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ML20247L107
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Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
ASME section
ASME Section XI +
Accession number
ML20247L107  +
CFR
10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.2 +, 10 CFR 50.55a +  and 10 CFR 50.55a#g6 +
Docket
05000364  +  and 00364  +
From
Office of Nuclear Reactor Regulation +  and Reeves E +
General design criterion
GDC 1, Quality standards and records +
Generic letter
NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +
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>.
ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +, ML20247L107 +...
Hours
0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +
Issue date
March 31, 1989  +
Letter
ML20154E847 +
Manufacturer
Limitorque +
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>.
00:59:21, 2 December 2024  +
NRC bulletin
NRC Bulletin 88-04 +  and NRC Bulletin 85-03 +
Page count
16  +
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.
ML20247L107 +
Project
TAC:71579 +
Project reference
TAC:71579 +
Project stage
Other  +
SSC
P001A-A +, P001C-AB +, P001E-B +, P001A-B +, P001C-A +, P001B-AB +, Q2E21-RV-10 +, Q2N23-RV-1 +, Q2E21-RV-13 +, Q2E11-RV-3 +, Q2E11-RV-7 +, Q2E21-RV-12 +, Q2E13-RV-3 +, Q2E11-RV-5 +, Q2E21-RV +  and Q2P16-RV-4 +
Site
Farley +
Start date
March 31, 1989  +
State
Georgia +, Washington +, Alabama +  and Idaho +
System
Reactor Coolant System +, Feedwater +, Service water +, Reactor Recirculation Pump +, Control Rod +  and Main Steam +
Title
Discusses Interim Approval of Inservice Testing & Insp Program for Pumps & Valves.Program Inconsistencies Identified in Review Listed on Encl.Interim Approval Granted  +
To
Southern Nuclear +  and Mcdonald R +
Topic
Boric Acid +, Stroke time +, Scram Discharge Volume +  and Power Operated Valves +
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http://pbadupws.nrc.gov/docs/ML2024/ML20247L107.pdf  +
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