 +  and WCAP-15666 +