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ML19294A793
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ASME section
ASME Section II +
Accession number
ML19294A793  +
Animal
Alewife +
Atomic Element
Boron +, Iodine +, Cesium +, Sodium +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50.109 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.34a +, 10 CFR 20.106#e +, 10 CFR 170.12#c +  and 10 CFR 20#10 +
Docket
05000309  +  and 00309  +
Drawing
SE-18 +
From
Vandenburgh D +  and Maine Yankee +
General design criterion
GDC 60 +
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ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +, ML19294A793 +  and ML19294A793 +
Hours
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)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +
Isotope
Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Cesium-137 +, Kr-85 +, I-131 +, Iodine-131 +, Carbon-14 +, H-3 +, Mo-99 +, Cesium 137 +, Cobalt-60 +  and Mn-54 +
Issue date
March 15, 1979  +
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13:34:32, 2 January 2025  +
NUREG
NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +
Page count
75  +
Power source
115KV +
Procedure
RT +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.109 +
SSC
06E-04 +
Site
Maine Yankee +
Site license
DPR-36 +
Start date
March 15, 1979  +
State
Washington +, Massachusetts +  and Maine +
System
Steam Generator +, Reactor Coolant System +, Service water +, Reactor Protection System +, Control Rod +  and Containment Spray +
TS
TS-3.16 +  and TS-3.17 +
Title
Forwards Proposed Mods to Radiological Effluent Tech Specs & Draft Offsite Dose Calculation Manual  +
To
Reid R +  and Office of Nuclear Reactor Regulation +
Topic
Shutdown Margin +, High Radiation Area +, Grab sample +, Offsite Dose Calculation Manual +, Annual Radiological Environmental Operating Report +, Fuel cladding +  and Fire Protection Program +
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http://pbadupws.nrc.gov/docs/ML1929/ML19294A793.pdf  +
 
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