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ML20236L804
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Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
ASME section
ASME Section XI +
Accession number
ML20236L804  +
Atomic Element
Nitrogen +  and Oxygen +
CFR
10 CFR 100 +, 10 CFR 50.55a +, 10 CFR 50.55a#a3i +, 10 CFR 50.55a#f6i +, 10 CFR 50.55a#s3i +  and 10 CFR 50.55a#f6 +
Docket
05000373  +, 05000374  +, 00373  +  and 00374  +
From
NRC (Affiliation Not Assigned) +
Generic letter
NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +  and NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +
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ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +, ML20236L804 +  and ML20236L804 +
Hours
1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
In package
ML20236L795 +
Inspection procedure
IP 73756 +
Issue date
July 6, 1998  +
Letter
ML20249A401 +  and ML20203L824 +
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>.
06:10:37, 3 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.
ML20236L804 +
Project stage
Approval  +
SR
SR-4.6.4.1 +
Site
LaSalle +
Start date
July 6, 1998  +
System
Reactor Core Isolation Cooling +, Primary containment +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +  and Emergency Core Cooling System +
TS
TS-3.6.6.2 +
Title
Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1  +
Topic
Breakaway torque +, Backfit +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML2023/ML20236L804.pdf  +
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