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TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT

Nitrogen +, Oxygen +, Hydrogen +, Aluminum +  and Tin +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 60 +, 10 CFR 501 +, 10 CFR 50.55a +, 10 CFR 50.55a#h +, 10 CFR 50.55#h +  and 10 CFR 50#10 +

Initiating Events +  and Mitigating Systems +

42 FR 5880 +  and 42 FR 58803 +

GDC 33 +, GDC 16 +, GDC 17, Electric power systems +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +, GDC 3, Fire protection +  and GDC 5, Sharing of structures, systems, and components +

IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action +, IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action +, IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action +, IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action +, IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action +  and IA-92-296, NRC Staff Rept on Union of Concerned Scientists Petition for Emergency & Remedial Action +

IEEE 384 +, IEEE 383 +, IEEE 382 +, IEEE 323 +, IEEE 323-1974 +, IEEE 279 +, IEEE 379 +, IEEE 323-1971 +, IEEE 334-1974 +, IEEE 334 +, IEEE 317 +, IEEE 334-1971 +, IEEE 381 +, IEEE 117 +, IEEE 98 1957 +  and IEEE 1323 1974 +

Natural Resources Defense Council +  and Union of Concerned Scientists +

Target Rock +  and General Electric +

NRC Bulletin 77-06 +  and NRC Bulletin 77-05 +

NUREG-0050, Forwards Documents Re 1975 Fire at Plant.Documents Provide Overview of Experience W/Significant Fire That Resulted in Spurious Component Operation,Loss of Control Functions & Erroneous Control Room Instrumentation Readings.W/O Encls +, NUREG-0138, Exemption from GDC 17 Requirements Re LPCI Swing Bus Design +, NUREG-0305, Forwards NUREG-0305,technical Rept on Dc Power Supplies in Nuclear Power Plants.W/O Encl +  and NUREG-0153, NRC Staff Response to ASLB Questions Concerning Generic Safety Issues.Conclusions in Perkins SER Re Issuance of Const Permits Will Not Be Affected by Results of Generic Tasks.W/Certificate of Svc.Supporting Documents Encl +

Regulatory Guide 1.75 +, Regulatory Guide 1.63 +, Regulatory Guide 1.53 +, Regulatory Guide 1.120 +, Regulatory Guide 1.89 +, Regulatory Guide 1.39 +, Regulatory Guide 1.20 +, Regulatory Guide 1.40 +, Regulatory Guide 1.73 +  and Regulatory Guide 1.131 +

07-60-100 +, 07-77-05A +  and 1NUBEG-3136 +

Texas +, Tennessee +, Connecticut +, Arizona +, Minnesota +, Washington +, South Carolina +, Arkansas +, New Mexico +  and Maine +

Steam Generator +, Feedwater +, Service water +, Reactor Protection System +, Auxiliary Feedwater +, Primary containment +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Main Steam +

Safe Shutdown +, Fire Barrier +, Coatings +, Incorporated by reference +, Design basis earthquake +, Earthquake +, Power Operated Valves +, Fire Protection Program +, Early Warning Fire Detection +  and Affidavit +