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ML18113A590
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Category
INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE
Accession number
ML18113A590  +
Atomic Element
Boron +, Iodine +, Carbon +, Sodium +, Chloride +  and Chromium +
CFR
10 CFR 20 +, 10 CFR 50.46 +  and 10 CFR 50 +
Docket
05000280  +, 05000281  +, 00280  +  and 00281  +
Equipment trip
Reactor Trip +  and Turbine Trip +
From
Schwencer A +  and Office of Nuclear Reactor Regulation +
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>.
ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +, ML18113A590 +  and ML18113A590 +
Isotope
Tritium +  and Co-60 +
Issue date
October 27, 1978  +
Letter
ML19093A973 +  and ML20031F102 +
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>.
04:43:11, 6 January 2025  +
NUREG
NUREG/CR-0199, Forwards NUREG/CR-0199, Radiological Assessment of Steam Generator Removal & Replacement, in Response to . Util Has Made No Request to Replace Steam Generators.W/O Encl +  and NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +
Page count
44  +
Regulatory Guide
Regulatory Guide 1.70 +
Site
Surry +
Site license
Surry +
Start date
October 27, 1978  +
State
Virginia +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Residual Heat Removal +, Main Steam Line +, Control Rod +  and Main Steam +
Title
Forwards Draft Safety Evaluation Re Steam Generator Prog (ANO:7812140180), & Copy of Radiological Assessment of Steam Generator Removal & Replacement (ANO:7812140185)  +
To
Quittschreiber +  and Advisory Committee on Reactor Safeguards +
Topic
Safe Shutdown +, Shutdown Margin +, Hydrostatic +, Nondestructive Examination +, Emergency Lighting +, Stress corrosion cracking +, Fire Protection Program +, Fire Watch +, Scaffolding +  and Flow Induced Vibration +
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http://pbadupws.nrc.gov/docs/ML1811/ML18113A590.pdf  +
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