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ML25091A301
Show incoming properties 
Category
License-Application for Facility Operating License (Amend/Renewal) DKT 50  and Topical Report
ASME section
ASME Section XI +, ASME Section III +  and ASME Section II +
Accession number
ML25091A301  +
Atomic Element
Boron +, Iron +, Vanadium +, Carbon +  and Manganese +
Code case
ASME Code Case N-830 +
Correspondence
RA-25-0067, Enclosure 3, Attachment 2 - Subsequent License Renewal Application, Appendix E, Environmental Report +
Docket
05000261  +, 00261  +, 00266  +, 00301  +, 00335  +  and 00389  +
Engineering change
EC-0000418725 +
From
Duke Energy +
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>.
ML25091A301 +, ML25091A301 +, ML25091A301 +, ML25091A301 +, ML25091A301 +, ML25091A301 +, ML25091A301 +, ML25091A301 +, ML25091A301 +, ML25091A301 +  and ML25091A301 +
In package
ML25091A290 +
Issue date
April 1, 2025  +
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>.
00:19:48, 11 April 2025  +
NUREG
NUREG-1509 +, NUREG/CR-5320, Summary of 890518 Meeting w/C-E Owners Group Re Reactor Vessel Support Embrittlement Discussed in NUREG/CR-5320, Impact of Radiation Embrittlement on Integrity of Pressure Vessel Supports for Two PWR Plants. Viewgraphs Encl +, NUREG-2191, Draft NUREG-2191 Vol 2 GALL-SLR Rev1 -12-14-24 +, NUREG-1785, (2:2) Page 3-337 - End, Safety Evaluation Report Related to the License Renewal of H. B. Robinson Steam Electric Plant, Unit 2 +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Page count
1  +
Procedure
TOP +
Project reference
EPID:L-2023-LLA-0122 +
Project stage
Other  +
RA
RA-25-0067, Enclosure 3, Attachment 2 - Subsequent License Renewal Application, Appendix E, Environmental Report +
Regulatory Guide
Regulatory Guide 1.190 +
Site
Robinson +
Start date
April 1, 2025  +
State
California +  and Florida +
System
Reactor Pressure Vessel +  and Reactor Coolant System +
Title
Enclosure 4, Attachment 5 - WCAP-18939-NP, H.B. Robinson Unit 2 Subsequent License Renewal: Fracture Mechanics Assessment of Reactor Pressure Vessel Structural Steel Supports, Revision 0, Dated November 2024  +
To
Office of Nuclear Reactor Regulation +
Topic
Boric Acid +, Safe Shutdown Earthquake +, Aging Management +, License Renewal +, Subsequent License Renewal +, Subsequent License Renewal Application +, Earthquake +  and Leak-Before-Break +
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/ML2509/ML25091A301.pdf  +
WCAP
WCAP-14422 +, WCAP-18124-NP-A +, WCAP-18939-NP +  and WCAP-18939-P +
Westinghouse report
WCAP-14422 +, WCAP-18124-NP-A +, WCAP-18939-NP +  and WCAP-18939-P +
 
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