ML17157B690

4 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications

ML17157B690
Person / Time
Site:	Duane Arnold
Issue date:	05/22/2017
From:	NextEra Energy Duane Arnold
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17157B650	List: ML17157B649 ML17157B674 ML17157B675 ML17157B677 ML17157B678 ML17157B679 ML17157B680 ML17157B681 ML17157B682 ML17157B683 ML17157B684 ML17157B685 ML17157B686 ML17157B687 ML17157B688 ML17157B689 ML17157B690 ML17157B691 ML17157B692 NG-17-0086, Transmittal of Revision 24 of the DAEC Updated Final Safety Analysis Report and the Current DAEC Technical Specifications Bases NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 4, Reactor NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 8, Electric Power NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Table of Contents NG-17-0111, Redacted - Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics
References
NG-17-0111
Download: ML17157B690 (1)

Text

UFSAR/DAEC-1 16.0-1 Revision 24 - 4/17 Chapter 16 TECHNICAL SPECIFICATIONS 16.0 TECHNICAL REQUIREMENTS MANUAL The Technical Specification amendment to convert the DAEC Custom Technical Specifications (CTS) to the Improved Technical Specifications (ITS) per NUREG-1433 (Amendment #223) includes relocation of certain CTS requirements to the Technical Requirements Manual (TRM).

The TRM is a licensee controlled document incorporated herein by reference into the UFSAR and subject to revision per 10 CFR 50.59 by Operation License (OL) condition (See Section 2.C.(7) and Appendix B to OL).

The TRM is bound separately from the UFSAR for user convenience.

2017-002