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ML030510302 +

BWRVIP

BWRVIP-05 +

CFR

10 CFR 50.55a#g5 +, 10 CFR 50.55a#g6iiA + and 10 CFR 50.55a#b2xvA +

Code case

ASME Code Case N-577 +

Docket

05000260 + and 00260 +

From

Tennessee Valley Authority + and Abney T +

Generic letter

NRC Generic Letter 98-05, Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds +

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>.

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Issue date

February 14, 2003 +

Letter

ML021490190 + and ML18038B439 +

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>.

17:26:18, 16 January 2025 +

NUREG

NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +

Page count

9 +

Project reference

TAC:MA5953 + and TAC:MA8873 +

Project stage

Request +

SSC

2A-BFN +, 2C-BFN +, 6A-C +, 5M-C +, 11A-K +, 4X-C +, 1G-BFN + and 1E-BFN +

February 14, 2003 +

Tennessee +, Georgia +, Maryland +, Washington + and Alabama +

System

Feedwater +, Reactor Pressure Vessel +, Standby Liquid Control + and Control Rod +

Title

American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Second Ten-Year Inspection Interval, Requests for Relief 2-ISI-6, Revision 2, 2-ISI-13, 2-ISI-14, and 2-ISI-15, Clarification and +

To

Office of Nuclear Reactor Regulation + and Document Control Desk +

Topic

VT-2 +

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http://pbadupws.nrc.gov/docs/ML0305/ML030510302.pdf +

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