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DCPP UNITS 1 & 2 FSAR UPDATE Chapter 17 QUALITY ASSURANCE CONTENTS Section Title Page i
Revision 27 May 2023 17.0 QUALITY ASSURANCE PROGRAM 17.1-1 17.1 REGULATORY REQUIREMENTS 17.1-1 17.2 SELECTION AND TRAINING OF NUCLEAR POWER PLANT PERSONNEL 17.1-2
17.3 REFERENCES
17.1-3
DCPP UNITS 1 & 2 FSAR UPDATE Chapter 17 QUALITY ASSURANCE TABLES Table Title ii Revision 27 May 2023 17.1-1 Deleted in Revision 27
DCPP UNITS 1 & 2 FSAR UPDATE Chapter 17 QUALITY ASSURANCE FIGURES Figure Title iii Revision 27 May 2023 17.1-1 Deleted in Revision 27 17.1-2 Deleted in Revision 27
17.1-1 Revision 27 May 2023 Chapter 17 QUALITY ASSURANCE 17.0 QUALITY ASSURANCE PROGRAM The purpose of this chapter is to provide a description of the Pacific Gas and Electric Company (PG&E) Quality Assurance (QA) Program. The QA Program is applicable to operation of Diablo Canyon Power Plant (DCPP) Unit 1 and Unit 2 and to the Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI). The purpose of the PG&E QA Program is to provide assurance that the design, construction, and operation of DCPP Unit 1 and Unit 2 and the ISFSI are in conformance with applicable regulatory requirements and with the specified design bases.
17.1 REGULATORY REQUIREMENTS The following regulatory requirements are applicable to DCPP and are described in the Diablo Canyon (DC) Quality Assurance Program Description (QAPD) [Reference 3]:
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General Design Criterion 1, 1967 - Quality Standards DCPP systems and components that are essential to the prevention of accidents which could affect the public health and safety or to mitigate their consequences are required to be designed, fabricated, and erected to quality standards that reflect the importance of the safety function to be performed.
Where generally recognized codes or standards on design, materials, fabrication, and inspection are used, they are identified. Where adherence to such codes or standards does not suffice to assure a quality product in keeping with the safety function, they are supplemented or modified as necessary. QA programs, test procedures, and inspection acceptance levels to be used are identified. A showing of sufficiency and applicability of codes, standards, QA programs, test procedures, and inspection acceptance levels used is made.
The DC QAPD provides assurance that this criterion is met. Refer to UFSAR Section 3.2 for a description of classifications used to identify the importance of safety functions performed by specific structures, systems, and components (SSCs).
- 2.
General Design Criterion 5, 1967 - Records Requirements Records of the design, fabrication, and construction of essential components of the plant are required to be maintained or controlled by PG&E throughout the life of the reactor.
17.1-2 Revision 27 May 2023
- 3.
10 CFR Part 50, Appendix B - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants DCPP is required to include, in its final safety analysis report, information pertaining to the managerial and administrative controls to be used to assure safe operation in accordance with 10 CFR Part 50 Appendix B Criteria I - XVIII.
- 4.
10 CFR 50.54 [(a) only] - Conditions of Licenses DCPP is required to implement the QA program described or referenced in the safety analysis report, which shall include the QA criteria in 10 CFR Part 50 Appendix B.
- 5.
10 CFR Part 72 Subpart G - Quality Assurance [ISFSI]
PG&E satisfies the requirement of 10 CFR 72.140(b) of 10 CFR Part 72 Subpart G, to establish a QA program for the ISFSI by crediting the DC QAPD
[Reference 3] as allowed by 10 CFR 72.140(d), which includes a provision that a QA program previously approved by the U.S. Nuclear Regulatory Commission (NRC) as satisfying the requirements of 10 CFR Part 50 Appendix B will be accepted as satisfying the requirements of 10 CFR 72.140(b).
License Condition 14 of ISFSI License No. SNM-2511 documents NRC determination that the PG&E 10 CFR Part 50 Appendix B QA program
[Reference 3] complies with the requirements of 10 CFR Part 72 Subpart G.
The DC QAPD is incorporated by reference into the DCPP UFSAR (refer to Section 1.6).
17.2 SELECTION AND TRAINING OF NUCLEAR POWER PLANT PERSONNEL Staffing, training, and qualification is the single most important variable which can be controlled to achieve the nuclear generation goals of maximizing plant safety, efficiency, and reliability. Therefore, it is the policy of nuclear generation that personnel at all levels shall be qualified for the positions they fill and receive the necessary training and retraining to enable them to perform at the highest level of efficiency. Nuclear generation personnel shall meet or exceed the minimum qualifications of ANSI/ANS 3.1 1978, for comparable positions, with the following exceptions [Reference 2]:
(a) The radiation protection manager shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 2, April 1987, for radiation protection manager.
(b) The operations manager shall meet or exceed the minimum qualifications as specified in Technical Specification 5.2.2.e.
17.1-3 Revision 27 May 2023 (c) The licensed Reactor Operators and Senior Reactor Operators shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1993 as endorsed by Regulatory Guide 1.8, Revision 3, May 2000 with the exceptions clarified in the current revision to the Operator Licensing Examination Standards for Power Reactors, NUREG-1021, Section ES-202 [Reference 1].
(d) For the purpose of 10 CFR 55.4, a licensed SRO and a licensed RO are those individuals who, in addition to meeting the requirements specified in (c), perform the functions described in 10 CFR 50.54(m).
NOTE: These exceptions are also listed in Appendix B of the DC QAPD, Current Regulatory Requirements and PG&E Commitments Pertaining to the Quality Assurance Program, where all pertinent commitments are captured.
17.3 REFERENCES
- 1.
License Amendment 187/189, dated May 26, 2006
- 2.
License Amendment 237/239, dated September 11, 2020
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Diablo Canyon Quality Assurance Program Description