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ML11270A261
Show incoming properties 
Category
Legal-Motion
ACI
ACI-349 +
ASME code
IWB-2412 +
ASME section
ASME Section XI +, ASME Section III +  and ASME Section I +
Accession number
ML11270A261  +
Atomic Element
Nickel +, Sodium +, Chlorine +, Chloride +  and Chromium +
CFR
10 CFR 50 Appendix R +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.49 +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 54.29#a +, 10 CFR 54.21#d +, 10 CFR 54.21#a3 +  and 10 CFR 54.21#b +
Committee
Advisory Committee on Reactor Safeguards +
Contact
SECY RAS +
Correspondence
NL-08-021, License Renewal Application Amendment 2 +
Docket
05000286  +, 05000247  +, 00247  +  and 00286  +
Document
ML111600498 +, ML080230637 +, ML090160204 +, ML103430502 +, ML110250634 +, ML11243A109 +, ML11228A030 +, ML11223A480 +, ML11108A106 +  and ML1014501190 +
EPRI MRP
MRP-146 +  and MRP-227 +
From
New York +, Office of the Attorney General +  and Sipos J +
Generic letter
NRC Generic Letter 07-01 +
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ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +, ML11270A261 +...
In package
ML11270A260 +
Intervenor
Morgan, Lewis & Bockius +
Issue date
September 27, 2011  +
LBP
LBP-11-17 +
LRA
LRA B.1.23 +  and LRA B.0.4 +
Letter
IR 05000286/2011003 +, IR 05000247/2010404 +, ML110871459 +, ML11208C309 +, ML102110086 +, ML11139A447 +, ML110180529 +, ML11234A470 +, CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 +, ML11146A131 +, ML083500409 +, ML071140022 +  and 05000247/LER-2009-003, Regarding Loss of Single Train 21 Pressurizer Backup Heater Required for Remote Plant Shutdown from the Control Room Due to an Inoperable Breaker +
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>.
06:50:32, 13 January 2025  +
NL
NL-08-021, License Renewal Application Amendment 2 +
NRC order
CLI-10-17 +
NUREG
NUREG/CR-6260 +, NUREG-1930, Lr Hearing - NUREG-1930 in ADAMS +, NUREG/CR-5999, Forwards Updated Fatigue Design Curves for Austenitic Stainless Steels in LWR Environments.Design Curves Being Provided in Advance of Future Update of NUREG/CR-5999 to Facilitate Efforts on Resolution of GSI-190 +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, 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
66  +
Procedure
SP-152 +  and SP-153 +
Project stage
Request  +
RAS
RAS 21135 +
Regulatory Issue Summary
RIS 2011-07, New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000310, NRC Regulatory Issue Summary 2011-07 License Renewal Submittal Information for Pressurized Water Reactor Internals Aging Management +
SSC
1O-inch +  and 1a-year +
Site
Indian Point +
Site license
Indian Point +
Start date
September 27, 2011  +
State
Pennsylvania +, Connecticut +, Washington +, New York +, Louisiana +  and Vermont +
System
Steam Generator +, Reactor Coolant System +, Service water +, Auxiliary Feedwater +  and Control Rod +
Title
State of New York Motion for an Extension of Time So That Outstanding Issues Affecting the Content of Prefiled Direct Testimony and Statements of Positions May Be Resolved  +
To
Atomic Safety and Licensing Board Panel +
Topic
Coatings +, Nondestructive Examination +, Condition Adverse to Quality +, Aging Management +, Fukushima Dai-Ichi +, Stress corrosion cracking +, License Renewal +, Chernobyl +, Environmental Justice +, Affidavit +  and Thermal fatigue +
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http://pbadupws.nrc.gov/docs/ML1127/ML11270A261.pdf  +
 
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