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ML20154S009
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ASME section
ASME Section II +
Accession number
ML20154S009  +
Atomic Element
Boron +, Oxygen +, Hydrogen +, Chloride +, Lead +, Gold +  and Tin +
Correspondence
L 40 +
Cross cutting aspect
P.4(c) +
Docket
05000498  +, 05000499  +, 00498  +  and 00499  +
From
Wisenburg M +  and Creating Houston Lighting and Power Company +
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>.
ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +, ML20154S009 +  and ML20154S009 +
Issue date
March 26, 1986  +
L
L 40 +
Letter
ML20266C523 +  and ST-HL-AE-1055, Final Deficiency Rept Re Reactor Vessel Core Support Tolerance.Initially Reported on 830726.Evaluations Disclosed That out-of-levelness Condition on Reactor Vessel Support Ledge Not Reportable Per 10CFR50.55(e) +
Manufacturer
Westinghouse +
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03:51:05, 11 December 2024  +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
48  +
Procedure
ST +, SP +, ST-HL +, ST.HL +, ST-HL-AE +, ST.HL-AE +  and ST.HL4AOF +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.97 +  and Regulatory Guide 1.23 +
SSC
7s-2T +
Site
South Texas +
Start date
March 26, 1986  +
State
Texas +  and Washington +
System
Steam Generator +, Feedwater +, Auxiliary Feedwater +, Main Steam Safety Valve +, Emergency Core Cooling System +, Safety Relief Valve +  and Containment Spray +
TS
TS-3.5.1 +
Title
Forwards Response to 860224 Request for Addl Info Re Conformance to Reg Guide 1.97 Concerning Emergency Response Capability.Meeting During Apr 1986 Suggested to Answer Remaining Questions.Revised FSAR Pages Also Encl  +
To
Office of Nuclear Reactor Regulation +  and Noonan V +
Topic
Boric Acid +, Grab sample +, Post Accident Monitoring +  and Main Steam Line Radiation Monitor +
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http://pbadupws.nrc.gov/docs/ML2015/ML20154S009.pdf  +
 
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