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ML15320A287
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Category
E-Mail
ASCE
ASCE 7-10 +
ASME section
ASME Section III +
Accession number
ML15320A287  +
Agency
American Society of Civil Engineers +
Atomic Element
Lead +
Correspondence
NRC 50 +
Cross cutting aspect
H.6(f) +, H.2(s) +, H.2(e) +  and H.5(o) +
EPRI
EPRI +
From
Nicholas Difrancesco +  and Japan Lessons-Learned Division +
Generic letter
NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +
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>.
ML15320A287 +, ML15320A287 +, ML15320A287 +, ML15320A287 +, ML15320A287 +, ML15320A287 +, ML15320A287 +  and ML15320A287 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +
Issue date
November 13, 2015  +
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>.
11:28:37, 10 January 2025  +
NEI
NEI 12-01, Response to March 12, 2012, Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency +  and NEI 12-06, Ne 12-06, Appendix H, Revision 2, H.4.3 Path 3: GMRS ≫ SSE ≪ IHS, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information +
NRC
NRC 50 +
NUREG
NUREG-0544, Forwards Revised Draft NUREG-0544,Rev 4, NRC Collection of Abbreviations. Requests Comments & Concurrence by 970930 +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG-1488, Notice of Draft NUREG 1488, Revised Livermore Seismic Hazard Estimates for 69 Nuclear Power Plant Sites East of Rocky Mountains +  and 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 +
Page count
14  +
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.
ML15320A287 +
Start date
November 13, 2015  +
System
Steam Generator +, Reactor Coolant System +, Automatic Depressurization System +  and Control Rod +
Title
NRR E-mail Capture - NRC Staff Comments on NEI 12-06 Appendix H Paths 1, 2, and 3  +
To
Nuclear Energy Institute +  and Mauer A +
Topic
Safe Shutdown +, Ultimate heat sink +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operator Manual Action +, FLEX +, Fukushima Dai-Ichi +, Design basis earthquake +  and Earthquake +
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http://pbadupws.nrc.gov/docs/ML1532/ML15320A287.pdf  +
 
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