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ML12090A881
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Category
Legal-Pre-Filed Exhibits
ASME section
ASME Section XI +  and ASME Section X +
Accession number
ML12090A881  +
Agency
New York State Energy Research and Development Authority +
Atomic Element
Iron +, Nickel +, Carbon +  and Lead +
CFR
10 CFR 50.48 +, 10 CFR 50 Appendix B +, 10 CFR 54 +, 10 CFR 2.390 +, 10 CFR 50.49 +, 10 CFR 50.65 +, 10 CFR 54.4 +, 10 CFR 54.4#a2 +, 10 CFR 54.4#a1 +  and 10 CFR 50.49#f +
CR
CR-IP3-2007-01852 +, CR-IP3-2008-00458 +, CR-IP2-2000-04864 +, CR-IP2-2001-07815 +, CR-IP2-2003-02364 +, CR-IP2-2004-05748 +, CR-IP2-2006-01485 +, CR-IP2-2006-01929 +, CR-IP2-2006-02146 +, CR-IP2-2006-02290 +, CR-IP2-2006-02639 +, CR-IP2-2006-02780 +, CR-IP2-2008-00124 +, CR-IP3-1995-00044 +, CR-IP3-2000-00561 +, CR-IP3-2005-02634 +, CR-IP3-2005-04563 +, CR-IP3-2006-02270 +, CR-IP3-2007-01399 +, CR-IP3-2007-03497 +, CR-IP2-02-32382 +, CR-IP2-03-10707 +, CR-IP2-04-14606 +, CR-IP2-04-14609 +, CR-IP2-06-01525 +, CR-IP3-02-20718 +, CR-IP3-05-21828 +, CR-IP3-05-19497 +, CR-IP3-05-24529 +, CR-IP3-06-13173 +...
Contact
SECY RAS +
Correspondence
NL-06-028, Day Response to NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications +, NL-05-063, Reactor Vessel Lower Head Inspection Results; Indian Point Unit 3 +, NL-05-044, Reactor Vessel Upper Head Inspection Results; Indian Point Unit 3. Spring 2005 Refueling Outage (3R13) +, NL-05-002, Reactor Vessel Lower Head Inspection Results Fall 2004 Refueling Outage (2R16) +  and NL-05-001, Reactor Vessel Upper Head Inspection Results; Indian Point 2. Fall 2004 Refueling Outage (2R16) +
Docket
05000247  +, 05000286  +, 00247  +  and 00286  +
Document
IR 05000247/2008006 +, ML081850595 +, ML081840487 +  and ML082130530 +
Entergy procedure
EN-DC-159 +, EN-LI-102 +, ENN-DC-150 +, EN-DC-317 +, EN-DC-319 +, EN-DC-343 +, EN-DC-315 +, EN-DC-178 +  and EN-DC-147 +
From
Conte R +  and Engineering Region 1 Branch 1 +
Generic letter
NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +
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ML12090A881 +, ML12090A881 +, ML12090A881 +, ML12090A881 +, ML12090A881 +, ML12090A881 +, ML12090A881 +, ML12090A881 +, ML12090A881 +, ML12090A881 +  and ML12090A881 +
In package
ML12090A878 +
Inspection Manual Chapter
NRC Inspection Manual 2516 +  and NRC Inspection Manual 0612, Power Reactor Inspection Reports +
Inspection procedure
IP 71111.08 +  and IP 71002, License Renewal Inspection +
Inspection report
IR 05000247/2008006 +
Intervenor
Union of Concerned Scientists +  and Public Citizen's Critical Mass Energy Project +
Issue date
March 30, 2012  +
License amendment topic
License Renewal Application +
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>.
07:57:58, 12 January 2025  +
NEI
NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +
NL
NL-06-028, Day Response to NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications +, NL-05-063, Reactor Vessel Lower Head Inspection Results; Indian Point Unit 3 +, NL-05-044, Reactor Vessel Upper Head Inspection Results; Indian Point Unit 3. Spring 2005 Refueling Outage (3R13) +, NL-05-002, Reactor Vessel Lower Head Inspection Results Fall 2004 Refueling Outage (2R16) +  and NL-05-001, Reactor Vessel Upper Head Inspection Results; Indian Point 2. Fall 2004 Refueling Outage (2R16) +
NRC bulletin
NRC Bulletin 02-01 +  and NRC Bulletin 80-11 +
NRC information notice
Information Notice 87-67 +, Information Notice 2003-02, Recent Experience with Reactor Coolant System Leakage & Boric Acid Corrosion +, Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head +  and Information Notice 2002-13, E-mail from H. Nieh, Oedo to A. Levin, Ocm, Et Al., Issuance of Information Notice 2002-13, Fwd: E-mail from D. Pickett T Davis-Besse Communication Plan +
NUREG
NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +
Page count
43  +
Person
Joseph Pollock +
RAS
RAS 22164 +
Regulatory Guide
Regulatory Guide 1.160 +
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 +
See also
IR 05000247/2008006 +
Site
Indian Point +
Site license
Indian Point +
Start date
March 30, 2012  +
State
New York +
System
Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Reactor Pressure Vessel +  and Containment Spray +
TSTF
TSTF-449 +
Title
NRC Staff Pre-Filed Hearing Exhibit NRC000107, Indian Point Nuclear Generating Units 2 and 3 - NRC License Renewal Inspection Report 05000247/2008006 and 05000286/2008006  +
To
Entergy +  and Joseph Pollock +
Topic
Unanalyzed Condition +, Boric Acid +, Non-Destructive Examination +, Fire Barrier +, Coatings +, Nondestructive Examination +, Zebra Mussel +, Aging Management +, Flow Accelerated Corrosion +, Stress corrosion cracking +, License Renewal +, Biofouling +, Through-Wall Leak +, Through-Wall Leakage +, Fire Protection Program +, Power Uprate +  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/ML1209/ML12090A881.pdf  +
WCAP
WCAP-12191 +  and WCAP-12937 +
Westinghouse report
WCAP-12937 +  and WCAP-12191 +
Work order
WO 51345229#01 +  and WO 51434864 +
Work request
WR 51550475 +
 
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