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ML18033A816
Show incoming properties 
Category
CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE
ANSI code
ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +
ASME code
IWA-2400 +
Accession number
ML18033A816  +
Act
Atomic Energy Act of 1954 +
Atomic Element
Boron +, Hydrogen +, Chloride +, Lead +  and Tin +
CFR
10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.55 +, 10 CFR 2 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50 Appendix H +, 10 CFR 50 Appendix I +, 10 CFR 51.22 +, 10 CFR 2.714 +, 10 CFR 2.714#a1i +, 10 CFR 5092#c +, 10 CFR 5122#b +, 10 CFR 50.55a +, 10 CFR 50.54#a3 +, 10 CFR 5#D +, 10 CFR 5#O +, 10 CFR 50.36#c5 +, 10 CFR 50.91#a +, 10 CFR 51.12#b +, 10 CFR 50.55a#g +, 10 CFR 51.22#b +, 10 CFR 73.40#d +, 10 CFR 50.92#c +...
CR
LO-LAR-88-00008 +, LO-LAR-89-00043 +  and LO-LAR-89-00046 +
Cross cutting aspect
S.2(c) +
Docket
05000260  +, 00260  +, 00328  +, 00325  +, 00324  +, 00213  +, 00223  +, 00255  +, 00334  +, 00321  +, 00366  +, 00220  +, 00423  +, 00275  +, 00323  +, 00276  +, 00286  +, 00354  +, 00272  +, 00311  +, 00208  +, 00415  +, 00327  +, 00305  +, 00315  +, 00313  +, 00247  +, 00155  +, 00414  +, 00370  +...
Equipment trip
Reactor Trip +
FR
51 FR 7744 +, 51 FR 7751 +, 54 FR 13763 +, 54 FR 9926 +, 54 FR 7633 +, 54 FR 13770 +, 54 FR 20659 +, 54 FR 15851 +, 54 FR 11599 +, 50 FR 29016 +, 50 FR 20373 +, 53 FR 32295 +, 54 FR 7630 +, 54 FR 6206 +, 54 FR 21297 +, 51 FR 41864 +, 54 FR 11841 +, 54 FR 5176 +, 54 FR 6207 +, 51 FR 29014 +, 54 FR 18055 +, 53 FR 20045 +, 54 FR 13767 +, 53 FR 50333 +, 54 FR 13768 +, 50 FR 20976 +, 54 FR 18369 +, 54 FR 18951 +, 54 FR 18372 +, 54 FR 18366 +...
From
Black S +  and Office of Nuclear Reactor Regulation +
Generic letter
NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 84-13, Technical Specification for Snubbers +, NRC Generic Letter 85-16, High Boron Concentrations +, NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +  and NRC Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications +
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>.
ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +, ML18033A816 +...
Hours
0.00152 d (0.0364 hours, 2.166005e-4 weeks, 4.98455e-5 months)  +, 0.00201 d (0.0483 hours, 2.876984e-4 weeks, 6.6207e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +  and 9.027778e-4 d (0.0217 hours, 1.289683e-4 weeks, 2.9679e-5 months)  +
Isotope
Tritium +  and Cesium-137 +
Issue date
June 28, 1989  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
07:03:33, 7 January 2025  +
NRC form
NRC Form 318 +
NUREG
NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +  and NUREG-4313 +
Page count
41  +
Power source
4V +
Procedure
TP +
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.
ML18033A816 +
Project
TAC:71631 +, TAC:62260 +, TAC:52901 +  and TAC:61049 +
Project reference
TAC:71631 +, TAC:62260 +, TAC:52901 +  and TAC:61049 +
Project stage
Other  +
Regulatory Guide
Regulatory Guide 1.93 +  and Regulatory Guide 1.155 +
SR
SR-4.2.7.c +, SR-4.7.1.2.a +, SR-4.6.2 +, SR-4.6.1.2.a +, SR-4.2.7.d +  and SR-4.6.12.a +
SSC
07-56-263 +  and 07-58-272 +
Site
Browns Ferry +
Site license
Peach Bottom +, Salem +, Palisades +, Sequoyah +, Susquehanna +, Surry +, North Anna +, Diablo Canyon +, San Onofre +, NPF-6 +, NPF-52 +, NPF-35 +, DPR-24 +  and DPR-27 +
Start date
June 28, 1989  +
State
Tennessee +, Pennsylvania +, Connecticut +, Georgia +, Minnesota +, Maryland +, North Carolina +, Washington +, California +, Alabama +, Virginia +, New Jersey +, South Carolina +, New York +, Michigan +, Wisconsin +, Florida +, Louisiana +, Missouri +, Indiana +, Mississippi +, Nebraska +  and Arkansas +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Residual Heat Removal +, Standby Gas Treatment System +, Shield Building +, Main Steam Safety Valve +, Intermediate Range Monitor +, Remote shutdown +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Rod +  and Main Steam +
TS
TS-3.5.1 +, TS-3.0.1 +, TS-3.8.3.1 +, TS-3.6 +, TS-3.4 +, TS-3.1.7 +, TS-3.3.3.1 +, TS-3.3.1 +, TS-6.2.2 +, TS-4.3.1.1 +, TS-3.2.B +, TS-4.6.1.2 +, TS-4.7.E +, TS-2.3.1.B +, TS-3.7.12.2 +, TS-6.1.2 +, TS-3.1.G +, TS-6.2.1 +, TS-6.1.1 +, TS-3.4.A +, TS-3.8.B +, TS-4.6.F +, TS-4.5.2.h +, TS-4.7.2.d +, TS-3.17.1 +  and TS-3.4.4.2 +
Title
Forwards List of Submittals Required of Util to Support NRC Decisions Re Restart.Util Will Be Apprised of Need for Addl Info to Resolve Technical Issues If Submittals Incomplete  +
To
Kingsley O +  and Tennessee Valley Authority +
Topic
Safe Shutdown +, Shutdown Margin +, Grab sample +, High Energy Line Break +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Integrated leak rate test +, Exemption Request +, Fire Protection Program +  and Control Room Habitability +
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/ML1803/ML18033A816.pdf  +
WCAP
WCAP-10263 +  and WCAP-12058 +
Westinghouse report
WCAP-10263 +  and WCAP-12058 +
 
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