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ML21197A009
Show incoming properties 
Category
Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation  and Technical Specifications
ASME section
ASME Section IV +  and ASME Section XI +
Accession number
ML21197A009  +
Act
Atomic Energy Act of 1954 +
Atomic Element
Iron +, Nickel +, Copper +, Lead +  and Titanium +
CFR
10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 30 +, 10 CFR 51 +, 10 CFR 50.60 +, 10 CFR 50.55a +, 10 CFR 50.36#c5 +, 10 CFR 51.22#b +  and 10 CFR 51.22#c9 +
Code case
ASME Code Case N-640 +  and ASME Code Case N-588 +
Contact
Goetz S, NRR/DORL/LPL1, 415-8004 +
Docket
05000334  +, 05000412  +, 00334  +  and 00412  +
Document
Regulatory Guide 1.190 +, ML050120209 +, ML031070449 +, ML070380185 +, RIS 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components +, ML031070438 +, L-14-141, Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report +, ML13242A266 +, ML18204A010 +, L-19-102, Submittal of Pressure and Temperature Limits Report Revision +, ML18164A082 +, ML19126A195 +, ML20024E573 +, L-20-274, Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits +, ML14288A393 +, ML20302A376 +, L-21-205, Supplement to Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperatures Limits +, ML21197A009 +, ML021580226 +  and ML21113A044 +
FR
85 FR 55514 +  and 85 FR 85674 +
From
Sujata Goetz +  and NRC/NRR/DORL/LPL1 +
Fuel cladding
ZIRLO +
General design criterion
GDC 14 +, GDC 30 +  and GDC 31 +
Generic letter
NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +  and NRC Generic Letter 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits +
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ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +, ML21197A009 +...
Issue date
November 1, 2021  +
Letter
ML13242A266 +, ML18178A112 +, ML19126A195 +, L-20-274, Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits +  and L-21-106, Response to Request for Additional Information Regarding Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits +
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>.
12:18:32, 29 November 2024  +
NUREG
NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
PWROG
PWROG-15109 +
Page count
24  +
Person
Sujata Goetz +
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ML21197A009 +
Project
EPID:L-2020-LLA-0233 +
Project reference
EPID:L-2020-LLA-0233 +
Project stage
Approval  +
Regulatory Guide
Regulatory Guide 1.190 +  and Regulatory Guide 1.99 +
Regulatory Issue Summary
RIS 2014-11, Information on Licensing Applications for Fracture Toughness Requirements for Ferritic Reactor Coolant Pressure Boundary Components +
Site
Beaver Valley +
Site license
Beaver Valley +  and NPF-73 +
Start date
November 1, 2021  +
State
Pennsylvania +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Pressure Vessel +  and Emergency Core Cooling System +
TS
TS-3.3.3 +, TS-3.4.12 +, TS-3.4.3 +, TS-5.6.4 +  and TS-5.6.4.b +
Title
Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report  +
To
Grabnar J +  and Energy Harbor Nuclear Corp +
Topic
Post Accident Monitoring +, Hydrostatic +, Nondestructive Examination +, Incorporated by reference +, Stress corrosion cracking +, Exemption Request +, Power Uprate +  and Pressure Temperature Limits Report +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML2119/ML21197A009.pdf  +
WCAP
WCAP-14040 +, WCAP-14040-A +, WCAP-12610-P-A +, WCAP-16045-P-A +, WCAP-17661 +, WCAP-18124-NP +, WCAP-18124 +, WCAP-18124-NP-A +, WCAP-17896-NP +, WCAP-18558-NP +, WCAP-18559-NP +  and WCAP-18124-NPA +
Westinghouse report
WCAP-14040 +, WCAP-14040-A +, WCAP-12610-P-A +, WCAP-16045-P-A +, WCAP-17661 +, WCAP-18124-NP +, WCAP-18124 +, WCAP-18124-NP-A +, WCAP-17896-NP +, WCAP-18558-NP +, WCAP-18559-NP +  and WCAP-18124-NPA +
 
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