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ML20129E082
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Category
TEXT-SAFETY REPORT  and SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
Accession number
ML20129E082  +
CFR
10 CFR 50 Appendix J +, 10 CFR 50.55a +, 10 CFR 50.55a#f4iv +  and 10 CFR 50.55a#b2vii +
Docket
05000324  +, 05000325  +, 00325  +  and 00324  +
Effective date
September 8, 1992  +  and October 26, 1995  +
From
NRC (Affiliation Not Assigned) +
Generic letter
NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +
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ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +, ML20129E082 +  and ML20129E082 +
In package
ML20129E073 +
Issue date
September 26, 1996  +
Letter
BSEP-96-0174, Requests Approval by NRC for Plant to Use Portion of ASME Code,Section XI,1987 Edition,W/Operational & Maint Code OM-10a-1988,Addenda Part 10 +
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16:40:42, 12 December 2024  +
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 +
Page count
5  +
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ML20129E082 +
Project stage
Request  +
SSC
0M-10 +
Site
Brunswick +
Start date
September 26, 1996  +
State
Washington +
System
Reactor Coolant System +
Title
Safety Evaluation Supporting Request to Use Certain Portions of Later Edition of ASME Code for Inservice Leakage Testing Valves for Brunswick Steam Electric Plant Units 1 & 2  +
Topic
Incorporated by reference +
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http://pbadupws.nrc.gov/docs/ML2012/ML20129E082.pdf  +
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