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Pages with broken file links, FINAL HAZARD SUMMARY REPORT (INCLUDING AMENDS)  and TEXT-SAFETY REPORT

ASME Section XI +, ASME Section III +  and ASME Section VIII +

Boron +, Iodine +, Nickel +, Copper +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Xenon +, Chlorine +, Zirconium +, Chloride +, Lead +, Helium +, Beryllium +, Phosphorus +, Chromium +, Silver +, Antimony +, Hafnium +  and Plutonium +

10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.62#c5 +, 10 CFR 50.55#a +  and 10 CFR 50.44#c3iii +

05000155  +  and 00155  +

FC-219 +, FC-444 +, FC-464 +, FC-497 +, FC-490 +, FC-498 +, FC-489 +, FC-479 +, FC-245 +, Drawing 5.4-24 +, FC-351 +, FC-590 +  and FC-598 +

NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +, NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +  and NRC Generic Letter 84-07, Procedural Guidance for Pipe Replacement at BWRs +

ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +, ML20011D739 +...

1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.430556e-4 d (0.00583 hours, 3.472222e-5 weeks, 7.9905e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

U-235 +, I-131 +, N-16 +, Nitrogen-16 +, Iodine-131 +  and Pu-239 +

ML030150829 +, ML20129K108 +, ML20126E362 +, A40314, Pressure Switch Data Sheet. Sheet 3 of 6 +, ML20210H862 +, 05000155/LER-1982-020, Forwards LER 82-020/03L-0 +, ML20054K484 +, ML20052B190 +, 05000155/LER-1981-027, Forwards LER 81-027/03L-0 +, 05000155/LER-1981-018, Forwards LER 81-018/03L-0 +, ML20028D361 +, ML20053D338 +, ML20027B219 +, ML20031C552 +, 05000155/LER-1981-011-03, /03L-0:on 810612,vacuum Relief Capability for Containment Bldg Exhaust Loop Was Inoperable on 810612,16 & 18.Cause Not Stated +, ML20005B011 +, IR 05000155/1975001 +, ML19344A314 +, ML19340D091 +, ML20002D895 +, ML19337A791 +, ML20023E204 +, ML20030A509 +, IR 05000155/1979013 +, ML19207B363 +, ML17194A294 +, ML19210C744 +, ML20030A524 +, ML20030A472 +, ML20028F725 +...

General Electric +  and Westinghouse +

NRC Bulletin 82-03 +  and NRC Bulletin 88-08 +

NUREG-0828, Concurs W/Interpretation of Intent of Item 4(5) of SER Re NUREG-0828,Sections 4.5, Wind & Tornado Loadings & 4.8, Tornado Missiles. Alternate Shutdown Bldg Will Be Manned When Tornado Warning Broadcast for General Area +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0138, Exemption from GDC 17 Requirements Re LPCI Swing Bus Design +, NUREG-0569, Forwards NUREG-0569, Evaluation of Integrity of SEP Reactor Vessels, Completing Review of SEP Topic V-6.W/o Encl +, NUREG-0531, Forwards NUREG-0531, Investigation & Evaluation of Stress Corrosion Cracking in Piping of LWR Plants & Notice of Issuance.W/O Rept.Fr Notice Encl +  and NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +

ST +, RT +, TP-304 +  and TP-316 +

Regulatory Guide 1.45 +  and Regulatory Guide 1.56 +

Idaho +  and Michigan +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +, Control rod blade +, Main Condenser +, Control Rod +  and Main Steam +

TS-3.4.3.2 +, TS-3.4.3.1 +  and TS-4.1.2 +

Safe Shutdown +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Probabilistic Risk Assessment +, Squib +, Feedwater Heater +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Liquid penetrant +, Pressure Boundary Leakage +, Flow Induced Vibration +, Unidentified leakage +, Unidentified leak +  and Failure to Scram +