RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance

Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance

ML17179A641
Person / Time
Site:	Dresden
Issue date:	06/21/2017
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML17179A528	List: ML17179A504 ML17179A519 ML17179A520 ML17179A529 ML17179A538 ML17179A629 ML17179A633 ML17179A635 ML17179A639 ML17179A641 ML17179A642 ML17180A121 ML17180A125 ML17180A126 ML17180A132 ML18079B036 RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Appendix a, UFSAR Supplement RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 01, Introduction and General Description of Plant RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 05, Reactor Coolant System and Connected Systems RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance RS-17-082, Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, List of Effective Pages Pages RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Amendment 21 to Fire Protection Report, Affected Pages List RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Technical Requirements Manual, Affected Page List RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases RS-17-082, Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases - Affected Page List RS-17-082, Dresden, Units 1, 2 and 3 - Updated Final Safety Analysis Report (Ufsar), Revision 12 and Fire Protection Report (Fpr), Amendment 21 RS-17-082, Redacted Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 02, Site Characteristics RS-17-082, Redacted Dresden Nuclear Power Station, Units 2 & 3, Amendment 21 to Fire Protection Report, Updated Fire Hazards Analysis, Vol. 1
References
RS-17-082
Download: ML17179A641 (4)

Text

DRESDEN - UFSAR 17.0 QUALITY ASSURANCE TABLE OF CONTENTS Page 17-i 17.0 QUALITY ASSURANCE 17.1-1 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION 17.1-1

17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE 17.2-1 17.2.1 References 17.2-2 DRESDEN - UFSAR 17.1-1 17.0 QUALITY ASSURANCE 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION

The Quality Assurance Program in place during the design, construction, equipment supply and installation, preoperational testing, and startup of Dresden Station is described in Appendix E of the FSAR.

DRESDEN - UFSAR Rev. 6 June 2005 17.2-1 17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE The Quality Assurance (QA) Program for the operations phase of Dresden Station is conducted in accordance with Quality Assurance Topical Report, NO-AA-10

[1]. This topical report was initially submitted to the NRC in June 1975 for review. The NRC found the CECo QA Program described in the topical report acceptable for the design, procurement, construction, and operational activities within CECo's scope-of-work for the nuclear stations, and provided instructions that CECo only need to reference Topical Report CE-1-A in Section 17 of license applications.

Topical Report NO-AA-10 is periodically updated to address changes in the Exelon Nuclear organization and current standards, including those necessary to satisfy regulatory requirements. Therefore, Topical Report NO-AA-10 and all subsequent revisions are the basis for the QA Program at Dresden Station. Since Topical Report NO-AA-10 is a generic document applicable to all Exelon Nuclear stations regardless of vintage, Chapter 2 and Appendix C of this topical report identifies specific QA-related Regulatory Guides, ANSI standa rds, and revisions that apply to the respective nuclear stations. When conflicts exist, the Dresden UFSAR and Technical Specifications take precedence over NO-AA-10.

DRESDEN - UFSAR Rev. 6 June 2005 17.2-2 17.2.1 References

1. Exelon Nuclear Quality Assurance Topical Report NO-AA-10, "Quality Assurance Program for Nuclear Generating Stations" (current revision).