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ML17255A392
Show incoming properties
Category
NRC TECHNICAL REPORT, NUREG REPORTS  and TEXT-SAFETY REPORT
Accession number
ML17255A392  +
Atomic Element
Sodium +
CFR
10 CFR 50 +, 10 CFR 50.48#d +, 10 CFR 50.71#e3ii +  and 10 CFR 50.71#e3 +
Docket
00244  +  and 05000244  +
Equipment trip
Reactor Trip +
From
Office of Nuclear Reactor Regulation +
General design criterion
GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +
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>.
ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +, ML17255A392 +  and ML17255A392 +
Issue date
August 31, 1983  +
Letter
ML17255A268 +  and ML17256A649 +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
16:07:12, 8 January 2025  +
NRC form
NRC Form 335 +
NUREG
NUREG-4821 +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant +  and NUREG-821 +
Page count
50  +
Person
None none +
Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.
ML17255A392 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.70 +, Regulatory Guide 1.26 +, Regulatory Guide 1.59 +  and Regulatory Guide 1.46 +
SSC
12la-Look +
Site
Ginna +
Start date
August 31, 1983  +
State
New York +  and Washington +
System
Steam Generator +, Feedwater +, Service water +, Auxiliary Feedwater +, Shutdown Cooling +, Residual Heat Removal +, Main Steam Safety Valve +  and Main Steam +
Task Interface Agreement
TIA 83-24 +
Title
Integrated Plant Safety Assessment Report,Systematic Evaluation Program - R. E. Ginna Nuclear Power Plant.Docket No. 50-244.(Rochester Gas and Electric Corporation)  +
Topic
Safe Shutdown +, Boric Acid +, High winds +, Ultimate heat sink +, Tornado Missile +, Hydrostatic +, Probabilistic Risk Assessment +, High Energy Line Break +, Tornado Missile Protection +, Earthquake +, Pressure Boundary Leakage +, Fire Protection Program +  and Backfit +
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http://pbadupws.nrc.gov/docs/ML1725/ML17255A392.pdf  +
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