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ML19346A195
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC
ANSI code
ANSI N18.2 +
Accession number
ML19346A195  +
Atomic Element
Lead +
CFR
10 CFR 100 +  and 10 CFR 50 +
Cross cutting aspect
S.0(e) +  and P.3(o) +
Docket
05000482  +, 05000483  +, 05000486  +, 00482  +, 00483  +  and 00486  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
Petrick N +  and STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM +
General design criterion
GDC 34 +, GDC 2, Design bases for protection against natural phenomena +, GDC 3, Fire protection +  and GDC 5, Sharing of structures, systems, and components +
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>.
ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +, ML19346A195 +  and ML19346A195 +
Hours
1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +
Issue date
June 3, 1981  +
Manufacturer
Westinghouse +
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>.
11:56:59, 24 December 2024  +
NRC bulletin
NRC Bulletin 79-13, Cracking in Feedwater System Piping +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +  and NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +
Page count
41  +
Procedure
RT +  and SP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.26 +, Regulatory Guide 1.29 +  and Regulatory Guide 1.32 +
SSC
1B-1 +
Site
Wolf Creek +  and Callaway +
Start date
June 3, 1981  +
State
Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Residual Heat Removal +, Main Steam Safety Valve +, Decay Heat Removal +, Main Steam Line +  and Main Steam +
Title
Forwards Draft Revisions to FSAR Re Auxiliary Feedwater Sys. Response to on Flow Requirements for Auxiliary Feedwater Sys Provided.Reliability Study of Subj Sys to Be Submitted Under Separate Cover  +
To
Office of Nuclear Reactor Regulation +  and Harold Denton +
Topic
Safe Shutdown +, Loss of Offsite Power +, Earthquake +, Loss of condenser vacuum +  and Water hammer +
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http://pbadupws.nrc.gov/docs/ML1934/ML19346A195.pdf  +
 
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