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ML25247A295
Show incoming properties 
Category
Letter  and Request for Code Relief or Alternative
ASME code
IWB-3500 +, IWB-2500 +, IWC-1222 +, IWC-2500 +, IWC-3600 +, IWB-3510 +, IWB-2430 +, IWC-3500 +, IWB-2411 +, IWC-2411 +  and IWC-3510 +
ASME section
ASME Section XI +, ASME Section III +  and ASME Section II +
Accession number
ML25247A295  +
Atomic Element
Carbon +
BWRVIP
BWRVIP-108 +  and BWRVIP-241 +
CFR
10 CFR 2.390 +, 10 CFR 50.55a +  and 10 CFR 50.55a#z1 +
Code case
ASME Code Case N-702 +
Correspondence
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles +  and RS-24-024 +
Docket
05000528  +, 05000529  +, 05000530  +, 00528  +, 00529  +, 00530  +, 00369  +, 00370  +, 00455  +, 00282  +  and 00306  +
Document
ML16179A178 +, ML072130487 +, ML101130187 +, ML110691154 +, ML14295A532 +, BYRON 2013-0100, Day Inservice Inspection Report for Interval 3, Period 3, (B2R17) +, ML13016A515 +, ML11279A035 +, ML12228A723 +, HNP-09-095, Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program +, HNP-08-045, Second Ten-Year Interval Inservice Inspection Program-Final Documentation Including Requests for Relief in Accordance with 10 CFR 50.55a +, ML062390020 +, ML011640178 +, L-PI-03-039, Response to Opportunity for Comment on Task Interface Agreement (TIA) 2003-01, Application of ASME Code Section XI, IWB-2430 Requirements Associated with Scope of Volumetric Weld Expansion at the Prairie Island Nuclear Generating Plant +, ML19241A545 +  and ML011550346 +
Drawing
FP-PV-326 +, FP-PV-325 +  and FP-PV-324 +
Equipment trip
Reactor Trip +
From
Spina J +  and Arizona Public Service +
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ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +, ML25247A295 +  and ML25247A295 +
Inspection Manual Chapter
NRC Inspection Manual 9171 +, NRC Inspection Manual 9172 +, NRC Inspection Manual 9173 +, NRC Inspection Manual 9174 +, NRC Inspection Manual 9175 +, NRC Inspection Manual 9176 +, NRC Inspection Manual 9177 +, NRC Inspection Manual 9178 +  and NRC Inspection Manual 9179 +
Issue date
September 4, 2025  +
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>.
20:12:55, 5 October 2025  +
NUREG
NUREG/CR-7278, Technical Basis for the Use of Probabilistic Fracture Mechanics in Regulatory Applications - Final +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +
Page count
1  +
Person
James Kim +
Procedure
AM +
Project reference
TAC:ME3809 +, TAC:MF3527 +, TAC:ME9748 +, TAC:ME7277 +, TAC:ME0608 +, TAC:MD4695 +, TAC:MC8337 +, TAC:MB0603 +, EPID:L-2020-LLR-0097 +, EPID:L-2020-LLR-0109 +, EPID:L-2020-LLR-0103 +, EPID:L-2020-LRR-0103 +, EPID:L-2023-LLR-0062 +  and EPID:L-2023-LLR-0053 +
Project stage
Request  +
RS
RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles +  and RS-24-024 +
Regulatory Guide
Regulatory Guide 1.147 +  and Regulatory Guide 1.245 +
SSC
07-42-115 +, 07-41-100 +, 07-42-104 +, 2R1-018 +, 2R1-019 +, 2R1-020 +, 2R1-021 +, 2R1-022 +, 2R2-009 +, 2R2-010 +, 2R2-011 +, 07-42-110 +, 07-42-100 +, 07-41-103 +, 07-42-103 +  and 07-41-115 +
Site
Palo Verde +
Site license
Palo Verde +  and Harris +
Start date
September 4, 2025  +
State
Connecticut +, Arizona +, Georgia +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Reactor Pressure Vessel +  and Main Steam +
Title
Renewed Operating License No. NPF-41, Relief Request 74 - Proposed Alternative for Steam Generator and Pressurizer Pressure Retaining Welds for PVNGS  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Non-Destructive Examination +, Hydrostatic +, Finite Element Analysis +, Flow Accelerated Corrosion +, Microbiologically influenced corrosion +  and Stress corrosion cracking +
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http://pbadupws.nrc.gov/docs/ML2524/ML25247A295.pdf  +
 
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