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10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 54.21 +, 10 CFR 50.61a +  and 10 CFR 50.55a +

CR-PNP-2016-00015 +  and CR-PNP-2014-00049 +

05000255  +  and 00255  +

ML14211A520 +, ML15209A791 +  and ML14336A397 +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +, ML16120A325 +  and ML16120A325 +

NEI 96-03 +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +

NRC Bulletin 79-14 +, NRC Bulletin 88-11 +, NRC Bulletin 88-08 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

NUREG/CR-5704 +, NUREG/CR-6260 +, NUREG-800 +, 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-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-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0820, Safety Evaluation Supporting Amend 125 to License DPR-20 +, NUREG-1424, Forwards SER of Util 900122 Application Re full-term OL for Plant.Conversion of Provisional OLs Subsumed in SEP Program. Issues Releval to Provisional OL Conversions Not Covered in SEP Program,Covered in Ser.W/O Encl +, NUREG-1871, Safety Evaluation Report Related to the License Renewal of Palisades Nuclear Plant +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

TAC:ME5263 +, CAC:MF5163 +, TAC:ME5806 +, TAC:ME7125 +  and TAC:M69468 +

Regulatory Guide 1.160 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.14 +

Steam Generator +, Service water +, Reactor Pressure Vessel +  and Residual Heat Removal +

Safe Shutdown +, Boric Acid +, Aging Management +, Loss of Offsite Power +, License Renewal +  and Control of Heavy Loads +

WCAP-15973-P +, WCAP-17628-NP +  and WCAP-15338-A +

WCAP-15973-P +, WCAP-17628-NP +  and WCAP-15338-A +