ML14113A118: Difference between revisions

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{{#Wiki_filter:LSCS-UFSAR 17.0-i REV.
{{#Wiki_filter:LSCS-UFSAR 17.0-i REV. 13 CHAPTER 17.0-QUALITY ASSURANCE TABLE OF CONTENTS PAGE 17.0 QUALITY ASSURANCE 17.01  
13 CHAPTER 17.0-QUALITY ASSURANCE TABLE OF CONTENTS PAGE 17.0   QUALITY ASSURANCE 17.01 LSCS-UFSAR 17.0-1 REV. 14, APRIL 2002 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 NRC's Chief, Quality Assurance Branch, Division of Reactor Licensing, informed CECo's Executive Vice Chairman, Mr. Behnke, that this Topical Report CE-1 was an acceptable program for the design, procurement, construction, and operations activities within CECo's scop e of work for nuclear power plants. Instructions were given to reference this Topical Report in Section 17 of license


applications.  
LSCS-UFSAR 17.0-1 REV. 14, APRIL 2002 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.  


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 refi ned 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 NRC' s 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 NRC's 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.
LSCS-UFSAR 17.0-2 REV. 15, APRIL 2004 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:
LSCS-UFSAR 17.0-2 REV. 15, APRIL 2004 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 Re
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.
: v. 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.
Specific operational exceptions, alternatives, and clarifications to these guides and standards to the extent they have been taken are delineated in Appendix B.
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.  
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.}}
 
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 Topica l 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 th is chapter, are the basis for the Quality Assurance Program at La Salle County Statio
: n. The current revision of the Exelon Nuclear Quality Assurance Topical Report is NO-AA-10.}}

Latest revision as of 21:29, 10 January 2025

Updated Final Safety Analysis Report, Revision 20, Chapter 17.0, Quality Assurance
ML14113A118
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 04/11/2014
From:
Exelon Generation Co
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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ML14113A099 List:
References
RS-14-128
Download: ML14113A118 (3)
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Text

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

LSCS-UFSAR 17.0-1 REV. 14, APRIL 2002 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.

LSCS-UFSAR 17.0-2 REV. 15, APRIL 2004 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.

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