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ML23107A025
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Category
Updated Final Safety Analysis Report (UFSAR)
ANSI code
ANSI/ANS-18.1-1999 +
ASME section
ASME Section III +
Accession number
ML23107A025  +
Atomic Element
Boron +, Iodine +, Germanium +, Carbon +, Hydrogen +  and Lead +
CFR
10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 70 +, 10 CFR 30 +, 10 CFR 20 Appendix B +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 61 +, 10 CFR 20.2106 +, 10 CFR 50 Appendix I +  and 10 CFR 20.302 +
CR
CR-PNP-2023-00002 +
Docket
05000255  +  and 00255  +
Equipment
Portal monitor +
From
Holtec Decommissioning International +
General design criterion
GDC 19, Control room +
Generic letter
NRC Generic Letter 85-14, Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste Not Generated by The Utility +, NRC Generic Letter 89-01, Implementation of Programmatic and Procedural Controls for Radiological Effluent Technical Specifications +  and NRC Generic Letter 1981-38, Storage of Low-Level Radioactive Wastes at Power Reactor Sites +
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ML23107A025 +, ML23107A025 +, ML23107A025 +, ML23107A025 +, ML23107A025 +, ML23107A025 +, ML23107A025 +, ML23107A025 +, ML23107A025 +  and ML23107A025 +
Hours
2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +
IE circular
IE Circular 80-18 +
In package
ML23107A065 +
Isotope
Tritium +, Co-60 +  and Cs-137 +
Issue date
March 31, 2023  +
License amendment topic
Alternate Source Term +
Licensing Basis Document
Updated Final Safety Analysis Report +
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11:51:58, 27 November 2024  +
NRC information notice
Information Notice 90-09 +
NUREG
NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +
Page count
48  +
Procedure
CP +
Project stage
Request  +
Regulatory Guide
Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.26 +, Regulatory Guide 1.109 +, Regulatory Guide 1.111 +  and Regulatory Guide 1.70.3 +
SSC
2E-03 +
Site
Palisades +
Start date
March 31, 2023  +
State
Michigan +
System
Steam Generator +, Feedwater +, Service water +, Primary containment +, HVAC +, Circulating Water System +, Main Steam Line +  and Main Steam +
TS
TS-5.7 +
Title
6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management and Radiation Protection  +
To
Office of Nuclear Reactor Regulation +
Topic
High Radiation Area +, Grab sample +, Offsite Dose Calculation Manual +  and Locked High Radiation Area +
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http://pbadupws.nrc.gov/docs/ML2310/ML23107A025.pdf  +
Ultimate Heat Sink
Cooling Tower +  and Lake Michigan +
 
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