ML21008A394

Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance

ML21008A394
Person / Time
Site:	Byron, Braidwood
Issue date:	12/17/2020
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML21008A383	List: ML21008A380 ML21008A386 ML21008A387 ML21008A388 ML21008A389 ML21008A392 ML21008A394 ML21008A397 ML21008A399 ML21008A401 ML21008A402 ML21008A403 ML21008A404 ML21008A405 ML21008A406 ML21008A408 ML21008A409 ML21008A410 ML21008A411 ML21008A413 ML21008A414 ML21008A416 ML21008A417 ML21008A418 ML21008A420 ML21008A421 ML21008A422 ML21008A426 ML21137A191 ML21137A207 ML21137A221 ML21137A238 ML21137A246 ML21137A251 ML21137A253 RS-20-153, Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1
References
RS-20-153
Download: ML21008A394 (2)

Text

B/B-UFSAR CHAPTER 17.0 - QUALITY ASSURANCE TABLE OF CONTENTS PAGE 17.0 QUALITY ASSURANCE 17.0-1 17.0-i

B/B-UFSAR CHAPTER 17.0 - QUALITY ASSURANCE The quality assurance program for the Byron and Braidwood Stations is conducted in accordance with the Quality Assurance Program for Nuclear Generating Stations. This program was initially submitted to the Nuclear Regulatory Commission in June 1975, as Topical Report CE-1. By letter of December 29, 1975, the NRC's Chief of Quality Assurance Branch, Division of Reactor Licensing, informed Commonwealth Edison's Executive Vice President, Mr. W. B. Behnke, that this Topical Report CE-1 was an acceptable program for the design, procurement, construction and operations activities within Commonwealth Edison's scope of work for nuclear power plants. Instructions were given to reference this Topical Report in Section 17 of License applications.

Currently Topical Report NO-AA-10 is the basis for the Quality Assurance Program at the Byron/Braidwood Stations.

Chapter 2 and Appendix C of the above-referenced topical report provides for compliance with certain regulatory guides and ANSI standards. Any exceptions taken to the requirements of these guides are found in Appendix A of this UFSAR. Otherwise, Byron/Braidwood Stations are in compliance with the guides and ANSI standards.

Subsection 3.2.1.1 of the UFSAR states that Safety Category I systems or portions of systems and components meet the requirements of Appendix B to 10 CFR 50. Those structures, systems, and components classified as Safety Category I, therefore, are under control of the QA program and are listed in Table 3.2-1. Where only portions of a system are classified as Safety Category I, the P&IDs identify the boundary between Safety Category I and Safety Category II.

17.0-1 REVISION 10 - DECEMBER 2004