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IR 05000269/2014003
Show incoming properties 
Category
Letter  and Inspection Report
ANSI code
ANSI/ANS-2.5-1984 +
ASME section
ASME Section XI +
Accession number
ML14219A195  +
Area
Switchyard +
Atomic Element
Iodine +, Carbon +  and Lead +
CFR
10 CFR 20 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 61 +, 10 CFR 50.65 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.55a +, 10 CFR 50.65#a1 +, 10 CFR 50.65#a4 +, 10 CFR 20.1501#a2 +  and 10 CFR 50.75#g +
CY
CY 2012 +  and CY 2013 +
Contact
D. Robinson +, C. Blackwelder +, S. Batson +, E. Burchfield +, C. Wasik +, C. King +, P. Street +, E. Lampe +, J. Pounds +, R. Guy +, G. Armentrout +, S. Boggs +, A. Lotfi +, F. Rickenbaker +, M. McNeely +, M. Barnes +, R. Lampe +, A. Spear III +, James Smith +, Teresa Ray +  and Tira Patterson +
Cornerstone
Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +
Correspondence
CY 2012 +  and CY 2013 +
Docket
05000269  +, 05000270  +, 05000287  +, 00269  +, 00270  +  and 00287  +
Document
IR 05000269/2013005 +, ML13114A928 +  and ML14178A535 +
ENS
ENS 50093 +
Engineering change
EC-91875 +  and EC-107579 +
Equipment
Portal monitor +
From
NRC/RGN-II/DRP/RPB1 +  and Gerald Mccoy +
Generic letter
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +
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>.
IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +, IR 05000269/2014003 +...
IP
TI 2515/182 +
Inspection Manual Chapter
NRC Inspection Manual 0612 Appendix B +
Inspection procedure
IP 71152, Problem Identification and Resolution (PI&R) +
Inspection report
IR 05000269/2014003 +
Isotope
Tritium +
Issue date
August 7, 2014  +
Licensing Basis Document
Updated Final Safety Analysis Report +
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>.
13:56:08, 20 December 2019  +
NEI
NEI 09-14, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000168, Guideline for the Management of Underground Piping and Tank Integrity, NEI 09-14 (Rev.1) (December 2010) (NEI 09-14 Rev. 1) +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +
NUREG
NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG-1608 +  and NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +
Page count
37  +
Person
Gerald Mccoy +
Power source
600V +
Regulatory Guide
Regulatory Guide 1.21 +, Regulatory Guide 8.38 +, Regulatory Guide 1.109 +, Regulatory Guide 4.1 +, Regulatory Guide 4.15 +  and Regulatory Guide 1.23 +
Report number
3  +
SSC
4RIA-45 +, 3RC-211-73 +, 3RC-211-70 +, 3XS1-F2D +, 3HP-4 +, 3HP-409 +, 3LP-2 +, 3PR-87 +, 3PR-90 +, 3PR-81 +  and 3PR-84 +
Site
Oconee +
Site license
Oconee +
Start date
August 7, 2014  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Transformer +, Reactor Building Ventilation +, Decay Heat Removal +  and Emergency Feedwater System +
TS
TS-5.0 +
Title
IR 05000269-14-003, 05000270-14-003, 05000287-14-003; on 04/01/2014 - 06/30/2014; Oconee Nuclear Station Units 1, 2 and 3; Integrated Inspection Report  +
To
Duke Energy +  and Batson S +
Topic
Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, High Radiation Area +, Non-Destructive Examination +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Internal Flooding +, Probabilistic Risk Assessment +, Functionality Assessment +, Locked High Radiation Area +, Annual Radioactive Effluent Release Report +, Annual Radiological Environmental Operating Report +, Process Control Program +, Eddy Current Testing +, Operability Determination +, Annual Radiological Effluent Release Report +  and Unidentified leakage +
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/ML1421/ML14219A195.pdf  +
Work order
WO 2076606 +
Year
2,014  +
 
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