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IR 05000247/2013009
Show incoming properties 
Category
Inspection Report  and Legal-Exhibit
ASME code
IWB-2412 +
ASME section
ASME Section XI +
Accession number
ML15337A266  +
Atomic Element
Iron +, Nickel +, Copper +, Carbon +  and Chloride +
CA
LO-LAR-2011-0174 CA-00029 +, LO-LAR-2011-0174 CA-00065 +  and LO-LAR-2011-0174 CA-00015 +
CFR
10 CFR 50.48 +, 10 CFR 54 +, 10 CFR 2.109 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 54.3 +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a1 +, 10 CFR 54.21#c1 +, 10 CFR 54.21#c1i +, 10 CFR 54.21#c1ii +, 10 CFR 54.21#c1iii +  and 10 CFR 2.109#b +
CR
CR-IP2-2013-01786 +, CR-IP2-2013-01989 +, CR-IP2-2013-01756 +, CR-IP2-2013-02005 +  and CR-IP2-2013-01440 +
Code case
ASME Code Case N-578-1 +
Contact
M. Woodby +, T. Chan +, N. Azevedo +, M. Tesoriero +, M. Troy +, R. Walpole +, G. Dahl +, R. Drake +, D. Mayer +, C. Caputo +, P. Guglielmino +, R. Dolanksy +, J. Ventosa +, T. McCaffrey +, P. Conroy +, S. Manzione +, SECY RAS +, J. Flagg +, T. Orlando +, D. Pennino +, J. Quirk +  and Jeanette Curry +
Cornerstone
Barrier Integrity +, Initiating Events +  and Mitigating Systems +
Correspondence
NL-12-174, Additional Clarification of Underground Piping Information Provided in Letter NL-12-149 Regarding the License Renewal Application +, NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application +, NL-13-001, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements +, NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program +, NL-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification +  and NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +
Docket
05000247  +, 05000286  +, 00247  +  and 00286  +
Document
ML12110A315 +, ML13186A179 +, ML12341A180 +, ML093170671 +, NL-13-071, Entergy, Actions Required Prior to Entry Into Period of Extended Operation Associated with License Renewal Application (LRA) for Indian Point Energy Center Unit 2 +  and NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +
EPRI MRP
MRP-227 +  and MRP-191 +
Entergy procedure
EN-AD-101 +, EN-LI-100 +, EN-DC-150 +, EN-DC-317 +  and EN-DC-178 +
From
NRC/OGC +
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 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +, IR 05000247/2013009 +...
IP
TI 2516/001 +
Inspection report
IR 05000247/2013009 +  and IR 05000247/2012008 +
Isotope
Tritium +
Issue date
July 5, 2013  +
LRA
LRA B.1.24 +, LRA B.1.28 +, LRA B.1.25 +, LRA B.1.27 +, LRA B.1.33 +, LRA B.1.22 +, LRA B.1.23 +, LRA B.1.37 +  and LRA B.1.38 +
License amendment topic
License Renewal Application +
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>.
11:15:21, 10 January 2025  +
NL
NL-12-174, Additional Clarification of Underground Piping Information Provided in Letter NL-12-149 Regarding the License Renewal Application +, NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application +, NL-13-001, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements +, NL-10-063, Amendment 9 to License Renewal Application, Reactor Vessel Internals Program +, NL-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification +  and NL-10-082, License Renewal Application - Completion of Commitment 33 Regarding the Fatigue Monitoring Program +
NRC bulletin
NRC Bulletin 03-02 +
NUREG
NUREG/CR-6260 +, NUREG-1930, Lr Hearing - NUREG-1930 in ADAMS +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +  and NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report +
Page count
43  +
Person
James Trapp +
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.
IR 05000247/2013009 +
Project stage
Request  +
RAS
RAS 28149 +
Regulatory Issue Summary
RIS 2003-13, NRC Review of Responses to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +
Report number
9  +
Site
Indian Point +
Site license
Indian Point +
Start date
July 5, 2013  +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +  and Control Rod +
Title
Official Exhibit - NRC000181-00-BD01 - Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 NRC License Renewal Team Inspection Report 05000247/2013009 (July 5, 2013)  +
Topic
Boric Acid +, Non-Destructive Examination +, Coatings +, Nondestructive Examination +, VT-2 +, Aging Management +, License Renewal +, Fire Protection Program +, Eddy Current Test +, Thermography +  and Thermal fatigue +
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/ML1533/ML15337A266.pdf  +
WCAP
WCAP-12866 +, WCAP-16752-NP +  and WCAP-15988-NP +
Westinghouse report
WCAP-12866 +, WCAP-16752-NP +  and WCAP-15988-NP +
Work order
WO 00282078#01 +
Year
2,013  +
 
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