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ML20101A150
Show incoming properties 
Category
SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT
Accession number
ML20101A150  +
Atomic Element
Boron +, Carbon +, Sodium +  and Lead +
CFR
10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.36#c3 +, 10 CFR 51.22#b +  and 10 CFR 50 Appendix J#60 +
Docket
05000341  +  and 00341  +
Equipment trip
Turbine Trip +
FR
60 FR 58400 +
From
NRC (Affiliation Not Assigned) +
General design criterion
GDC 54 +
Generic letter
NRC Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle +
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>.
ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +, ML20101A150 +  and ML20101A150 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +
In package
ML20101A139 +
Issue date
March 1, 1996  +
Letter
NRC-95-0139, Responds to Informal Request for Info Re Use of Historical Plant Drift Data in Calculating Nominal Trip Setpoints for Extended Surveillance Intervals +, ML20095G577 +, ML20092L176 +  and NRC-95-0083, Requests one-time Exemption from 10CFR50,App J,Paragraphs III.D.2.a & III.D.3,which Require,In Part,Type B & C Tests to Be Performed at Intervals No Greater than 2 Yrs,To Allow 25% Extension to 2 Yr Testing Interval +
Licensing Basis Document
Updated Final Safety Analysis Report +
Manufacturer
Target Rock +  and General Electric +
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>.
10:17:42, 13 December 2024  +
NUREG
NUREG-0991, Advises That Rev 1 to Plant Preservice Insp Program for Reactor Coolant Pressure Boundary & for ASME Code Class 2 & 3 Sys & Components Acceptable & in Compliance W/ 10CFR50.55a(g)(2).Evaluation Included in NUREG-0991,Suppl 7 +
Page count
37  +
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.
ML20101A150 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.118 +  and Regulatory Guide 1.52 +
Report
NEDC-30936P +
SR
SR-4.8.1.1.2 +, SR-4.8.1.1.1 +, SR-4.8.2.1.d +, SR-4.8.1.2 +, SR-4.8.2.2 +, SR-4.8.2.1 +, SR-4.3.1.1.2 +, SR-4.8.4.2.a +  and SR-4.8.2.1.C +
Site
Fermi +
Site license
NPF-43 +
Start date
March 1, 1996  +
State
Washington +  and Michigan +
System
Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Control Room Emergency Filtration System +, Automatic Depressurization System +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Safety Relief Valve +  and Control Rod +
TS
TS-4.7.1.2 +, TS-4.0.5 +, TS-4.3.3.2 +, TS-4.3.2.2 +, TS-4.1.3.1 +, TS-4.4.2.2 +, TS-4.6.1.2 +, TS-4.0.2 +, TS-4.3.1.3 +, TS-4.5.1 +, TS-4.6.3.2 +, TS-4.6.3.4 +, TS-4.6.3.5 +, TS-4.6.2.1 +, TS-4.3.1.2 +, TS-3.6.I +, TS-4.5.1.d +, TS-4.5.1.c +, TS-4.3.9.2 +, TS-4.4.3.2 +, TS-4.1.3.5 +, TS-4.3.4.2 +, TS-4.1.5.d +, TS-4.6.1.4 +, TS-4.1.5 +, TS-4.4.8 +, TS-4.4.2.1 +, TS-4.7.5.b +, TS-4.6.4.1 +, TS-4.5.2.1 +...
Test
Bench test +
Title
Safety Evaluation Supporting Amend 106 to License NPF-43  +
Topic
Safe Shutdown +, Ultimate heat sink +, Stroke time +, Squib +, Excess Flow Check Valve +, Integrated leak rate test +, Exemption Request +, Pressure Boundary Leakage +, Through-Wall Leakage +, Unidentified leakage +, Overspeed trip +, Overspeed +  and Basic Component +
Trip
Turbine Control Valve Fast Closure +
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/ML2010/ML20101A150.pdf  +
 
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