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ML102100259
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Category
Report  and Technical
ANSI code
ANSI B16.1 +
ASCE
ASCE 4-98 +
ASME section
ASME Section III +
Accession number
ML102100259  +
Atomic Element
Iron +, Carbon +, Oxygen +  and Hydrogen +
Cross cutting aspect
S.2(s) +  and S.1(s) +
Docket
05000282  +  and 05000306  +
From
Xcel Energy +  and J.D. Stevenson & Associates +
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>.
ML102100259 +, ML102100259 +, ML102100259 +, ML102100259 +, ML102100259 +, ML102100259 +, ML102100259 +, ML102100259 +  and ML102100259 +
Issue date
June 30, 2010  +
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08:49:39, 14 January 2025  +
NUREG
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
84  +
Procedure
TP +, CP-8 +, CP-3 +, CP-7 +, CP-1 +, CP-4 +, CP-5 +, CP-2 +, CP-9 +, CP-6 +, CP-12 +, CP-10 +, CP-11 +, SP-58 +  and CP-52-1 +
Regulatory Guide
Regulatory Guide 1.208 +
SSC
03Q0418-C-002 +, 03Q0418-C-003 +, 09Q4836-CAL-001 +, 10C3877-REP-001 +, 10C3877-BOS-CAL-002 +, 10C3877-BOS-CAL-006 +, 10C3877-BOS-CAL-001 +, 10C3877-BOS-CAL-004 +, 10C3877-BOS-CAL-005 +, 03P-XI-1 +, 01P-III-1 +, 01P-VIII-1 +, 01P-VIII-2 +, 01P-VIII-4 +, 01P-VIII-3 +, 18-2CL-9 +, 16-2CL-9 +, 24-2CL-56 +, 14-2CL-56 +, 16-2CL-09 +, 01P-II-1 +, 01P-VIII-5 +, 01P-VIII-7 +, 01P-VIII-6 +, 12-2CL-56 +, 24-2CL-24 +, 18-2CD-2 +, 2CP-52-1 +, 10C3877-CLE-CAL-036 +, 10C3877-BOS-CAL-003 +...
Site
Prairie Island +
Start date
June 30, 2010  +
State
Idaho +
System
Steam Generator +, Feedwater +, Service water +, Auxiliary Feedwater +, HVAC +  and Main Steam Line +
Title
Seismic Fragilities for Unit 1 and Unit 2 Turbine Building Piping and Equipment  +
To
NRC/RGN-III/DRMA +
Topic
Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Design basis earthquake +  and Earthquake +
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http://pbadupws.nrc.gov/docs/ML1021/ML102100259.pdf  +
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