ML20111A271

4 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance

ML20111A271
Person / Time
Site:	LaSalle
Issue date:	04/13/2020
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML20111A244	List: ML20111A245 ML20111A246 ML20111A248 ML20111A250 ML20111A251 ML20111A252 ML20111A254 ML20111A257 ML20111A264 ML20111A265 ML20111A268 ML20111A269 ML20111A270 ML20111A271 ML20111A274 RS-20-029, Technical Specification Bases
References
RS-20-029
Download: ML20111A271 (3)

Text

LSCS-UFSAR CHAPTER 17.0-QUALITY ASSURANCE TABLE OF CONTENTS PAGE 17.0 QUALITY ASSURANCE 17.01 17.0-i REV. 13

LSCS-UFSAR CHAPTER 17.0-QUALITY ASSURANCE The quality assurance program for the La Salle County Station (LSCS) is conducted in accordance with the EGC 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 NRCs Chief, Quality Assurance Branch, Division of Reactor Licensing, informed CECos Executive Vice Chairman, Mr. Behnke, that this Topical Report CE-1 was an acceptable program for the design, procurement, construction, and operations activities within CECos scope of work for nuclear power plants.

Instructions were given to reference this Topical Report in Section 17 of license applications.

Exceptions or alternatives to this Topical Report for specific plants identified in the Safety Analysis Report will take precedence over commitments in this Topical Report.

By this technique, it is expected that a broad-scope QA Topical Report can cover the past, present, and future, while allowing the fixed-time aspects for any plant, such as La Salle to be historically represented under the QA provisions extant during its design, procurement, construction, operation, modification and refurbishment.

Time indexing of applicable standards and guides is mandatory for La Salle because this Topical Report was developed and refined during the period when La Salle was under construction. Some of the design and procurement preceded the imposition of formal QA requirements by the NRC on these activities; however, most of these activities were concurrent with the NRCs circulation of detailed QA guidelines.

The same was true with respect to construction activities at La Salle and those detailed Regulatory Guides in that area. Test, operations, and maintenance activities are also concurrent with the NRCs issuance of detailed guidance.

Thereas general conformance is the goal on end point with respect to these activities, the evolutionary process in attaining full compliance has been a significant activity on La Salle; it is a continuing process as additional NRC guidelines are published or ANSI standards are released.

For La Salle, the extent of compliance to NRC Regulatory Guides is compiled in Appendix B.

17.0-1 REV. 14, APRIL 2002

LSCS-UFSAR As indicated in Appendix B, the QA program to be implemented for the operations phase of LSCS complies with the objectives of the following Regulatory Guides and Standards:

Regulatory Guides 1.8, Rev. 1-R, 1.28 Rev. 3, 1.30, 8-11-72; 1.33, Rev. 2; 1.37, 3-16-73; 1.38, Rev.2; 1.39, Rev. 2; 1.58, 8-73; 1.64, Rev. 2; 1.74, 2-74; 1.88 Rev. 2, 1.94, Rev. 1; 1.116, Rev. O-R; 1.123, Rev.1; and to NQA-1-1994 Part I and II that was approved for use by an NRC SER dated 12/24/02.

Specific operational exceptions, alternatives, and clarifications to these guides and standards to the extent they have been taken are delineated in Appendix B.

Revision 70 of Quality Assurance Topical Report EGC-1-A was approved by the NRC in December 2002. Therefore, EGC-1-A Revision 70, and all subsequent revisions, except as otherwise noted in this chapter, are the basis for the Quality Assurance Program at La Salle County Station. The current revision of the Exelon Nuclear Quality Assurance Topical Report is NO-AA-10.

17.0-2 REV. 15, APRIL 2004