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ML18155A450
Show incoming properties
Category
Updated Final Safety Analysis Report (UFSAR)
ASME section
ASME Section III +, ASME Section I +  and ASME Section VIII +
Accession number
ML18155A450  +
Atomic Element
Boron +, Iodine +, Nickel +, Copper +, Nitrogen +, Carbon +, Sodium +, Hydrogen +, Chloride +  and Lead +
CFR
10 CFR 50.67 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +  and 10 CFR 50.72#b2ii +
Code case
ASME Code Case N-10 +
Cross cutting aspect
S.6(f) +
Docket
05000282  +  and 05000306  +
Document
ML16133A406 +, ML13084A154 +, ML112521289 +  and ML15062A301 +
Engineering change
EC-21790 +, EC-13483 +, EC-378 +, EC-25820 +, EC-21789 +, EC-25792 +, EC-7948 +, EC-12083 +, EC-24942 +, EC-16940 +, EC-14787 +, EC-16381 +, EC-16722 +, EC-18252 +, EC-24804 +, EC-17508 +, EC-16022 +, EC-18437 +, EC-16220 +, EC-18839 +, EC-14086 +, EC-10931 +, EC-17225 +, EC-18516 +, EC-22880 +, EC-24126 +, EC-7645 +  and EC-12474 +
From
Minnesota +  and Xcel Energy +
General design criterion
GDC 38 +, GDC 41 +, GDC 44 +, GDC 61 +, GDC 60 +, GDC 30 +, GDC 46 +, GDC 45 +, GDC 40 +, GDC 37 +, GDC 42 +, GDC 43 +, GDC 52 +, GDC 48 +, GDC 47 +, GDC 58 +, GDC 59 +  and GDC 4, Environmental and dynamic effects design bases +
Generic letter
NRC Generic Letter 04-02 +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +  and NRC Generic Letter 08-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems +
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>.
ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +, ML18155A450 +  and ML18155A450 +
Hours
3.125e-4 d (0.0075 hours, 4.464286e-5 weeks, 1.02735e-5 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +  and 4.050926e-4 d (0.00972 hours, 5.787037e-5 weeks, 1.33175e-5 months)  +
IEEE
IEEE 279-1971 +  and IEEE 279-1968 +
In package
ML18155A439 +
Isotope
Cobalt-60 +
Issue date
May 18, 2018  +
License amendment topic
Alternate Source Term +
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>.
23:35:48, 5 January 2025  +
NEI
NEI 02-01 +, NEI 09-10 +  and NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +
NRC bulletin
NRC Bulletin 88-04 +
NUREG
NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
157  +
Procedure
SP +, TOP +, TP-304 +, SP-66 +, JF +  and SP-61 +
Project reference
CAC:MF6449 +, TAC:ME2976 +  and TAC:ME2609 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.183 +  and Regulatory Guide 1.45 +
SSC
1a-A +, 2R-11 +, 1R-11 +, 2CS-33-6 +, 2SI-14-2 +, 2CA-11-1 +, 2CA-4-2 +, 2R-10 +, 1R-10 +, 2SI-14-1 +, 1s1-r41 +, 1s1-15-BI +, 1s1-r21 +, 1s1-15-7I +, 11-2PJ-15 +, 1s1-2 +, 1s1-20-J2I +, 12s1-199 +, 2SI-199 +, 12s1-I45-3 +, 12-2s1-29A +, 2HCV-945 +, 12s1-22-11 +, 12-25l-27A +, 2S1-35-13 +, 12S1-145-6 +, L2SI-20-52f +, 12-25l-28B +, 2s1-20-27 +, 2SI-35-17 +...
Site
Prairie Island +
Start date
May 18, 2018  +
State
Minnesota +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Reactor Building Ventilation +, Residual Heat Removal +, Shield Building +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +
TSTF
TSTF-523 +
Title
Updated Safety Analysis Report (USAR) Revision 35, Section 6, Engineered Safety Features  +
To
Office of Nuclear Reactor Regulation +
Topic
Safe Shutdown +, Boric Acid +, Mission time +, Internal Flooding +, Hydrostatic +, Coatings +, Foreign Material Exclusion +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Liquid penetrant +, GOTHIC +, Unidentified leakage +, Eddy Current Test +, Water hammer +, Gas accumulation +  and Leak-Before-Break +
Training curricula
F-23-1 +, J-20-281 +, F-22-lf-I +, F-23-ll +, F-22-l +, F-23-3I +, F-21-11 +, F-133-l +  and F-18-l +
URL"URL" is a <a href="/Special:Types/URL" title="Special:Types/URL">type</a> and predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> to represent URI/URL values.
http://pbadupws.nrc.gov/docs/ML1815/ML18155A450.pdf  +
WCAP
WCAP-7829 +, WCAP-7744 +, WCAP-7503 +, WCAP-16793-NP +, WCAP-7607 +, WCAP-16793-NP-A +, WCAP-9003 +, WCAP-16406 +  and WCAP-11925 +
Westinghouse report
WCAP-7829 +, WCAP-7744 +, WCAP-7503 +, WCAP-16793-NP +, WCAP-7607 +, WCAP-16793-NP-A +, WCAP-9003 +, WCAP-16406 +  and WCAP-11925 +
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