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ML20114D068
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Category
CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and RESEARCH INSTITUTION/LABORATORY TO NRC
ASME section
ASME Section XI +
Accession number
ML20114D068  +
Atomic Element
Hydrogen +, Lead +  and Tin +
CFR
10 CFR 50 +  and 10 CFR 2.790#a +
Committee
Advisory Committee on Reactor Safeguards +
Correspondence
TXX-4218, Forwards Demonstration of Ultrasonic Exam Techniques Applied to Welds in Main Coolant Loop Piping +
Cross cutting aspect
P.1(f) +
Docket
05000423  +, 00423  +, 00400  +  and 00445  +
Emergency Facility
Technical Support Center +
From
Battelle Memorial Institute +, Thomas Taylor +  and PACIFIC NORTHWEST NATION +
General design criterion
GDC 19, Control room +
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>.
ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +, ML20114D068 +  and ML20114D068 +
In package
ML20107K577 +
Issue date
November 21, 1984  +
Letter
ML20095G910 +
Manufacturer
Westinghouse +
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04:53:33, 13 December 2024  +
NRC information notice
Information Notice 82-34 +
NUREG
NUREG-1031, Forwards Safety Evaluation Re Emergency Operating Procedures Upgrade Program Per TMI Action Item 1.C.1.Eight Procedures Validated on Simulator & Actions Acceptable +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +
Page count
6  +
Procedure
ST +  and MP +
Project stage
Request  +
Site
Millstone +
Start date
November 21, 1984  +
State
Texas +, Ohio +, Pennsylvania +, Georgia +, Washington +  and Idaho +
System
Steam Generator +, Reactor Coolant System +  and Main Steam +
TXX
TXX-4218, Forwards Demonstration of Ultrasonic Exam Techniques Applied to Welds in Main Coolant Loop Piping +
Title
Summarizes 841109 Meeting W/Northeast Utils & Westinghouse at Site to Observe & Evaluate Effectiveness of Ultrasonic Insp of Cast Stainless Steel Welds in Primary Piping Sys  +
To
Hum M +  and Office of Nuclear Reactor Regulation +
Topic
Liquid penetrant +
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http://pbadupws.nrc.gov/docs/ML2011/ML20114D068.pdf  +
WCAP
WCAP-9894 +
Westinghouse report
WCAP-9894 +
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