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ML18352A227 +

Agency

Pennsylvania Bureau of Radiation Protection +

CFR

10 CFR 50 Appendix J +, 10 CFR 50.55a +, 10 CFR 50.55a#z1 + and 10 CFR 50.55a#z +

Code case

ASME Code Case OMN-16 +

Docket

05000352 +, 05000353 +, 00352 + and 00353 +

Document

Regulatory Guide 1.192 +, ML13042A348 +, ML17004A063 +, ML102360570 +, ML15174A303 +, ML16235A340 + and ML093080382 +

From

Exelon + and David Helker +

Generic letter

NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +

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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ISTC

ISTC-3630 +

Issue date

December 17, 2018 +

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>.

13:06:39, 5 January 2025 +

NEI

NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NUREG

NUREG-1482, Revision 4, Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants Final Report + and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

Page count

22 +

Processing error"Processing error" is a predefined property provided by <a rel="nofollow" class="external text" href="https://www.semantic-mediawiki.org/wiki/Help:Special_properties">Semantic MediaWiki</a> and represents errors that appeared in connection with improper value annotations or input processing.

ML18352A227 +

Project

EPID:L-2018-LLR-0384 +

Project reference

TAC:ME7983 +, TAC:ME2556 +, TAC:MD3894 + and TAC:MD3300 +

Project stage

Request +

Regulatory Guide

Regulatory Guide 1.163 + and Regulatory Guide 1.192 +

SR

SR-4.1.3.2 +, SR-4.1.3.2.b +, SR-4.1.3.2.c + and SR-4.1.3.2.a +

SSC

F017A-D +, 42A-D +, 1and2-Propose + and 1and2-Safety +

December 17, 2018 +

Service water +, Reactor Protection System +, Primary containment +, Shutdown Cooling +, Core Spray +, Residual Heat Removal +, Spray Pond +, Emergency Core Cooling System + and Control Rod +

TS

TS-6.8.4.j +

Title

Relief Requests Associated with Fourth Ten-Year Inservice Testing Interval +

To

Office of Nuclear Reactor Regulation + and Document Control Desk +

Topic

Safe Shutdown +, Stroke time +, Surveillance Frequency Control Program +, Power-Operated Valves + and Power Operated Valves +

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http://pbadupws.nrc.gov/docs/ML1835/ML18352A227.pdf +

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