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ML22119A032
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Category
Manual  and Calculation
ANSI code
ANSI N13.1-1969 +  and ANSI N13.10-1974 +
ASME section
ASME Section IV +
Accession number
ML22119A032  +
Agency
Environmental Protection Agency +
Atomic Element
Iodine +, Uranium +, Hydrogen +, Radon +, Lead +  and Plutonium +
CFR
10 CFR 50.73 +, 10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 20.1301 +, 10 CFR 20.1302 +, 10 CFR 20.2203 +, 10 CFR 50 Appendix I +, 10 CFR 50.36a +, 10 CFR 50.34a +, 10 CFR 50.65#a4 +, 10 CFR 20.1301#d +, 10 CFR 20.1301#a1 +  and 10 CFR 20.1302#b2 +
Correspondence
L-003388 +, L-003430 +  and L-003884 +
Cross cutting aspect
H.4(e) +  and H.3(t) +
Docket
05000373  +, 05000374  +  and 07200070  +
Engineering change
EC-360580 +, EC-387237 +  and EC-387161 +
From
Constellation +
General design criterion
GDC 60 +  and GDC 50 +
Generic letter
NRC Generic Letter 79-41, Compliance with 40 CFR 190, EPA Uranium Fuel Cycle Standard +  and NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +
Has query"Has query" is a predefined property that represents meta information (in form of a <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Subobject">subobject</a>) about individual queries and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +, ML22119A032 +  and ML22119A032 +
Hours
2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 4.166667e-4 d (0.01 hours, 5.952381e-5 weeks, 1.3698e-5 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 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)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +  and 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +
In package
ML22122A085 +
Isotope
Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Ra-226 +, Kr-85 +, I-131 +, N-16 +, Nitrogen-16 +, Iodine-131 +, H-3 +, Mo-99 +  and Mn-54 +
Issue date
September 30, 2021  +
L
L-003388 +, L-003430 +  and L-003884 +
Manufacturer
General Electric +
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07:46:29, 7 February 2025  +
NUREG
NUREG/CR-2919 +, NUREG-0172 +, NUREG-0543 +, NUREG/CR-3332 +, NUREG-0002 +, NUREG-4013 +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, 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 +, NUREG-0016, Revision 2 Calculation of Release of Radioactive Materials in Gaseous and Liquid Effluents from Boiling-Water Reactors GALE-BWR 3.2 Code +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, 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 +, NUREG-0348, Responds to Re Rural & Urban Characteristics of Proposed & Existing Nuclear Power Plants.Data Re Plant Site Characteristics & Current Licensing Status Contained in NUREG-0348 & NUREG-0380 +  and NUREG-0511, Forwards NUREG-0511, Draft Generic EIS on U Milling & Fr Notice.Rept Withheld (Ref 10CFR2.790) +
Page count
200  +
Power source
4V +
Procedure
RT +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.182 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 4.1 +, Regulatory Guide 4.15 +, Regulatory Guide 4.8 +, Regulatory Guide 1.23 +, Regulatory Guide 8.29 +, Regulatory Guide 1.111 +, Regulatory Guide 1.112 +, Regulatory Guide 4.2 +  and Regulatory Guide 1.113 +
Report
NEDO-20969B +  and NEDO-10871 +
SSC
1x10-6 +, 4E-5 +, 5E-4 +, 1x10-7 +, 2E-4 +, 1x10-4 +, 1x10-5 +, 9E-5 +, 7E-5 +, 6E-4 +, 1x10-11 +, 7E-4 +, 5x10-7 +, 5x10-8 +, 1x10-12 +, 1x10-10 +, 2N62-F057 +, 1N62-F057 +, 1D18-N903A +, 1D18-N903B +, 1D18-N002 +, 1D18-N012 +, 2D18-N903A +, 2D18-N002 +, 2D18-N012 +, 2FT-VG009 +, 2FY-VG009 +, 2FR-VG-009 +, 1FT-VG009 +, 1FY-VG009 +...
Site
LaSalle +
Start date
September 30, 2021  +
State
Idaho +  and Illinois +
System
Service water +, Primary containment +, HVAC +, Reactor Building Ventilation +, Standby Gas Treatment System +, Steam Jet Air Ejector +, Main Steam Line +  and Main Condenser +
TS
TS-3.7.6 +, TS-5.5.9.b +, TS-5.5.1 +, TS-5.6.3 +, TS-5.5.4.g +, TS-5.6.2 +  and TS-5.5.4.f +
Test
Post maintenance test +
Title
Offsite Dose Calculation Manual Part I RECS & Part II ODCM  +
To
Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +
Topic
Unanalyzed Condition +, Time of Discovery +, Grab sample +, Offsite Dose Calculation Manual +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Process Control Program +, Deep Dose Equivalent +, Power change +, Loss of condenser vacuum +  and Operational convenience +
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http://pbadupws.nrc.gov/docs/ML2211/ML22119A032.pdf  +
Ultimate Heat Sink
Mississippi River +  and Cooling Tower +
 
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