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ML20211F428
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Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
ASME code
IWB-3500 +, IWB-2500 +  and IWB-1220 +
ASME section
ASME Section XI +
Accession number
ML20211F428  +
Atomic Element
Carbon +, Chloride +  and Lead +
CFR
10 CFR 50 +, 10 CFR 50.55a +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#a3 +  and 10 CFR 50.55a#g6 +
Code case
ASME Code Case N-560 +  and ASME Code Case N-500 +
Cornerstone
Initiating Events +  and Mitigating Systems +
Docket
05000313  +  and 00313  +
Equipment trip
Reactor Trip +
From
NRC (Affiliation Not Assigned) +
Generic letter
NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
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>.
ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +, ML20211F428 +  and ML20211F428 +
In package
ML20211F425 +
Issue date
August 25, 1999  +
Letter
1CAN069804, Submits Results of Pilot Plant Application Study Performed at Unit 1 for NRC Review.Submittal Provides Pilot Application Based on ASME Code Case N-560.Calculations NSD-024 & EPRI-116-310 & Rept SIR-98-055,encl +  and 1CAN059902, Responds to NRC 990406 RAI Re risk-informed Inservice Insp Pilot Application,Submitted 980603.Approval of Alternative Is Requested Prior to End of July 1999,to Allow Sufficient Time for Util to Revise ANO-1 ISI Program +
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04:31:53, 6 December 2024  +
Page count
18  +
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ML20211F428 +
Project stage
Approval  +
Regulatory Guide
Regulatory Guide 1.174 +  and Regulatory Guide 1.147 +
Site
Arkansas Nuclear +
Start date
August 25, 1999  +
State
Washington +  and Arkansas +
System
Reactor Coolant System +, Feedwater +, Emergency Core Cooling System +  and Decay Heat Removal +
Title
Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety  +
Topic
Probabilistic Risk Assessment +, Nondestructive Examination +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Large early release frequency +, Stress corrosion cracking +, Loss of Offsite Power +, Dissimilar Metal Weld +, Thermal fatigue +  and Leak-Before-Break +
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http://pbadupws.nrc.gov/docs/ML2021/ML20211F428.pdf  +
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