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Pages with broken file links, CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

ANSI N18.1-1971 +, ANSI 18.7-1976 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +

Strontium +, Iodine +, Cesium +, Uranium +  and Plutonium +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 30 +, 10 CFR 10 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 40 +, 10 CFR 50.49 +, 10 CFR 50.71 +, 10 CFR 50.91 +, 10 CFR 50.120 +, 10 CFR 73.21 +, 10 CFR 73.55 +, 10 CFR 50.54 +, 10 CFR 20.106 +, 10 CFR 20.302 +, 10 CFR 50.55a +, 10 CFR 50.49#a +, 10 CFR 50.54#p +, 10 CFR 50.54#a3ii +, 10 CFR 50.54#a3iv +, 10 CFR 50.36#a3 +, 10 CFR 50.48#f +, 10 CFR 50.48#f2 +, 10 CFR 50.82#a2 +, 10 CFR 50.82#a +, 10 CFR 50.82#a6 +...

05000155  +  and 00155  +

Consumers Energy +  and Powers K +

NRC Generic Letter 39-01 +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +  and NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification +

ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +, ML20236T665 +  and ML20236T665 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

Tritium +, Co-60 +, Cs-137 +, Cesium-137 +, Kr-85 +, Iodine-131 +, H-3 +  and Cobalt-60 +

IR 05000155/1987026 +, ML20216J441 +  and ML19345F513 +

NUREG-0586, Forwards NUREG-0586, Final Generic Environ Impact Statement on Decommissioning of Nuclear Facilities, W/Re to 971113 Request for Info Pertaining to Expected Occupational Doses Associated w/long-term Storage.W/O Encl +, NUREG-1302, Forwards Matl on CRGR Meeting 180 Re NUREG-1301 & NUREG-1302 & Summary of Discussions of Proposal to Eliminate CRGR Review of Certain Rev to 10CFR50.55a +  and NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +

SR-4.7.12 +, SR-4.3.3.8.1 +, SR-4.1.3 +, SR-4.7.11.2 +, SR-4.7.11.1.1 +, SR-4.7.11.1.2 +, SR-4.7.11.5 +  and SR-4.1.1.d +

Washington +, Michigan +  and Maine +

Service water +, Reactor Protection System +, Circulating Water System +  and Emergency Core Cooling System +

TS-3.7.12 +, TS-6.2.2 +, TS-3.2.2 +, TS-3.3.3.8 +, TS-5.2 +, TS-6.8.1 +, TS-1.0 +, TS-3.3.1.a +, TS-4.0.2 +, TS-6.4.1 +, TS-6.14 +, TS-5.1.5 +, TS-6.2.2.d +, TS-6.1.2 +, TS-4.1.3 +, TS-6.9.3 +, TS-7.0 +, TS-6.5 +, TS-6.2 +, TS-6.15 +, TS-6.1.1 +, TS-6.2.1.d +, TS-6.2.2.g +, TS-6.2.2.b +, TS-7.4 +, TS-4.2.5 +, TS-6.5.1.2 +, TS-3.7.11.2 +, TS-6.5.1.4 +, TS-3.7.11.1 +...

Safe Shutdown +, Grab sample +, Offsite Dose Calculation Manual +, Fire Barrier +, Process Control Program +, Loss of Offsite Power +, Safeguards Contingency Plan +, Control of Heavy Loads +  and Fire Protection Program +