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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

ASME Section XI +  and ASME Section III +

Environmental Protection Agency +  and Federal Emergency Management Agency +

Boron +, Iodine +, Cobalt +, Uranium +, Iron +, Radium +, Nickel +, Copper +, Carbon +, Oxygen +, Hydrogen +, Radon +, Zirconium +, Thorium +, Lead +, Tin +, Neptunium +  and Plutonium +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 30 +, 10 CFR 35 +, 10 CFR 40 +, 10 CFR 60 +  and 10 CFR 61 +

Emergency Preparedness +, Initiating Events +, Physical Protection +  and Mitigating Systems +

ML20135C927 +, ML20135C927 +, ML20135C927 +, ML20135C927 +, ML20135C927 +  and ML20135C927 +

IEEE 383 +, IEEE 382 +, IEEE 323 +, IEEE 317 +  and IEEE 535 +

Tritium +, Strontium-90 +, Cesium-137 +, Iodine-131 +  and Cobalt-60 +

Westinghouse +  and General Electric +

NUREG-0961 +, NUREG-1080, Forwards Listed Documents,Including Vol 3 to NUREG-1080, Vol 2 to NUREG-1145 & NUREG-1175, Safety Research in Support of Us NRC, for Preparation of Biennial Science & Technology Rept to Congress.W/O Encls +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR +, NUREG/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +, NUREG-0900, Informs Commission of Status of Staff Reassessment of Source Terms & Related Severe Accident Research Activities,For Use in Implementing Commission Severe Accident Policy Statement. NEA Mar 1986 Rept, Nuclear Reactor...Source Terms, Encl +, NUREG-0885, Notifies of NRC Feb or Mar 1985 Site Visits W/Bmnl to Obtain Util Views on Any Regulatory Requirements Believed to Have Marginal Importance to Safety & Burdensome to Util,Per Encl 841003 Fr Notice +, NUREG-0740, 04-14-81 Comments on NRC Long Range Research Plan, Fy 1983-1987 (NUREG-0740) +, NUREG-0784, 04-05-82 Comments on NRC Long-Range Research Plan, Fy 1984-1988 (Draft NUREG-0784) +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

RAP +, MP +, CP +  and SP-90 +

Regulatory Guide 1.63 +, Regulatory Guide 1.99 +, Regulatory Guide 3.54 +, Regulatory Guide 1.89 +  and Regulatory Guide 4.17 +

Pennsylvania +, Maryland +, Washington +, California +, Massachusetts +, New Jersey +, Idaho +, New York +, Oklahoma +, Arkansas +  and New Hampshire +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, Standby Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

Fitness for Duty +, High winds +, Ultimate heat sink +, Safe Shutdown Earthquake +, Weld Overlay +, Probabilistic Risk Assessment +, Nondestructive Examination +, Design basis earthquake +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Eddy Current Testing +, Earthquake +, Overexposure +, Thermal fatigue +, Leak-Before-Break +  and Leak Before Break +