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ML14038A346
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Category
Letter  and Inspection Report
ASME section
ASME Section XI +  and ASME Section IV +
Accession number
ML14038A346  +
Atomic Element
Boron +, Carbon +, Hydrogen +  and Lead +
CFR
10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 19 +, 10 CFR 61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix E +, 10 CFR 72.48 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.54#q +, 10 CFR 50.54#t +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 50.47#b +, 10 CFR 50.47#b2 +  and 10 CFR 50.47#b5 +
CY
CY 2014 +
Code case
ASME Code Case N-729-1 +
Cornerstone
Emergency Preparedness +, Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +
Correspondence
CY 2014 +
Cross cutting aspect
P.2 +
Docket
05000327  +, 05000328  +, 00327  +  and 00328  +
Document
ML12326A678 +, ML13025A102 +, ML13219A022 +, ML12353A050 +, ML13070A025 +  and ML13246A091 +
Emergency Facility
Technical Support Center +
Equipment
Portal monitor +
Finding
05000327/FIN-2013005-01 +  and 05000327/FIN-2013004-01 +
From
Bartley J +  and Reactor Projects Region 2 Branch 6 +
Generic letter
NRC Generic Letter 07-01 +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +  and NRC Generic Letter 88-17, Loss of Decay Heat Removal +
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ML14038A346 +, ML14038A346 +, ML14038A346 +, ML14038A346 +, ML14038A346 +, ML14038A346 +, ML14038A346 +, ML14038A346 +, ML14038A346 +  and ML14038A346 +
Hours
8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +
IE circular
IE Circular 81-07 +
Inspection Manual Chapter
NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, IMC 0305, Operating Reactor Assessment Program +  and IMC 0310, Aspects within the Cross-Cutting Areas +
Inspection procedure
IP 71114.05 +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71114, Reactor Safety Emergency Preparedness +  and IP 71152, Problem Identification and Resolution (PI&R) +
Inspection report
IR 05000327/2013005 +
Issue date
February 7, 2014  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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04:21:19, 11 January 2025  +
NUREG
NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +
Page count
44  +
SR
SR-4.6.2.1.1 +
SSC
1B-B +, 1A-A +, 3D-C +, 07-14-215 +  and 48N1701-17 +
See also
IR 05000327/2013005 +
Site
Sequoyah +
Site license
Sequoyah +
Start date
February 7, 2014  +
State
Tennessee +, Georgia +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Pressure Vessel +, Auxiliary Building Gas Treatment System +, Residual Heat Removal +, Emergency Gas Treatment System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Condenser +, Control Rod +, Containment Spray +  and Emergency Feedwater System +
TS
TS-3.7.4 +, TS-3.5.2 +, TS-3.9.1 +  and TS-6.8 +
Test
Post maintenance test +
Title
IR 05000327-13-005, 05000328-13-005; 10/1/2013 - 12/31/2013; Sequoyah Nuclear Plant, Units 1 and 2; Other Activities  +
To
Tennessee Valley Authority +  and James Shea +
Topic
Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Fire Barrier +, Stroke time +, Post Accident Monitoring +, Internal Flooding +, Functionality Assessment +, Locked High Radiation Area +, Condition Adverse to Quality +, Significance Determination Process +, Foreign Material Exclusion +, Process Control Program +, Loss of Offsite Power +, Eddy Current Testing +, Operability Determination +, Coast down +, Unidentified leakage +  and Siren +
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http://pbadupws.nrc.gov/docs/ML1403/ML14038A346.pdf  +
USA certificate
USA/9168B(U) +
Work order
WO 113312025 +, WO 113223153 +, WO 113377829 +, WO 112096045 +, WO 111234712 +, WO 113806636 +, WO 114560807 +, WO 114198329 +, WO 113408190 +, WO 113756597 +, WO 11108121224 +, WO 114067330 +  and WO 114139751 +
 
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