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IWB-2500 +  and IWA-2400 +

Nickel +, Copper +, Carbon +, Oxygen +, Hydrogen +  and Chloride +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 54 +, 10 CFR 2.109 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix I +, 10 CFR 54.21 +, 10 CFR 50.55a +, 10 CFR 54.4#b +, 10 CFR 50.49#f +, 10 CFR 50.49#e5 +, 10 CFR 50.54#q +, 10 CFR 54.37#b +, 10 CFR 54.21#d +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1iii +, 10 CFR 54.21#c +, 10 CFR 50.48#f +, 10 CFR 50.82#a1 +, 10 CFR 50.82#a2 +, 10 CFR 50.82#a1i +  and 10 CFR 50.71#e +

05000255  +  and 00255  +

NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, 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 +

ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +, ML23107A061 +  and ML23107A061 +

NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

NUREG-1432 +, 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-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0820, Safety Evaluation Supporting Amend 125 to License DPR-20 +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +, 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 +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

FPP +, RT +  and CP +

Regulatory Guide 1.160 +  and Regulatory Guide 1.26 +

Steam Generator +, Feedwater +, Service water +, Emergency Diesel Generator +, HVAC +, Circulating Water System +  and Control Rod +

Boric Acid +, High Radiation Area +, Ultimate heat sink +, Non-Destructive Examination +, Fire Barrier +, Probabilistic Risk Assessment +, Coatings +, Nondestructive Examination +, Aging Management +, Design basis earthquake +, Flow Accelerated Corrosion +, Feedwater Heater +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Moisture barrier +, License Renewal +, Earthquake +, Control of Heavy Loads +, Biofouling +, Fire Protection Program +, Backfit +, Siren +, Control Room Habitability +  and Spent fuel rack +

Cooling Tower +  and Lake Michigan +