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ML19136A411
Show incoming properties 
Category
Letter, Report  and Technical
Accession number
ML19136A411  +
CFR
10 CFR 50 Appendix A +, 10 CFR 50.36 +, 10 CFR 2.390 +, 10 CFR 50 Appendix B Criterion XI +, 10 CFR 50.36#c3 +, 10 CFR 50.36#c1iiA +  and 10 CFR 50.55a#h +
Docket
05200048  +
Document
ML18297A378 +
Equipment trip
Reactor Trip +
FR
75 FR 26294 +
From
Bergman T +  and NuScale +
General design criterion
GDC 20 +  and GDC 13 +
Generic letter
NRC Generic Letter 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle +
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ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +, ML19136A411 +  and ML19136A411 +
IEEE
IEEE 603 +
In package
ML19136A410 +
Issue date
May 16, 2019  +
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07:27:20, 5 January 2025  +
Page count
96  +
Person
Omid Tabatabai +, Gregory Cranston +  and Samuel Lee +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.105 +
Regulatory Issue Summary
RIS 2006-17, NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specification, with Respect to Limiting Safety System Settings (LSSS) During Periodic Testing and Calibration of Instrument Channels +
SSC
07-52-048 +
Site
NuScale +
Start date
May 16, 2019  +
State
Oregon +  and Washington +
System
Steam Generator +, Reactor Coolant System +, Reactor Protection System +, Emergency Core Cooling System +  and Main Steam +
TSTF
TSTF-493 +
Title
LLC - Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 2  +
To
Document Control Desk +  and Office of New Reactors +
Topic
Anticipated operational occurrence +, High Energy Line Break +, Operability Determination +  and Affidavit +
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http://pbadupws.nrc.gov/docs/ML1913/ML19136A411.pdf  +
 
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