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ML041170468
Show incoming properties 
Category
Letter  and License-Application for Facility Operating License (Amend/Renewal) DKT 50
ANSI code
ANSI/ANS 56.8-1994 +  and ANSI/ANS 56.8 - 1994 +
ASME section
ASME Section V +
Accession number
ML041170468  +
Atomic Element
Nitrogen +  and Lead +
CFR
10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.90 +, 10 CFR 50.92 +  and 10 CFR 51.22#c9 +
Docket
05000293  +  and 00283  +
Effective date
October 26, 1995  +
From
Entergy +  and Balduzzi M +
Generic letter
NRC Generic Letter 87-05, Request for Additional Information Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells +
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>.
ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +, ML041170468 +  and ML041170468 +
Issue date
April 14, 2004  +
Manufacturer
General Electric +
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08:22:58, 16 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-1493 +  and NUREG/CR-4551 +
Page count
26  +
Person
Bryan Ford +  and Travis Tate +
Project reference
TAC:MB4752 +, TAC:MB6551 +, TAC:MB9004 +  and TAC:M95326 +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.174 +  and Regulatory Guide 1.163 +
SR
SR-3.7 +  and SR-4.7 +
SSC
T1n-Year +
Site
Pilgrim +
Site license
Pilgrim +
Start date
April 14, 2004  +
State
Washington +  and Massachusetts +
System
Reactor Coolant System +, Main Steam Isolation Valve +, Primary containment +  and Main Steam Line +
TS
TS-3.7.A +, TS-4.7.A +  and TS-1.0 +
Title
Request for Amendment, to the Technical Specifications to Provide a One-time Integrated Leak Rate Test (ILRT) Interval Extension  +
To
Office of Nuclear Reactor Regulation +  and Document Control Desk +
Topic
Probabilistic Risk Assessment +, Local Leak Rate Testing +, Large early release frequency +  and Integrated leak rate test +
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http://pbadupws.nrc.gov/docs/ML0411/ML041170468.pdf  +
 
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