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ML15092A854
Show incoming properties 
Category
License-Operator  and Part 55 Examination Related Material
Accession number
ML15092A854  +
Act
Endangered Species Act +
Area
Switchyard +
Atomic Element
Boron +, Iodine +, Hydrogen +  and Lead +
CFR
10 CFR 100 +  and 10 CFR 73 Appendix G +
Cornerstone
Physical Protection +
Docket
05000327  +  and 05000328  +
Equipment trip
Turbine Trip +  and Reactor Trip +
From
NRC Region 2 +
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ML15092A854 +, ML15092A854 +, ML15092A854 +, ML15092A854 +, ML15092A854 +, ML15092A854 +, ML15092A854 +  and ML15092A854 +
Hours
9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-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)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
Isotope
Tritium +
Issue date
April 2, 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>.
18:30:20, 10 January 2025  +
NRC form
NRC Form 361, Immediate Notification +
NUREG
NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +
Page count
61  +
Procedure
AM +, AOP +, Emergency Plan +, AOP-M.02 +, AOP-M.04 +, AOP-M.09 +, ES-401 +, ES-i.3 +, AOP-R.01 +, AOP-R.05 +, AOP-P.07 +  and AOP-I.01 +
SR
SR-4.8.2.1 +
SSC
2A-A +, 2A1-A +, 1A2-A +, 2A2-A +  and H2l-43-200 +
Scram
Automatic Scram +
Site
Sequoyah +
Start date
April 2, 2015  +
State
Washington +  and Tennessee +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Control Rod +, Containment Spray +  and Emergency Feedwater System +
TS
TS-3.0.3 +, TS-3.4 +, TS-3.8.2.1 +, TS-3.3.2 +, TS-3.1 +, TS-3.6.5.1 +, TS-3.3.3.7 +, TS-3.9.12 +  and TS-3.11 +
Title
Initial Exam 2015-301 Final SRO Written Exam  +
To
Tennessee Valley Authority +
Topic
Safe Shutdown +, Unanalyzed Condition +, Time of Discovery +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Internal Flooding +, Local Leak Rate Testing +, Loss of Offsite Power +, Operability Determination +, Rod Drop Event +, Fuel cladding +, Pressure Boundary Leakage +, Power change +  and Fatality +
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http://pbadupws.nrc.gov/docs/ML1509/ML15092A854.pdf  +
 
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