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ML22144A130 +

Boron +, Iodine +, Cesium +, Uranium +, Krypton +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Xenon +, Zirconium + and Lithium +

CFR

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 71 +, 10 CFR 61 +, 10 CFR 50 Appendix I + and 10 CFR 50.34a +

Correspondence

L-22-058, Submittal of Revision 26 to Updated Final Safety Analysis Report +

Docket

05000412 +

FR

40 FR 40816 +

From

Energy Harbor Nuclear Corp +

Fuel cladding

Zircaloy +

General design criterion

GDC 60 + and GDC 64 +

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>.

ML22144A130 +, ML22144A130 +, ML22144A130 +, ML22144A130 +, ML22144A130 +, ML22144A130 +, ML22144A130 +, ML22144A130 +, ML22144A130 + and ML22144A130 +

Hours

5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months) +

IEEE

IEEE 344 +, IEEE 323 + and IEEE 279 +

In package

ML22144A115 +

Isotope

Tritium +, Co-60 +, Cs-137 +, U-235 +, Sr-90 +, Fe-55 +, Y-90 +, Kr-85 +, I-131 +, N-16 +, Nitrogen-16 +, C-14 +, Krypton-85 +, H-3 +, Mo-99 +, Mn-54 + and Deuterium +

Issue date

May 18, 2022 +

L

L-22-058, Submittal of Revision 26 to Updated Final Safety Analysis Report +

Licensing Basis Document

Updated Final Safety Analysis Report +

Manufacturer

Westinghouse + and General Electric +

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>.

07:33:54, 7 February 2025 +

NUREG

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Encls +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 + and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

Page count

181 +

Project stage

Request +

Regulatory Guide

Regulatory Guide 1.183 +, Regulatory Guide 1.97 +, Regulatory Guide 1.143 +, Regulatory Guide 1.100 +, Regulatory Guide 1.21 +, Regulatory Guide 8.8 + and Regulatory Guide 1.89 +

Report

NEDO-12154 +

SSC

1x10-6 +, 1x10-7 +, 1x10-4 +, 2x10-8 +, 1x10-2 +, 11A-1 +, 11A-i +, 11A-2 +, 11A-3 +, 11A-4 +, 11A-5 +, 11A-6 +, 11A-7 +, 11A-8 +, 11A-9 +, 11A-10 +, 11A-11 +, 11A-12 +, 11A-13 +, 11A-14 +, 11A-15 +, 11A-16 +, 11A-17 +, 11A-18 +, 1x10-10 +, 5x10-2 +, 11A-19 +, 11A-20 +, 11A-21 +, 11A-22 +...

May 18, 2022 +

Ohio +, Washington +, New York + and West Virginia +

System

Steam Generator +, Reactor Coolant System +, Service water +, Auxiliary Feedwater +, Main Steam Safety Valve +, Main Steam Line +, Main Condenser +, Control Rod + and Main Steam +

Title

6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management +

To

Office of Nuclear Reactor Regulation +

Topic

Boric Acid +, Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Annual Radioactive Effluent Release Report +, Feedwater Heater +, Process Control Program +, Fuel cladding + and Power Uprate +

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http://pbadupws.nrc.gov/docs/ML2214/ML22144A130.pdf +

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