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ML20207F911
Show incoming properties 
Category
Pages with broken file links, CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
Accession number
ML20207F911  +
Atomic Element
Hydrogen +
CFR
10 CFR 50 Appendix J +
Correspondence
L-11 +, L-10 +, L-12 +, L-14 +  and L-17 +
Docket
05000271  +, 00271  +, 00154  +, 00155  +, 00868  +  and 00498  +
Drawing
SE-70-4C +, SE-70-2B +  and SE-70-2A +
From
Office of Nuclear Reactor Regulation +  and Rooney V +
General design criterion
GDC 54 +
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>.
ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +, ML20207F911 +  and ML20207F911 +
Isotope
H-3 +
Issue date
January 5, 1987  +
L
L-11 +, L-10 +, L-12 +, L-14 +  and L-17 +
Letter
FVY-84-139, Forwards Info Supporting 790130 Application to Amend License DPR-28,consisting of Proposed Change 77 to Tech Specs to Allow Exemption from Inservice Insp Program Code (ASME Section Xi).Revised Inservice Insp Program Encl.Fee Paid +
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>.
02:32:51, 7 December 2024  +
Page count
23  +
SSC
70-1A-D +
Site
Vermont Yankee +
Start date
January 5, 1987  +
State
Pennsylvania +, Washington +, Massachusetts +  and Vermont +
System
Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Safety Relief Valve +  and Control Rod +
Title
Forwards Request for Addl Info Re Proposed Inservice Testing Program for Pumps & Valves Submitted w/841127 Ltr,Including Discussion of safety-related Functions of HPCI Pumps.Meeting Recommended  +
To
VERMONT YANKEE NUCLEAR POWER CORP. +  and Capstick R +
Topic
Stroke time +, Excess Flow Check Valve +  and Power Operated Valves +
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http://pbadupws.nrc.gov/docs/ML2020/ML20207F911.pdf  +
 
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