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| number = ML12170A620
| number = ML12170A620
| issue date = 09/15/2011
| issue date = 09/15/2011
| title = Watts Bar, Unit 2, Final Safety Analysis Report, Amendment 106, Section 17.0, Quality Assurance
| title = Final Safety Analysis Report, Amendment 106, Section 17.0, Quality Assurance
| author name =  
| author name =  
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
Line 13: Line 13:
| page count = 10
| page count = 10
}}
}}
=Text=
{{#Wiki_filter:WATTS BAR TABLE OF CONTENTS Section                                Title                    Page 17.0      QUALITY ASSURANCE                                        17-1 17.1            QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION  17-1 17.1.1              TVA ORGANIZATION                              17-1 17.1.2              QUALITY ASSURANCE PROGRAM                      17-1 17.1A              WESTINGHOUSE QUALITY MANAGEMENT SYSTEM        17-2 17.2      QUALITY ASSURANCE FOR STATION OPERATION                17.2-1 17.2.1          IDENTIFICATION OF SAFETY-RELATED FEATURES        17.2-1 Table of Contents                                                  17-i
WATTS BAR TABLE OF CONTENTS Section          Title                          Page THIS PAGE INTENTIONALLY BLANK 17-ii                                  Table of Contents
WATTS BAR LIST OF TABLES Section                      Title THIS PAGE INTENTIONALLY LEFT BLANK List of Tables                                    17-iii
WATTS BAR LIST OF TABLES Section                Title THIS PAGE INTENTIONALLY LEFT BLANK 17-iv                                        List of Tables
WATTS BAR LIST OF FIGURES Section                      Title THIS PAGE INTENTIONALLY LEFT BLANK List of Figures                                    17-v
WATTS BAR LIST OF FIGURES Section              Title THIS PAGE INTENTIONALLY LEFT BLANK 17-vi                                        List of Figures
WATTS BAR                                                                            WBNP-106 17.0 QUALITY ASSURANCE 17.1 Quality Assurance During Design and Construction 17.1.1 TVA Organization The information presented in "Nuclear Power Organization Topical Report," TVA-NPOD89-A, is applicable to Watts Bar Nuclear Plant.
17.1.2 Quality Assurance Program The information presented in Tennessee Valley Authority Nuclear Quality Assurance Program, TVA-NQA-PLN89-A (latest NRC approved revision), is applicable to Watts Bar Nuclear Plant.
==References:==
: 1. Nuclear Power Organization Topical Report, TVA-NPOD89-A.
: 2. Nuclear Quality Assurance Program, TVA-NQA-PLN89A.
QUALITY ASSURANCE                                                                        17.1-1
WATTS BAR                                                                              WBNP-106 17.1A Westinghouse Quality Management System The contents of this chapter can be found in the Westinghouse Quality Management System (QMS) [1] current revisions, with the exception of the identification of safety-related equipment, which is covered in Section 3.2 of this FSAR.
REFERENCES (1)  Westinghouse Quality Management Systems (QMS) 17.1-2                                                                      QUALITY ASSURANCE
WATTS BAR                                                                                WBNP-106 17.2 QUALITY ASSURANCE FOR STATION OPERATION See the TVA Nuclear Quality Assurance Program, TVA-NQA-PLN89-A.[1]
17.2.1 Identification of Safety-Related Features The Watts Bar Nuclear Plant Q-List is a listing of structures, systems, and components covered by the Nuclear Quality Assurance program as set forth in the Nuclear Quality Assurance Program, TVA-NQA-PLN89-A.
The Q-List consists of a combination of an itemized section and notes. Items addressed on this list are handled in accordance with the TVA Quality Assurance Program. The Q-List contains safety-related features. Safety-related features are those structures, systems, and components that are necessary to ensure:
(1)  The integrity of the reactor coolant pressure boundary.
(2)  The capability to shut down the reactor and maintain it in a safe condition.
(3)  The capability to prevent or mitigate the consequences of an incident which could result in potential offsite exposures comparable to those specified in 10 CFR 100.
Additionally, the Q-List includes quality-related and some non quality-related features which are not safety-related. TVA identified quality-related features are also defined by the TVA Nuclear Quality Assurance Program.
The Q-List is in a QA software database, as a computer generated list and is maintained per engineering site procedure. Hard copy reports, (i.e., Q-List), are extracted from the data base and can be issued as controlled design outputs. The data is accessible from computer terminals throughout the plant.
In addition, a site wide procedure provides guidelines for using the WBN Q-List to determine the 10CFR 50, Appendix B QA program application. Q-List changes are controlled through the design change process/administrative process to ensure continued completeness and accuracy.
REFERENCES
: 1. "Nuclear Quality Assurance Program," TVA-NQA-PLN89-A.
QUALITY ASSURANCE FOR STATION OPERATION                                                        17.2-1
WATTS BAR                                                                                    WBNP-106 THIS PAGE INTENTIONALLY BLANK Watts Bar FSAR Section 17.0 Quality Assurance 17.2-2                                                        QUALITY ASSURANCE FOR STATION OPERATION}}

Latest revision as of 03:04, 12 November 2019

Final Safety Analysis Report, Amendment 106, Section 17.0, Quality Assurance
ML12170A620
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 09/15/2011
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
References
Download: ML12170A620 (10)


Text

WATTS BAR TABLE OF CONTENTS Section Title Page 17.0 QUALITY ASSURANCE 17-1 17.1 QUALITY ASSURANCE DURING DESIGN AND CONSTRUCTION 17-1 17.1.1 TVA ORGANIZATION 17-1 17.1.2 QUALITY ASSURANCE PROGRAM 17-1 17.1A WESTINGHOUSE QUALITY MANAGEMENT SYSTEM 17-2 17.2 QUALITY ASSURANCE FOR STATION OPERATION 17.2-1 17.2.1 IDENTIFICATION OF SAFETY-RELATED FEATURES 17.2-1 Table of Contents 17-i

WATTS BAR TABLE OF CONTENTS Section Title Page THIS PAGE INTENTIONALLY BLANK 17-ii Table of Contents

WATTS BAR LIST OF TABLES Section Title THIS PAGE INTENTIONALLY LEFT BLANK List of Tables 17-iii

WATTS BAR LIST OF TABLES Section Title THIS PAGE INTENTIONALLY LEFT BLANK 17-iv List of Tables

WATTS BAR LIST OF FIGURES Section Title THIS PAGE INTENTIONALLY LEFT BLANK List of Figures 17-v

WATTS BAR LIST OF FIGURES Section Title THIS PAGE INTENTIONALLY LEFT BLANK 17-vi List of Figures

WATTS BAR WBNP-106 17.0 QUALITY ASSURANCE 17.1 Quality Assurance During Design and Construction 17.1.1 TVA Organization The information presented in "Nuclear Power Organization Topical Report," TVA-NPOD89-A, is applicable to Watts Bar Nuclear Plant.

17.1.2 Quality Assurance Program The information presented in Tennessee Valley Authority Nuclear Quality Assurance Program, TVA-NQA-PLN89-A (latest NRC approved revision), is applicable to Watts Bar Nuclear Plant.

References:

1. Nuclear Power Organization Topical Report, TVA-NPOD89-A.
2. Nuclear Quality Assurance Program, TVA-NQA-PLN89A.

QUALITY ASSURANCE 17.1-1

WATTS BAR WBNP-106 17.1A Westinghouse Quality Management System The contents of this chapter can be found in the Westinghouse Quality Management System (QMS) [1] current revisions, with the exception of the identification of safety-related equipment, which is covered in Section 3.2 of this FSAR.

REFERENCES (1) Westinghouse Quality Management Systems (QMS) 17.1-2 QUALITY ASSURANCE

WATTS BAR WBNP-106 17.2 QUALITY ASSURANCE FOR STATION OPERATION See the TVA Nuclear Quality Assurance Program, TVA-NQA-PLN89-A.[1]

17.2.1 Identification of Safety-Related Features The Watts Bar Nuclear Plant Q-List is a listing of structures, systems, and components covered by the Nuclear Quality Assurance program as set forth in the Nuclear Quality Assurance Program, TVA-NQA-PLN89-A.

The Q-List consists of a combination of an itemized section and notes. Items addressed on this list are handled in accordance with the TVA Quality Assurance Program. The Q-List contains safety-related features. Safety-related features are those structures, systems, and components that are necessary to ensure:

(1) The integrity of the reactor coolant pressure boundary.

(2) The capability to shut down the reactor and maintain it in a safe condition.

(3) The capability to prevent or mitigate the consequences of an incident which could result in potential offsite exposures comparable to those specified in 10 CFR 100.

Additionally, the Q-List includes quality-related and some non quality-related features which are not safety-related. TVA identified quality-related features are also defined by the TVA Nuclear Quality Assurance Program.

The Q-List is in a QA software database, as a computer generated list and is maintained per engineering site procedure. Hard copy reports, (i.e., Q-List), are extracted from the data base and can be issued as controlled design outputs. The data is accessible from computer terminals throughout the plant.

In addition, a site wide procedure provides guidelines for using the WBN Q-List to determine the 10CFR 50, Appendix B QA program application. Q-List changes are controlled through the design change process/administrative process to ensure continued completeness and accuracy.

REFERENCES

1. "Nuclear Quality Assurance Program," TVA-NQA-PLN89-A.

QUALITY ASSURANCE FOR STATION OPERATION 17.2-1

WATTS BAR WBNP-106 THIS PAGE INTENTIONALLY BLANK Watts Bar FSAR Section 17.0 Quality Assurance 17.2-2 QUALITY ASSURANCE FOR STATION OPERATION