RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance

Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance

ML16357A533
Person / Time
Site:	Byron, Braidwood
Issue date:	12/15/2016
From:	Exelon Generation Co
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML16357A264	List: ML16357A507 ML16357A508 ML16357A509 ML16357A521 ML16357A523 ML16357A524 ML16357A526 ML16357A529 ML16357A530 ML16357A532 ML16357A533 ML16357A534 ML16357A535 ML16357A536 ML16357A537 ML16357A540 ML16357A545 ML16357A549 ML16357A579 ML16357A580 ML16357A583 ML16357A584 ML16357A591 ML16357A592 ML16357A593 ML17086A588 ML17086A589 ML17086A590 ML17086A591 ML17086A592 ML17086A593 ML17086A595 ML17086A596 ML17086A597 ML17086A598 ML17086A599 ML17086A600 ML17086A601 ML17094A865 ML17095A852 ML17095A866 RS-16-248, Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases RS-16-248, Byron Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 RS-16-248, Byron Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Specifications Bases RS-16-248, Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix B - Construct Material Standards and Quality Control Procedures RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix C - Deleted RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix D - Computer Programs ... further results
References
RS-16-248
Download: ML16357A533 (2)

Text

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

B/B-UFSAR 17.0-1 REVISION 10 - DECEMBER 2004 CHAPTER 17.0 - Q UALITY ASSURANCE The quality assurance program for the By ron and Braidwood Stations is conducted in accordance with the Quality Assurance Program for Nuclear Generating S tations. This program was initially submitted to the Nuclear Regul atory Commission in June 1975, as Topical Report CE-1. By letter of December 29, 1975, the NRC's Chief of Qua lity Assurance Branch, Division of Reactor Licensing, informed Commonwealth Edison's Executive Vice President, Mr. W. B. B ehnke, that this Topic al Report CE-1 was an acceptable program for the design, procureme nt, construction and operations activities wi thin Commonwealth Ed ison's scope of work for nuclear power plants. Instr uctions were giv en to reference this Topical Report in Section 17 of L icense applications.

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

Chapter 2 and Ap pendix C of the above-re ferenced topical report provides for compliance with certain regulat ory guides a nd ANSI standards. Any except ions taken to the requ irements of these guides are found in Ap pendix A of this U FSAR. Otherwise, Byron/Braidwood Stations are in compliance w ith the guides and ANSI standards.

Subsection 3.2.1.1 of the UFSAR states that Safe ty Category I systems or portions of systems and com ponents meet the requirements of Appendix B to 10 CFR 50. Those structures, systems, and compone nts classified as Safety Category I, therefore, are u nder control of the QA program and are listed in Table 3.2-1. Where only portions of a sy stem are classified as Safety Category I, the P&

IDs identify the boundary between Safety Category I and Safety Category II.