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Category:Updated Final Safety Analysis Report (UFSAR)
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001 LAS FRP Rev_9 ML 20111A273-Redacted ML20153A7922020-06-0404 June 2020 EPID L-2020-LRO-0020, SUNSI Review of UFSAR Rev 24 and FPR Rev 9 - 009 Chap 09 Auxiliary Systems-ML20111A256 Redacted ML20154K6122020-06-0404 June 2020 EPID L-2020-LRO-0020, SUNSI Review of Usfar Rev 24 and FPR Rev 9 - 020 Chap 13 Conduct of Operations-ML20111A267-Redacted ML20147A6712020-06-0404 June 2020 EPID-L-2020-LRO-0020, SUNSI Review of UFSAR Rev 24 and FPR Rev 9 - 001 Appendices (Amended)-ML20133J880_Redacted ML20150A2562020-06-0404 June 2020 EPID L-2020-LRO-0020, SUNSI Review of UFSAR Rev 24 and FPR Rev 9 - 006 Chap 06 Eng Safety Features-ML20111A253_Redacted ML20150A2592020-06-0404 June 2020 EPID L-2020-LRO-0020, SUNSI Review of UFSAR Rev 24 and FPR Rev 9 - 008 Chap 08 Electric Power-ML20111A255_Redacted ML20111A2692020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML20111A2502020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components Equipment and Systems ML20111A2482020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20111A2642020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML20111A2652020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20111A2522020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML20111A2452020-04-13013 April 2020 Submittal of Revision 24 to Updated Final Safety Analysis Report and Revision 9 to Fire Protection Report ML20111A2512020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 4, Reactor RS-20-029, Submittal of Revision 24 to Updated Final Safety Analysis Report and Revision 9 to Fire Protection Report2020-04-13013 April 2020 Submittal of Revision 24 to Updated Final Safety Analysis Report and Revision 9 to Fire Protection Report ML20111A2702020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML20111A2712020-04-13013 April 2020 4 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance 2022-04-13
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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