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NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval
Show incoming properties 
Category
Letter type:NRC
ASME code
IWB-3600 +, IWB-3132 +, IWB-3142 +, IWB-2420 +  and IWB-2400 +
ASME section
ASME Section XI +  and ASME Section X +
Accession number
ML14006A318  +
CFR
10 CFR 50.91 +, 10 CFR 50.55a +, 10 CFR 50.55a#a3i +  and 10 CFR 50.55#a +
Correspondence
NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +
Docket
05000266  +  and 00266  +
Document
ML120190748 +  and NRC 2010-0050, Refueling 32 Analytical Evaluation Report for the Reactor Vessel +
From
Point Beach +  and Meyer L +
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>.
NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +, NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +  and NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +
Issue date
December 30, 2013  +
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>.
05:03:13, 11 January 2025  +
NRC
NRC 2013-0107, CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval +
Page count
7  +
Project reference
TAC:ME7504 +
Project stage
Request  +
SSC
13R-13 +  and 3W14-FOR +
Site
Point Beach +
Site license
DPR-24 +
Start date
December 30, 2013  +
State
Washington +  and Wisconsin +
System
Reactor Coolant System +  and Reactor Pressure Vessel +
Title
CFR 50.55a Request, Relief Request 1-RR-6, Re-Examination of the Unit 1 Reactor Pressure Vessel Indication on the a Inlet Nozzle Weld Fifth Ten-Year Inservice Inspection Program Interval  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Non-Destructive Examination +, VT-2 +, Eddy Current Testing +  and Dissimilar Metal Weld +
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/ML1400/ML14006A318.pdf  +
 
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