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ML18053A736
Show incoming properties 
Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI 18.1 +, ANSI N42.18-2004 +, ANSI N13.1-1969 +, ANSI N13.1 +, ANSI/ANS-18.1-1984 +, ANSI/ANS-55.6 +, ANSI-N42.18-1980 +, ANSI-18.1 +, ANSI/ANS-55.6-1993 +  and ANSI/ANS-55.6 3 +
Accession number
ML18053A736  +
Agency
Department of Natural Resources +
Atomic Element
Boron +, Iodine +, Cobalt +, Cesium +, Uranium +, Rubidium +, Krypton +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Lead +, Lithium +  and Silver +
CFR
10 CFR 20 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 20 Appendix B +, 10 CFR 71 +, 10 CFR 61 +, 10 CFR 20.1301 +, 10 CFR 20.1406 +, 10 CFR 50 Appendix I +, 10 CFR 61.55 +, 10 CFR 71 Appendix A +, 10 CFR 50.36a +  and 10 CFR 70.24 +
Contact
Brian Hughes +
Docket
05200018  +  and 05200019  +
Document
ML091050234 +  and ML091460627 +
Drawing
Drawing 11.5-1 +, Drawing 11.2-52 +, Drawing 11.3-34 +  and Drawing 11.4-34 +
FR
58 FR 67657 +
From
Duke Energy +  and Donahue J +
General design criterion
GDC 60 +, GDC 64 +  and GDC 63 +
Generic letter
NRC Generic Letter 80-09, Low Level Radioactive Waste Disposal +, NRC Generic Letter 81-39, NRC Volume Reduction Policy +  and NRC Generic Letter 1981-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites +
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ML18053A736 +, ML18053A736 +, ML18053A736 +, ML18053A736 +, ML18053A736 +, ML18053A736 +, ML18053A736 +, ML18053A736 +, ML18053A736 +  and ML18053A736 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
Isotope
Tritium +, Co-60 +, Cs-137 +, Sr-90 +, Fe-55 +, Y-90 +, Co-57 +, Kr-85 +, I-131 +, N-16 +, Nitrogen-16 +, C-14 +, Carbon-14 +, H-3 +, Mo-99 +, Mn-54 +  and Deuterium +
Issue date
December 19, 2017  +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Westinghouse +
Modification date"Modification date" is a predefined property that corresponds to the date of the last modification of a subject and is provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a>.
14:24:48, 6 January 2025  +
NUREG
NUREG/BR-0058 +, 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 +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
184  +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.143 +, Regulatory Guide 1.21 +, Regulatory Guide 1.109 +, Regulatory Guide 4.15 +, Regulatory Guide 8.8 +, Regulatory Guide 1.113 +  and Regulatory Guide 1.110 +
Site
Lee +
Start date
December 19, 2017  +
State
Arizona +  and South Carolina +
System
Steam Generator +, Reactor Coolant System +, Service water +, HVAC +, Residual Heat Removal +, Circulating Water System +, Main Steam Line +  and Main Condenser +
Title
Duke Energy Wsl III Units 1 & 2 COL (Updated Final Safety Analysis Report) Rev.1 - UFSAR Chapter 11 - Radioactive Waste Management  +
To
Office of New Reactors +
Topic
Safe Shutdown +, Boric Acid +, Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Hydrostatic +, Probabilistic Risk Assessment +, Process Control Program +, Main Steam Line Radiation Monitor +, Fuel cladding +, Pressure Boundary Leakage +  and Pressure boundary leak +
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http://pbadupws.nrc.gov/docs/ML1805/ML18053A736.pdf  +
Ultimate Heat Sink
Cooling Tower +
 
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