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ML15252A442
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Category
Legal-Pre-Filed Exhibits
ASME section
ASME Section III +  and ASME Section XI +
Accession number
ML15252A442  +
Agency
American Society of Civil Engineers +
Atomic Element
Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Molybdenum +, Lead +, Titanium +, Gold +, Manganese +, Chromium +, Niobium +  and Tungsten +
CFR
10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix S, General Information +, 10 CFR 100.23 +, 10 CFR 100 Appendix A +, 10 CFR 50.55a +, 10 CFR 50.55a#b4 +, 10 CFR 50.55a#d +, 10 CFR 50.55a#a1i +  and 10 CFR 50 Appendix J#67 +
Contact
SECY RAS +
Docket
05000247  +, 05000286  +  and 00100  +
Document
ML13207A044 +, ML13207A045 +, ML13203A235 +  and ML13203A236 +
ENS
ENS 1 +  and ENS 52 +
EPRI
EPRI +
EPRI MRP
MRP-175 +  and MRP-160 +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
New York +  and Office of the Attorney General +
General design criterion
GDC 1, Quality standards and records +
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ML15252A442 +, ML15252A442 +, ML15252A442 +, ML15252A442 +, ML15252A442 +, ML15252A442 +, ML15252A442 +, ML15252A442 +, ML15252A442 +  and ML15252A442 +
Issue date
June 30, 2015  +
Manufacturer
Westinghouse +  and General Electric +
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>.
13:33:19, 10 January 2025  +
NRC information notice
Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head +  and Information Notice 2001-05, Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station Unit 3 +
NUREG
NUREG/CR-5704 +, NUREG/CR-6583 +, NUREG/CR-4513 +, NUREG/CR-7027 +, NUREG/CR-6923 +, NUREG/CR-6428 +, NUREG/CR-6960 +, NUREG/CR-7185 +, NUREG/CR-2827 +, NUREG/CR-6983 +, NUREG/CR-7015 +, NUREG/CR-5013 +, NUREG/CR-6787 +, NUREG/CR-4667 +, NUREG/CR-5142 +, NUREG/CR-6098 +, NUREG-1557, Technical Info from Industry Repts Addressing License Renewal, Presented at 970817-22 14th Intl Conference on Structural Mechanics in Reactor Technology in Lyon,France +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-1344, Advises That Util 890710 Response to Generic Ltr 89-08 Re Pipe Wall Thinning Induced by Erosion &/Or Corrosion Acceptable,Based on Confirmation That Erosion/Corrosion Program Meets or Exceeds App a to NUREG-1344 Requirements +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +
Page count
149  +
Person
Appajosula Rao +
Procedure
RT +  and CP +
Project stage
Request  +
RAS
RAS 28270 +
Regulatory Guide
Regulatory Guide 1.84 +, Regulatory Guide 1.26 +, Regulatory Guide 1.65 +, Regulatory Guide 1.29 +, Regulatory Guide 1.60 +, Regulatory Guide 1.92 +, Regulatory Guide 1.61 +, Regulatory Guide 1.122 +, Regulatory Guide 1.208 +, Regulatory Guide 1.193 +, Regulatory Guide 1.165 +  and Regulatory Guide 1.193.92 +
SSC
1x10-3 +, 07-95-106 +, 1T-CT +, 07-91-111 +, 07-93-107 +, A8W-110 +, A8W-107 +  and A8W-108 +
Site
Indian Point +
Start date
June 30, 2015  +
State
Texas +, Illinois +, Washington +, California +, New York +, Arkansas +, Vermont +  and Alaska +
System
Reactor Coolant System +, Feedwater +, Reactor Pressure Vessel +  and Control Rod +
Title
NYS000565 - Technical Letter Report on Literature Review and Assessment of Potential Seismic Effects on Ongoing Material Degradation � Tensile Strength, Fracture Toughness and Physical Properties (Published June 2015)  +
To
Atomic Safety and Licensing Board Panel +
Topic
Safe Shutdown +, Boric Acid +, Safe Shutdown Earthquake +, Hydrostatic +, Operating Basis Earthquake +, Incorporated by reference +, Aging Management +, Design basis earthquake +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, License Renewal +, Earthquake +, Thermal fatigue +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1525/ML15252A442.pdf  +
WCAP
WCAP-7414 +
Westinghouse report
WCAP-7414 +
 
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