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ML20045B786
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Category
Pages with broken file links, INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML20045B786  +
Atomic Element
Lead +  and Magnesium +
CFR
10 CFR 50 +, 10 CFR 50 Appendix B +  and 10 CFR 50.59 +
Committee
Advisory Committee on Reactor Safeguards +
Docket
05000155  +  and 00155  +
From
Taylor J +  and NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) +
Generic letter
NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +
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>.
ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +, ML20045B786 +  and ML20045B786 +
IP
TI 2515/109 +
Issue date
June 8, 1993  +
Letter
ML20042G674 +  and ML20035G832 +
Manufacturer
Westinghouse +, Limitorque +  and General Electric +
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17:08:43, 19 December 2024  +
NUREG
NUREG/CR-1275 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +
Page count
4  +
Procedure
TST +
Site
Big Rock Point +
Start date
June 8, 1993  +
State
Washington +
System
Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +  and Safety Relief Valve +
Title
Discusses NRC Review of Provisions of Generic Ltr 89-10, Safety-Related MOV Testing & Surveillance & Suppls to Confirm Ability of Valves to Close Under Pipe Break Conditions  +
To
Wilkins J +  and Advisory Committee on Reactor Safeguards +
Topic
Stroke time +  and Overthrust +
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http://pbadupws.nrc.gov/docs/ML2004/ML20045B786.pdf  +
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