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CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE  and NRC TO PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA

Boron +, Iodine +, Oxygen +, Sodium +, Hydrogen +  and Chlorine +

10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2 +, 10 CFR 50.92 +, 10 CFR 51.22 +, 10 CFR 2.714 +, 10 CFR 2.714#a1i +, 10 CFR 80.92 +, 10 CFR 51.12#b +, 10 CFR 50.62#c41 +, 10 CFR 51.22#b +  and 10 CFR 50.92#c +

LO-LAR-86-00005 +, LO-LAR-86-00012 +, LO-LAR-86-00009 +, LO-LAR-87-00001 +, LO-LAR-87-00002 +  and LO-LAR-87-00003 +

05000333  +, 00333  +, 00261  +, 00370  +, 00302  +, 00289  +, 00323  +, 00275  +, 00286  +, 00267  +, 00361  +, 00414  +, 00409  +, 00315  +, 00335  +, 00418  +, 00382  +, 00312  +, 00354  +, 00395  +, 00271  +, 00397  +, 00338  +, 00339  +, 00362  +  and 00389  +

Turbine Trip +  and Reactor Trip +

51 FR 7744 +, 51 FR 7751 +, 51 FR 7750 +, 50 FR 20969 +, 49 FR 25363 +, 51 FR 27287 +, 49 FR 25372 +, 52 FR 2889 +, 52 FR 11352 +, 51 FR 22234 +, 51 FR 8600 +, 52 FR 4402 +, 50 FR 41243 +, 52 FR 5852 +, 52 FR 5851 +, 49 FR 25358 +, 49 FR 42818 +, 52 FR 3894 +, 51 FR 38090 +, 52 FR 5855 +, 51 FR 41843 +, 52 FR 1555 +, 52 FR 5862 +, 52 FR 8859 +, 52 FR 4400 +, 52 FR 5865 +, 51 FR 18690 +, 52 FR 2888 +, 51 FR 20373 +, 52 FR 5888 +...

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 85-09, Technical Specifications for Generic Letter 83-28, Item 4.3 +  and NRC Generic Letter 65-19 +

ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +, ML20215H785 +  and ML20215H785 +

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)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 0.00926 d (0.222 hours, 0.00132 weeks, 3.044e-4 months)  +, 0.00463 d (0.111 hours, 6.613757e-4 weeks, 1.522e-4 months)  +  and 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +

IR 05000333/1987008 +, ML20266G966 +  and JPN-87-005, Forwards Rev to IGSCC Weld Insp Program.Rev Affects Method of Expanding Sample Size,Per Agreement.Implementation of Program Proceeding +

Westinghouse +  and General Electric +

NUREG-0452 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, 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-0830, Advises That Condition 2.c.(3)(a) of License NPF-30 Fulfilled,Based on & 860117 Rept Re Environ Qualification Program for Electrical Equipment.Program Previously Accepted Per NUREG-0830,Section 3.11 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

07-97-415 +, 3A3-1 +, 07-30-387 +, 07-88-418 +, 07-56-414 +, 07-56-333 +, 07-56-313 +, 07-58-381 +, 07-56-300 +, 2AS-070 +, 07-58-444 +, 07-56-395 +, 07-88-483 +, 07-56-348 +, 07-56-440 +  and 3A3-L +

Manual Scram +  and Automatic Scram +

Turkey Point +, Diablo Canyon +, La Crosse +  and DPR-81 +

Ohio +, Pennsylvania +, Connecticut +, Arizona +, Georgia +, Illinois +, Colorado +, Maryland +, North Carolina +, Washington +, California +, Alabama +, Virginia +, New Jersey +, South Carolina +, New York +, Michigan +, Wisconsin +, Florida +, Louisiana +, Missouri +, Indiana +, Mississippi +, Nebraska +, Arkansas +, Vermont +, Oregon +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Residual Heat Removal +, Reactor Water Cleanup +, Main Steam Safety Valve +, Main Steam Line +, Safety Relief Valve +, Control Rod +  and Main Steam +

TS-3.8.1.1 +, TS-3.3.1 +, TS-5.3.1 +, TS-6.5.2.9 +, TS-4.7.5.1 +  and TS-4.3.10.b +

Reactor Vessel Water Level +, Anticipated operational occurrence +, Post Accident Monitoring +, High Energy Line Break +, Loss of Offsite Power +, Control of Heavy Loads +, Fuel cladding +  and Fire Protection Program +