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NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals
Show incoming properties 
Category
Report  and Technical
ASME code
IWB-3500 +, IWB-35 +  and IWB-25 +
ASME section
ASME Section XI +
Accession number
ML15226A229  +
Atomic Element
Nitrogen +, Oxygen +, Molybdenum +, Zirconium +, Lead +  and Helium +
CFR
10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 50.5 +, 10 CFR 54.4 +, 10 CFR 54.2 +, 10 CFR 50.55a +, 10 CFR 54.4#a +, 10 CFR 54.4#a1 +, 10 CFR 54.4#a1i +  and 10 CFR 54.21#a1 +
Correspondence
NL-15-1507, Units 1 and 2 - License Renewal Commitment Item 6 +
Docket
05000348  +  and 00348  +
Document
ML003717179 +
EPRI MRP
MRP-227 +, MRP-228 +, MRP-191 +, MRP-189 +  and MRP-232 +
From
Westinghouse +, Carpenter B T +, Szweda K N +  and Walsh M T +
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>.
NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +, NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +  and NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals +
Hours
0.0116 d (0.278 hours, 0.00165 weeks, 3.805e-4 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +
Issue date
July 31, 2015  +
License amendment topic
License Renewal Application +
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>.
04:41:17, 9 July 2018  +
NEI
NEI 03-08, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) 2019-008, Materials Reliability Program: Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants . +
NL
NL-15-1507, Units 1 and 2 - License Renewal Commitment Item 6 +
NRC bulletin
NRC Bulletin 88-09 +
NUREG
NUREG/CR-45 +, NUREG-1825, Safety Evaluation Report Related to License Renewal of Joseph M. Farley Nuclear Plant, Units 1 & 2 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +
Page count
109  +
Person
None none +
Project stage
Request  +
Regulatory Issue Summary
RIS 2011-07, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000310, NRC Regulatory Issue Summary 2011-07 License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management +
SSC
1WB-2500-1 +, 07-98-003 +  and M1RP-227-A +
Site
Farley +
Start date
July 31, 2015  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Reactor Pressure Vessel +  and Control Rod +
Title
J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals  +
To
Office of Nuclear Reactor Regulation +
Topic
Nondestructive Examination +, Functionality Assessment +, Aging Management +, Stress corrosion cracking +, License Renewal +, EVT-1 +, Liquid penetrant +, DM weld +  and Power Uprate +
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/ML1522/ML15226A229.pdf  +
WCAP
WCAP-17096-NP +, WCAP-14577 +, WCAP-18011-NP +  and WCAP-1801 +
Westinghouse report
WCAP-17096-NP +, WCAP-14577 +, WCAP-18011-NP +  and WCAP-1801 +
 
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