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ML25091A299
Show incoming properties 
Category
License-Application for Facility Operating License (Amend/Renewal) DKT 50  and Topical Report
ASME code
IWB-3410 +
ASME section
ASME Section XI +
Accession number
ML25091A299  +
Atomic Element
Boron +, Nickel +, Carbon +, Oxygen +, Hydrogen +, Molybdenum +, Chloride +, Lead +, Sulfur +, Zinc +, Chromium +  and Tungsten +
CFR
10 CFR 50 +
Code case
ASME Code Case N-770-5 +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
RA-25-0067, Enclosure 3, Attachment 2 - Subsequent License Renewal Application, Appendix E, Environmental Report +
Docket
05000261  +
Document
ML21266A045 +
Equipment trip
Reactor Trip +
From
Duke Energy +
General design criterion
GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +
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ML25091A299 +, ML25091A299 +, ML25091A299 +, ML25091A299 +, ML25091A299 +, ML25091A299 +, ML25091A299 +, ML25091A299 +, ML25091A299 +, ML25091A299 +  and ML25091A299 +
Hours
0 d (0 hours, 0 weeks, 0 months)  +
In package
ML25091A290 +
Inspection report
IR 05000152/2037100 +, IR 05000263/2034200 +  and IR 05000500/2036100 +
Issue date
April 1, 2025  +
License amendment topic
License Renewal Application +
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>.
00:19:52, 11 April 2025  +
NUREG
NUREG/CR-4513 +, NUREG-0691 +, NUREG/CR-6177 +, NUREG/CR-6721 +, NUREG/CR-3464 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0531, Forwards NUREG-0531, Investigation & Evaluation of Stress Corrosion Cracking in Piping of LWR Plants & Notice of Issuance.W/O Rept.Fr Notice Encl +
Page count
1  +
Procedure
RT +
Project stage
Other  +
RA
RA-25-0067, Enclosure 3, Attachment 2 - Subsequent License Renewal Application, Appendix E, Environmental Report +
Regulatory Guide
Regulatory Guide 1.45 +
Site
Robinson +
Start date
April 1, 2025  +
State
Washington +  and New York +
System
Reactor Coolant System +, Feedwater +, Reactor Pressure Vessel +  and Control Rod +
Title
Enclosure 4, Attachment 3 - WCAP-15628-NP, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the H.B. Robinson Unit 2 Nuclear Power Plant for the Subsequent License Renewal Program,  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown Earthquake +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, License Renewal +, Subsequent License Renewal +, Pressure Boundary Leakage +, Pressure boundary leak +, DM weld +, Water hammer +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML2509/ML25091A299.pdf  +
WCAP
WCAP-9283 +, WCAP-9558 +, WCAP-9787 +, WCAP-15628 +  and WCAP-15628-NP +
Westinghouse letter
NS-EPR-2519 +
Westinghouse report
WCAP-9283 +, WCAP-9558 +, WCAP-9787 +, WCAP-15628 +  and WCAP-15628-NP +
 
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