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ML20210D916
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Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
ASME section
ASME Section XI +
Accession number
ML20210D916  +
CFR
10 CFR 100 +, 10 CFR 50 Appendix J +, 10 CFR 50.55a +  and 10 CFR 50.55a#a3i +
Docket
05000498  +, 05000499  +, 00498  +  and 00499  +
From
NRC (Affiliation Not Assigned) +
Generic letter
NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +
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ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +, ML20210D916 +  and ML20210D916 +
In package
ML20210D907 +
Issue date
July 23, 1999  +
Letter
ML20077A998 +, ML20151T606 +, ML20204B256 +, ML20238F084 +, NOC-AE-00338, Requests Relief from ASME Section XI Code Requirement to Testing of Component Cooling Water & Safety Injection Check Valces for Closure Exercise to Same Frequency as 10CFR50 App J,Option B Frequency +  and ST-HL-AE-4193, Forwards Vols 1 & 2 of Level 2 PRA & IPE, in Response to Generic Ltr 88-20,Suppls 1,2,3 & 4 +
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21:35:10, 6 December 2024  +
NUREG
NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report +
Page count
9  +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML20210D916 +
Project stage
Approval  +
Regulatory Guide
Regulatory Guide 1.174 +, Regulatory Guide 1.163 +  and Regulatory Guide 1.175 +
SR
SR-4.0.5 +
Site
South Texas +
Start date
July 23, 1999  +
State
Washington +  and Texas +
System
Reactor Coolant System +, Residual Heat Removal +  and Decay Heat Removal +
Title
Safety Evaluation Accepting Inservice Testing Relief Request RR-56 Re Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency  +
Topic
Enforcement Discretion +, Probabilistic Risk Assessment +, Incorporated by reference +, Foreign Material Exclusion +  and Large early release frequency +
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http://pbadupws.nrc.gov/docs/ML2021/ML20210D916.pdf  +
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