ML033070160
| ML033070160 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Palisades, Kewaunee, Point Beach, Prairie Island, Duane Arnold  |
| Issue date: | 10/31/2003 |
| From: | Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033070160 (78) | |
Text
ENCLOSURE 2 NUCLEAR MANAGEMENT COMPANY DUANE ARNOLD ENERGY CENTER DOCKET 50-331 KEWAUNEE NUCLEAR POWER PLANT DOCKET 50-305 MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 PALISADES NUCLEAR PLANT DOCKET 50-255 POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 DOCKETS 50-266 AND 50-301 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 DOCKETS 50-282 AND 50-306 October 31, 2003 EXISTING SITE QA PROGRAMS VS QATR COMPARISON MATRICES 77 Pages Follow
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Ref: UFSAR 17.2 - Quality Assurance During the Operations Phase Rev. 29 4/18/03 NMC QATR [Rev. 0a, October 10, 2003]
Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.0.1(1) Policy (1) Note 2 N 17.2.0.1(2) A.7.1 The QATR has not been approved by the NRC N for activities covered by 10 CFR 71. The QATR was developed to meet 10 CFR 71 Subpart H.
This QATR is being submitted to the NRC for approval for 10 CFR 71 applications along with its approval for 10 CFR 50 applications.
17.2.0.1(3) A.7.1 The QATR has not been approved by the NRC N for activities covered by 10 CFR 72. The QATR was developed to meet 10 CFR 72 Subpart G.
This QATR is being submitted to the NRC for approval for 10 CFR 72 applications along with its approval for 10 CFR 50 applications.
17.2.0.1(4) N/A This paragraph discusses the quality assurance R This is not required by 10CFR50 program required for the characterization and Appendix B. Therefore, this does not classification of radioactive waste being shipped degrade the DAEC Quality Assurance to a disposal site. Program. This paragraph was added since the last NRC review to provide the site with additional information.
Since this was not in the last NRC reviewed version, removing this paragraph is not a reduction in commitment.
17.2.0.1(5) A.7.1 Note 2 N 17.2.0.1(6) A.4 (1) The QATR does not differentiate between the N nuclear power plant and the spent fuel storage installation. Both are covered under the QATR.
17.2.0.1(7) A.1 (2) Note 2 N 17.2.0.1(8) Policy 1 Note 2 N 17.2.0.2(1) N/A This explanation is not required in the QATR. N 17.2.0.2(2) Policy 2 Note 2 N 17.2.0.2(3) A.1 (1) Note 2 N 17.2.0.2(4) Policy 1 Note 2 N 1
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.1.1(1) A.2 (2) Note 2 N 17.2.1.1(2) A.2 (1) Note 2. The information contained in UFSAR N Section 13.1 will remain in that section.
17.2.1.2 A.2.1.2.b.1 Note 2 N 17.2.1.3(1) A.2.1.2.b.1 Responsibility for the Operational Quality N Assurance Program and the Nuclear Oversight Department implementing procedures is assigned to the Director, Nuclear Oversight in the QATR. Transfer of responsibility is not viewed as a reduction in commitment.
17.2.1.3(2) A.2.2.1.e Note 2 N 17.2.1.3(3) N/A Note 4 17.2.1.3(4) N/A Note 4 17.2.1.3(5) A.2.2.1.e Note 2 N Figure #2 17.2.1.3.1 A.2.2.1.e Note 2 N 17.2.1.4 A.2.1.2.b.1 Responsibility for supplier assessment has been N assigned to the Director, Nuclear Oversight in the QATR. Transfer of responsibility is not viewed as a reduction in commitment.
17.2.2.1(1) A.1 (3) Note 2 - Definition of safety related structures, N systems and components is not in the QATR.
Basis for deciding what SSCs the QATR applies to is provided.
17.2.2.1(2) A.1 (4) Note 2 N 17.2.2.2(1) A.7.1 Note 2 N A.7.3 17.2.2.2(2) A.7.3 Note 2 N 17.2.2.3.1(1) A.1 (4) Note 2 N 17.2.2.3.1(2) A.1 (4) Note 2 N 17.2.2.3.2 A.1 (4) Note 2 N 17.2.2.4(1) A.7.1 Note 2 N 17.2.2.4(2) A.1 (3) Note 2 - The QATR does not mention N department instructions specifically. The QATR term site procedures covers all instructions and procedures unique to a site.
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Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.2.4.1 A.1 (3) Note 2 N 17.2.2.4.2 A.1 (3) Note 2 N 17.2.2.4.3 A.1 (3) Note 2 N 17.2.2.4.4 A.1 (3) Note 2 - The QATR does not mention N department instructions specifically. The QATR term site procedures covers all instructions and procedures unique to a site.
17.2.2.5 A.1 (1) Note 2 N 17.2.2.6(1) A.5 Note 2 N 17.2.2.6(2) N/A Note 3 N 17.2.2.6(3) N/A Note 3 N 17.2.2.6(4) N/A Note 3 N 17.2.2.6(5) N/A Note 3 N 17.2.2.6(6) N/A Note 3 N 17.2.2.7(1) C.3 (1) Note 2 N C.3 (2)
C.3 (3) 17.2.2.7(2) C.3 (3) Note 2 N 17.2.3.1(1) B.2 (1) Note 2 N 17.2.3.1(2) B.2 (1) Note 2 N 17.2.3.1(3) B.2 (1) Note 2 N 17.2.3.2 N/A Note 4 N 17.2.3.3 B.2 (5) Note 2 N 17.2.3.4(1) B.2 (5) Note 2 N 17.2.3.4(2) B.2 (5) Note 2 N 17.2.3.4(3) B.2 (5) Note 2 N 17.2.3.5 B.2 (5) Note 2 N 17.2.3.6(1) B.3 (1) Note 2 N 17.2.3.6(2) B.3 (5) Note 2 N 17.2.3.6(3) B.3 (4) Note 2 N 17.2.3.6(4) B.3 (3) Note 2 N 17.2.3.6(5) B.3 (4) Note 2 N 17.2.3.6(6) B.3 (4) Note 2 N 17.2.3.6(7) B.3 (4) Note 2 N 17.2.3.6(8) B.3 (4) Note 2 N 17.2.3.6.1(1) B.3 (4) Note 2 N 3
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.3.6.1(2) B.3 (4) Note 2 N 17.2.3.6.2 B.3 (4) Note 2 N 17.2.3.6.3(1) B.3 (4) Note 2 N 17.2.3.6.3(2) B.3 (4) Note 2 N 17.2.3.7(1) B.3 (4) Note 2 N 17.2.3.7(2) N/A Note 3 N 17.2.3.8 Appendix A Note 2 N Appendix B 17.2.4.1 B.4 (1) Note 2 N 17.2.4.2 N/A Note 4 N 17.2.4.3 B.4 (1) Note 2 N B.4 (2) 17.2.4.4 B.4 (2) Note 2 N B.7 (1) 17.2.4.5 N/A Note 3 N 17.2.5.1 B.14 (1) Note 2 N 17.2.5.2(1) B.14 (1) Note 2 N 17.2.5.2(2) B.14 (1) Note 2 N 17.2.5.2(3) N/A Note 3 N 17.2.5.3 B.14 (1) Note 2 N 17.2.6.1 B.14 (2) Note 2 N 17.2.6.2 B.14 (1) Note 2 N B.14 (2) 17.2.6.3(1) B.14 (1) Note 2 N B.14 (2) 17.2.6.3(2) B.14 (1) Note 2 N B.14 (2) 17.2.6.4(1) N/A Note 3 N 17.2.6.4(2) N/A Note 3 N 17.2.6.4(3) N/A Note 3 N 17.2.6.4(4) N/A Note 3 N 17.2.6.4(5) N/A Note 3 N 17.2.6.5(1) B.14 (2) Note 2 N 17.2.6.5(2) N/A Note 3 N 17.2.6.5(3) B.14 (2) Note 2 N 4
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.7.1 B.6 (1) Note 2 N B.5 (1) 17.2.7.2(1) B.4 (2) Note 2 N 17.2.7.2(2) B.4 (2) Note 2 N 17.2.7.2(3) B.4 (2) Note 2 N 17.2.7.2(4) N/A Note 3 N 17.2.7.3(1) B.4 (2) Note 2 N 17.2.7.3(2) B.4 (2) Note 2 N 17.2.7.3(3) B.4 (2) Note 2 N 17.2.7.3(4) B.4 (2) Note 2 N 17.2.7.3(5) B.4 (2) Note 2 N 17.2.7.4(1) B.4 (2) Note 2 N 17.2.7.4(2) B.4 (2) Note 2 N 17.2.7.4(3) B.4 (2) Note 2 N 17.2.7.4(4) B.4 (2) Note 2 N 17.2.7.5 B.4 (2) Note 2 N 17.2.8.1(1) B.6 (1) Note 2 N B.6 (2) 17.2.8.1(2) B.6 (1) Note 2 N B.6 (2) 17.2.8.1(3) B.6 (1) Note 2 N B.6 (2) 17.2.8.1(4) B.6 (1) Note 2 N B.6 (2) 17.2.8.2(1) B.6 (1) Note 2 N B.6 (2) 17.2.8.2(2) B.6 (1) Note 2 N B.6 (2) 17.2.8.2(3) B.6 (1) Note 2 N B.6 (2) 17.2.8.2(4) B.6 (1) Note 2 N B.6 (2) 17.2.8.2(5) B.4 (2) Note 2 N 17.2.8.2(6) B.6 (1) Note 2 N B.6 (2) 5
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.8.2(7) B.6 (1) Note 2 N B.6 (2) 17.2.8.2(8) N/A Note 3 N 17.2.8.3(1) B.6 (1) Note 2 N B.6 (2) 17.2.8.3(2) B.6 (1) Note 2 N B.6 (2) 17.2.8.3(3) B.6 (1) Note 2 N B.6 (2) 17.2.9.1(1) B.11 (1) Note 2 N 17.2.9.1(2) N/A Note 4 N 17.2.9.2(1) B.11 (1) Note 2 N 17.2.9.2(2) B.11 (2) Note 2 N 17.2.9.2(3) N/A Note 3. This paragraph describes how we are N implementing NQA-1Supplement 9S-1 Sections 2, 3, 3.1.2 and 3.2.
17.2.9.2(4) B.11 (2) Note 2 N 17.2.9.2(5) B.11 (2) Note 2 N 17.2.9.2(6) B.11 (2) Note 2 N 17.2.9.2(7) B.11 (2) Note 2 N 17.2.9.3(1) B.11 (2) Note 2 N 17.2.9.3(2) A.5 Note2, Note 4 N 17.2.9.4(1) B.14 (1) Note 2 N 17.2.9.4(2) B.5 (1) Note 2, Note 4 N 17.2.9.4(3) N/A Note 3 N 17.2.9.5 A.7.3 Note 2 - The definition of Special Processes in N the QATR encompasses coatings. This section will be moved to UFSAR Section 1.8 via CAP 28651.
17.2.10.1(1) B.12 (1) Note 2 N 17.2.10.1(2) N/A Note 4 N 17.2.10.2(1) B.14 (1) Note 2 N 17.2.10.2(2) B.12 Note 2 N 17.2.10.2(3) B.12 Note 2 N 17.2.10.2(4) B.12 Note 2 N 17.2.10.2(5) B.12 Note 2 N 6
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.10.2(6) B.12 Note 2 N 17.2.10.3(1) B.12 Note 2 N 17.2.10.3(2) B.12 Note 2 N 17.2.10.4(1) B.12 Note 2 N 17.2.10.4(2) B.12 Note 2 N A.7.2 17.2.10.4(3) B.14 (1) Note 2 N 17.2.10.4.1(1) N/A Note 3 - This paragraph describes how we are N implementing the ASME Boiler and Pressure Vessel Code and code Quality Assurance Requirements (A.7.2).
17.2.10.4.1(2) N/A Note 4 N 17.2.10.4.2 B.8 Note 2 N 17.2.10.5 B.12 Note 2 N 17.2.10.6 B.12 Note 2 N 17.2.11.1 B.8 (1) Note 2 N 17.2.11.2(1) B.8 (1) Note 2 N 17.2.11.2(2) B.8 (1) Note 2 N 17.2.11.3 B.8 (1) Note 2 N 17.2.11.4 B.8 (1) Note 2 N 17.2.11.5(1) B.8 (1) Note 2 N 17.2.11.5(2) B.8 (1) Note 2 N 17.2.12.1 B.9 (1) Note 2 N 17.2.12.2(1) B.9 (1) Note 2 N 17.2.12.2(2) B.9 (1) Note 2 N 17.2.12.2(3) B.9 (2) Note 2 N 17.2.12.2(4) N/A Note 3 N 17.2.12.2(5) B.9 (6) Note 2 N 17.2.12.2(6) B.9 (2) Note 2 N 17.2.12.3(1) B.9 (1) Note 2 N 17.2.12.3(2) B.9 (1) Note 2 N 17.2.13.1(1) B.7 (1) Note 2 N 17.2.13.1(2) B.7 (1) Note 2 N 17.2.13.1(3) B.7 (1) Note 2 N 17.2.13.1(4) B.7 (1) Note 2 N 17.2.13.1(5) B.7 (1) Note 2 N 7
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.13.2(1) B.7 (1) Note 2 N 17.2.13.2(2) B.7 (1) Note 2 N 17.2.13.2(3) B.7 (2) Note 2 N 17.2.13.3(1) B.7 (1) Note 2 N 17.2.13.3(2) B.7 (1) Note 2 N 17.2.13.3(3) A.7.1 Note 2 N 17.2.13.4(1) B.7 (1) Note 2 N 17.2.13.4(2) B.7 (1) Note 2 N 17.2.13.5 B.7 (1) Note 2 N 17.2.13.6(1) B.7 (1) Note 2 N 17.2.13.6(2) B.7 (1) Note 2 N 17.2.13.7(1) B.7 (2) Note 2 N 17.2.13.7(2) B.7 (2) Note 2 N 17.2.13.8 B.7 (1) Note 2 N 17.2.14.1 B.10 (1) Note 2 N 17.2.14.2(1) B.10 (1) Note 2 N 17.2.14.2(2) B.10 (1) Note 2 N 17.2.14.2(3) B.10 (1) Note 2 N 17.2.14.3(1) B.10 (2) Note 2 N 17.2.14.3(2) N/A Note 3 N 17.2.14.3(3) N/A Note 3 N 17.2.14.3(4) N/A Note 3 N 17.2.14.4(1) N/A Note 3 N 17.2.14.4(2) N/A Note 3 N 17.2.14.4(3) N/A Note 3 N 17.2.14.4(4) N/A Note 3 N 17.2.14.5 B.14 (1) Note 2 N B.14 (2) 17.2.14.6(1) N/A This paragraph discusses the requirements for R This report is not required by 10CFR50 the Start-up Test Report. There is not an Appendix B. Therefore, not including equivalent discussion in the QATR. this wording does not degrade the Quality Assurance Program at the DAEC. This is being moved to UFSAR Section 1.8 via CAP 28653.
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Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.14.6(2) N/A This paragraph discusses the requirements for R This report is not required by 10CFR50 the Start-up Test Report. There is not an Appendix B. Therefore, not including equivalent discussion in the QATR. this wording does not degrade the Quality Assurance Program at the DAEC. This is being moved to UFSAR Section 1.8 via CAP 28653.
17.2.15.1 B.13 (1) Note 2 N B.13 (2) 17.2.15.2 B.13 (2) Note 2 N 17.2.15.3(1) B.13 (2) Note 2 N 17.2.15.3(2) B.13 (2) Note 2 N 17.2.15.4(1) B.13 (2) Note 2 N 17.2.15.4(2) B.13 (2) Note 2 N 17.2.15.4(3) B.13 (2) Note 2 N 17.2.16.1 B.13 (1) Note 2 N 17.2.16.2(1) B.13 (1) Note 2 N 17.2.16.2(2) N/A Note 4 N 17.2.16.2(3) B.13 (3) Note 2, Note 3, Note 4 N 17.2.16.3 B.13 (2) Note 2 N 17.2.16.4(1) A.7.1 Note 2 N 17.2.16.4(2) A.2.1.2 Note 2, Note 4 N 17.2.16.5 Appendix A 4.0 Note 2 R The Offsite Review Committee has been eliminated. See Enclosure 6 for the basis for reduction.
17.2.17.1 B.15 (1) Note 2 N 17.2.17.2(1) B.15 (1) Note 2 N 17.2.17.2(2) B.15 (3) Note 2 N 17.2.17.2(3) B.15 (3) Note 2 N 17.2.17.3(1) B.15 (3) Note 2 N 17.2.17.3(2) B.15 (3) Note 2 N 17.2.17.3(3) B.15 (3) Note 2 N 17.2.17.3.1(1) B.15 (2) Note 2 N 17.2.17.3.1(2) B.15 (2) Note 2 N 17.2.17.3.2 N/A Note 3 N 17.2.17.4(1) B.15 (2) Note 2 N 17.2.17.4(2) B.15 (2) Note 2 N 9
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.17.4(3) B.15 (2) Note 2 N 17.2.17.4(4) B.15 (2) Note 2 N 17.2.17.5(1) B.15 (3) Note 2 N 17.2.17.5(2) B.15 (3) Note 2 N 17.2.17.5(3) B.15 (3) Note 2 N 17.2.18.1(1) C.1 (1) Note 2 N 17.2.18.1(2) C.3 (1) Note 2 N 17.2.18.2(3) C.3 (1) Note 2 N 17.2.18.2 A.7.3 Note 2 N 17.2.18.2.1(1) A.7.3 Note 2 N 17.2.18.2.1(2) A.7.3 Note 2 N 17.2.18.2.1(3) A.7.3 Note 2 N 17.2.18.2.2(1) A.7.3 Note 2 N 17.2.18.2.2(2) C.3 (1) Note 2 N 17.2.18.2.2(3) C.3 (1) Note 2 R 10 CFR 50 Appendix B requires a system of planned and periodic audits. The provisions of the QATR provide for such a system in a manner that assures appropriate topic coverage using both a defined-frequency and a performance-based approach.
17.2.18.2.2(4) C.3 (3) Note 2 N 17.2.18.3(1) A.5 (1) Note 2 N A.5 (2) 17.2.18.3(2) A.5 (1) Note 2 N A.5 (2) 17.2.18.3(3) A.5 (1) Note 2 N A.5 (2) 17.2.18.4(1) C.1 (4) Note 2 N 17.2.18.4(2) C.1 (4) Note 2 N 17.2.18.4(3) C.1 (4) Note 3 N 17.2.18.4(4) C.1 (4) Note 3 N 17.2.18.5(1) C.1 (4) Note 2 N 17.2.18.5(2) C.1 (4) Note 2 N 17.2.18.5(3) C.1 (4) Note 2 N 17.2.18.5(4) C.1 (4) Note 2 N 10
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2.18.5(5) C.1 (4) Note 2 N 17.2A(1) A.7.3 Note 2 N 17.2A(2) A.7.3 Note 2 N 17.2A(3) N/A This is an information paragraph that is not N required in the QATR 17.2A - 1.0 A.7.3 Bullet 1 Note 2 N 17.2A - 1.1 A.7.3 Bullet 1 Note 2 N 17.2A - 1.2 N/A This paragraph discusses the selection and R This commitment remains in the DAEC training of security personnel. There is not an Technical Specifications.
equivalent discussion in the QATR.
17.2A - 2.0 A.7.3 Bullet 2 Note 2 N 17.2A - 3.0 A.7.3 Bullet 3 Note 2 N 17.2A - 4.0 A.7.3 Bullet 4 Note 2 N 17.2A - 5.0 A.7.3 Bullet 5 Note 2 N 17.2A - 5.1 A.7.3 Bullet 5 Note 2 N 17.2A - 5.2 B.12 (3) Note 2 N B.16 (2) 17.2A - 5.3 B.9 (2) Note 2 N 17.2A - 5.4 B.4 (2) Note 2 N 17.2A - 5.5 B.9 (2) Note 2 N 17.2A - 5.6 B.6 Note 3 N B.7 17.2A - 5.7 B.9 (2) Note 2 N 17.2A - 6.0 A.7.3 Bullet 6 Note 2 N 17.2A - 6.1 A.7.3 Bullet 6 Note 2 N 17.2A - 6.2 This statement is is an information statement. It N is not needed in the QATR.
17.2A - 6.3 C.3.1 Note 2 N 17.2A - 6.4 Appendix A Note 2 R The Offsite Review Committee has been eliminated. See Enclosure 6 for the basis for reduction.
17.2A - 6.4.1(1) Appendix A Note 2 N 11
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2A - 6.4.1(2) Appendix A Note 2. PORC review of procedures is deleted R Review of the procedures has been based on NRC SER dated August 11, 1999, removed. This is covered by SER Safety Evaluation by the Office of Nuclear 1999-009 for the Point Beach Nuclear Reactor Regulation Related to Amendment No. Plant. The DAEC procedure process 190 to Facility Operating License No. DPR-24 does have independent review of and Amendment No. 195 to Facility Operating procedures by a cognizant individual so License No. DPR-27, Wisconsin Electric Power the SER is applicable to the DAEC.
Company Point Beach Nuclear Plant, Units 1 Therefore, removing the requirement to and 2, Docket Nos. 50-266 and 50-301. review these documents does not degrade the Quality Assurance Program.
PORC review of programs reduced to those Appendix B does not address PORC common to all current QAPDs at NMC plants. activities. The previous industry guidance for this function was not explicit regarding PORC review of specific programs. Reduction to the set common to all NMC plants provides consistency. The QATR continues to meet Appendix B.
17.2A - 6.4.1(3) Appendix A Note 2 N 17.2A - 6.4.2 All R The Offsite Review Committee has Paragraphs been eliminated. See Enclosure 6 for the basis for reduction.
17.2A - 6.5 R The Offsite Review Committee has been eliminated. See Enclosure 6 for the basis for reduction.
17.2A - 6.6 This statement is an information statement. It is not needed in the QATR.
17.2A - 6.7(1) B.14 (3) Note 2 N 17.2A - 6.7(2) B.14 (3) Note 2 - The first statement in this section is not R The review by the Operations contained in the QATR and is therefore a Committee (PORC) and the Plant reduction in commitment. Manager is not required by 10 CFR 50 Appendix B. Therefore, the change does not degrade the Quality Assurance Program.
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Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2A - 6.9(1) This statement is an information statement. It is N not needed in the QATR.
17.2A - 6.9(2) A.7.3 Bullet 8 Note 2 N 17.2A - 6.10(1) R This commitment remains in the DAEC Security Plan 17.2A - 6.10(2) R This commitment remains in the DAEC Security Plan 17.2A - 6.11(1) B.14 (1) Note 3 - Procedures where usage may be N dictated by an event are reviewed during operator training, including simulator activities, and emergency planning drills. Therefore, these procedures are reviewed per 17.2A - 6.11 (3).
17.2A - 6.11(2) B.14 (1) Note 3 R Processes exist to review procedures that are infrequently performed prior to use (Infrequently Performed Task/Evolution Pre-Job Briefings).
Experience has shown that programs do keep procedures current, regardless of their type or usage frequency.
Appendix B. requires that documents controlling activities be kept current and distributed to and used on the job. The QATR establishes controls that meet Appendix B.
17.2A - 6.11(3) B.14 (1) Note 3 N 17.2A - 6.12 B.9 (2) Note 2 N 17.2A - 6.13 B.14 Note 2 N 17.2A - 7.0 B.7 (4) Note 2 N 17.2A - 7.1 B.7 (4) Note 2 N 17.2A - 7.2 B.7 (4) Note 2 N 17.2A - 8.0 B.7 (2) Note 2 N 17.2A - 8.1 B.7 (2) Note 2 N 17.2A - 8.2 B.7 (2) Note 2 N 17.2A - 8.3 B.7 (2) Note 2 N 17.2A - 9.0 B.7 (4) Note 2 N 17.2A - 9.1 B.7 (4) Note 2 N 13
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2A - 10.0 A.7.3 Bullet 8 Note 2 N 17.2A - 11.0 A.5 Note 2 N 17.2A - 11.1 A.5 Note 2 N 17.2A - 11.2 A.5 Note 3 N 17.2A - 11.3 N/A This statement is is an information statement. It N is not needed in the QATR.
17.2A - 11.4 N/A Note 3 N 17.2A - 11.5 A.5 Note 2 N 17.2A - 12.0 B.2 (6) Note 2 N B.3 (4) 17.2A - 13.0 C.3 Note 2 N 17.2A - 13.1 C.3 Note 2 N 17.2A - 13.2 C.3 Note 2 N 17.2A - 14.0 B.15 (3) Note 2 N 17.2A - 14.1 B.15 (3) Note 2 N 17.2A - 14.2 N/A Note 3 N 17.2A - 14.3 B.15 Note 3 R The handling of documents that have not become records (not yet authenticated) is not addressed in 10 CFR 50 Appendix B or NQA-1.
Therefore, removing the statements does not degrade the Quality Assurance Program. NQA-1 17S-1 addresses temporary storage.
17.2A - 14.4 B.15 (3) Note 2 N 17.2A - 14.5 B.15 (3) Note 2 N 17.2A - 15.0 B.12 (4) Note 2 N 17.2A - 15.1 B.12 (4) Note 2 N 17.2A - 15.2 B.12 (4) Note 2 N 17.2A - 16.0 B.16 (2) Note 2 N 17.2A - 16.1 B.16 (2) Note 2 N 17.2A - 16.2 B.16 (2) Note 2 N 17.2A - 17.0 B.4 (2) Note 2 N 17.2A - 17.1 B.4 (2) Note 2 N 17.2A - 18.0 C.3 Note 2 N 17.2A - 18.1 C.3 Note 2 N 14
Enclosure 2, Number 1 QA Program Comparison Matrix DUANE ARNOLD ENERGY CENTER Current QAPD Section / QATR Section / R/N/I Basis for Reduction in Commitment (paragraph) (paragraph) s (Note 1) Meeting Appendix B 17.2A - 18.2 C.3 Note 2 N 17.2A - 18.3 C.3 Note 2 N 17.2A - 18.4 NQA-1 18S01 3.0 Note 2, Note 3 N 17.2A - 18.5 NQA-1 18S01 3.0 Note 2, Note 3 N 17.2A - 19.0 A.5 RG 1.146 was withdrawn. R 17.2A - 19.1 A.5 RG 1.146 was withdrawn. R 17.2A - 19.2 C.3 RG 1.146 was withdrawn. R 17.2A - 19.3 A.5 Note 2 N 17.2A - 20.0 A.7.3 Bullet 20 Note 2 N 17.2A - 21.0 A.7.3 Bullet 18 Note 2 N 17.2A - 22.0 A.7.2 Note 2 N B.16 This is a new commitment. I B.17 This is a new commitment. I A.7.3 This is a new commitment. I NOTES:
- 1. R = Reduction in Commitment.
N = Not a Reduction in Commitment.
I = Increase in commitment.
- 2. Wording in the QATR establishes equivalent requirements or commitments. Any wording difference is the result of format needs associated with changing to Standard Review Plan 17.3 format. 10CFR50.54(a)(3)(i) or (v) apply.
- 3. Methodology details (the how) in the current program description are not included in the NMC QATR. The intent of the QATR is to establish appropriate/sufficient requirements (the what) to provide a quality assurance program meeting 10CFR50, Appendix B, but to allow flexibility in how the requirement is met. Therefore, this change in methodology detail (the how) is not considered to be a reduction in commitment.
- 4. The QATR does not assign responsibilities beyond those listed in Section A.2 and A.3. The responsibilities listed in DAEC UFSAR 17.2 are documented in lower tier documents.
15
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B Introduction(1) Introduction Note 2. N Policy Statements Introduction(2) A.1(2) Note 2. N Introduction(3) Policy Statement Note 2. N A.1(4) 1.0-1 A.1(1), A.2 Note. 2 N 1.0-2(1) A.2.1.1 Note 2. N 1.0-2(2) A.2.1.2 Note 2. N 1.0-2(3) A.2.1.2.a Note 2. Note 3. N 1.0-2(4) A.2.1.2.a Note 2. Note 3. N 1.0-2(5) A.2.1.2.b Note 3. N 1.0-2(6) A.2.1.2.a Note 3. N 1.0-2(7) A.2.1.2.a Note 3. N 1.0-2(8) A.2.1.2.a Note 3. N 1
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 1.0-3(1) A.1(1)(2) The relationship with the Asset owner is described in R The QATR specifies that contractors, or general (rather than specifically) in QATR section A.1. other organizations supporting NMC, including Asset Owners, are required to comply with the QAP established by this QATR, or with their own programs having appropriate scope and controls.
Therefore, the activities and responsibilities of WPSC are either covered by this QATR, or contained within their own Appendix B program.
Because the QATR does not result in a reduction in commitment for the remaining organizational sections, in the aggregate, the QATR meets Appendix B. As such, this change to remove the WPSC specific reporting requirements from the QATR still meets Appendix B.
1.0-3(2) A.1(1)(2) Note 3. R See KNPP OQAPD Section 1.0-3(1) basis above.
1.0-3(3) A.1(1)(2) Note 3. R See KNPP OQAPD Section 1.0-3(1) basis above.
1.0-4(1) A.2.2.1 Responsibility for 10CFR21 reporting transferred to N the CNO in A.2.1.2 1.0-4(2) A.2.2.1.a Site Director recognized N 1.0-4(3) A.2.2.1.b Note 3. N 1.0-4(4) A.2.2.1, B.16(1) Note 3. N 1.0-4(5) A.2.2.1, A.3(6) Note 3. N 1.0-4(6) A.2.1.2.a Note 3. N 1.0-4(7) A.2.1.2.a Note 3. N 1.0-4(8) A.2.2.1.e Note 3. N 2
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 1.0-4(9) A.2.2.1.e Note 3. QA Typing committee not described. See N A.1(4).
1.0-4(10) A.2.2.1.e Note 3. N 1.0-4(11) A.2.2.1.e Note 3. N 1.0-4(12) A.2.2.1.e Note 3. N 1.0-4(13) A.2.2.1.b, Note 3. N A.2.2.1.d 1.0-4(14) A.2.2.1.b Note 3. N 1.0-4(15) A.2.2.1.b Note 3. N 1.0-4(16) A.2.2.1.d Note 3. N 1.0-4(17) A.2.2.1.d Note 3. N 1.0-4(18) A.2.2.1.c Note 3. N 1.0-4(19) A.2.2.1.d Note 3. N 1.0-4(20) A.2.2.1.d Note 3. N 1.0-4(21) A.2.2.1.d Note 3. N 1.0-4(22) A.2.2.1.d Note 3. N 1.0-4(23) A.2.2.1.d Note 3. N 1.0-4(24) A.2.2.1.g Note 3. N 1.0-4(25) A.2(3), A.2.2.1.h Note 3. N 1.0-4(26) A.5(1), A.7.3 Note 3. N 1.0-4(27) A.2.2.1.h Note 3. N 3
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 1.0-4(28) A.2.2.1.h Note 3. N 1.0-4(29) A.2.2.1.h Note 3. N 1.0-4(30) A.2.1.2.b.1 Note 3. N 1.0-4(31) NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.1 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.2 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.3. NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.4 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.5 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.6 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.A NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.B NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.C NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.D NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.E NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.F NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.G NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.7.H NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 4
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 1.0-4.7.I NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.8 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.9 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.10 NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.10.A NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.10.B NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4.10.C NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee 1.0-4(32) App. A, 1.0 Note 2. N (PORC) 1.0-4.1 App. A, 1.0 Note 2. N 1.0-4.2 App. A, 2.0(1) Note 2. Disciplines represented differ slightly. N 1.0-4.3 App. A, 2.0(2), N App. A, 3.0(2) 1.0-4.4 App. A, 3.0(1) Note 3. Minimum meeting frequency will be R The QATR provides for establishing established in implementing procedures. (similar) requirements at the procedure level. Previous industry guidance for PORC did not address this requirement. 10CFR50 Appendix B does not address PORC activities; therefore, the QATR continues to meet Appendix B.
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Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 1.0-4.5 App. A, 3.0(2) Note 3. Minimum quorum requirements will be R The QATR provides for establishing established in implementing procedures. (similar) requirements at the procedure level. Previous industry guidance for PORC did not address this requirement. 10CFR50 Appendix B does not address PORC activities; therefore, the QATR continues to meet Appendix B.
1.0-4.6.A App. A, 4.0(1), Note 2. PORC review of procedures is deleted based R Deletion of PORC review of procedures B.14(1) on NRC SER dated August 11, 1999, Safety is consistent with the provisions of the Evlaution by the Office of nuclear Reactor Regulation cited SER, and the necessary review Related to Amendment No. 190 to Facility Operating requirements are included in section License No. DPR-24 and Amendment No. 195 to B.14 of the QATR. The provisions for Facility Operating Licens No. DPR-27, Wisconsin procedure review and approval Electric Power Company Point Beach Nuclear Plant, continue to meet Appendix B Untis 1 and 2, Docket Nos. 50-266 and 50-301. requirements.
1.0-4.6-B App. A, 4.0(2) Note 2. N 1.0-4.6.C App. A, 4.0(5) Note 2. N 1.0-4.6.D App. A, 4.0(3) Note 2. N 1.0-4.6.E App. A, 4.0(1) Note 2. PORC review of programs reduced to those R Appendix B does not address PORC common to all current QAPDs at NMC plants. activities. The previous industry (Review of procedures addressed above.) guidance for this function was not explicit regarding PORC review of specific programs. Reduction to the set common to all NMC plants provides consistency. The QATR continues to meet Appendix B.
1.0-4.6.F App. A, 4.0(6) Note 2. N 1.0-4.6.G App. A, 4.0(9) Note 2. N 1.0-4.6.H App. A, 4.0(7) Note 2. OSRC replaced by Site Vice President, Site R See Enclosure 6.
Director and Plant Manager.
1.0-4.6.I App. A, 4.0(8) Note 2. N 6
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 1.0-4.6.J App. A, 4.0(1) PORC review of programs reduced to those R Appendix B does not address PORC common to all current QAPDs at NMC plants. activities. The previous guidance for this function was not explicit regarding PORC review of specific programs.
Reduction to the set common to all NMC plants provides consistency. The QATR continues to meet Appendix B.
1.0-4.6.K App. A, 4.0(4) Note 2. N 1.0-4.7.A App. A, 5.0(1) Note 3. N 1.0-4.7.B App. A, 5.0(3) Note 3. Requirement for providing meeting minutes R See Enclosure 6.
to OSRC removed.
1.0-4.8 App. A, 6.0, B.15 Note 3. Requirement for providing meeting minutes R See Enclosure 6.
to OSRC removed.
1.0-4(32) A.1(4) The Quality Typing Committee function is not R The QATR establishes typing criteria, addressed in the QATR. Note 3. and the requirement to maintain a means of identification of SSCs subject to QATR control.
2.0-1(1) A.1(4) Note 3. QATR substitutes NQA-1 for ANSI standards R The QATR establishes typing criteria, and of itself addresses the N18.7 administrative and the requirement to maintain a controls. Details of QA typing are not discussed in means of identification of SSCs subject the QATR. to QATR control.
2.0-1(2) A.1(4), B.2 Note 3. Details of QA Typing not in QATR. Plant R The QATR establishes typing criteria, Physical change program not addressed in QATR. and the requirement to maintain a means of identification of SSCs subject to QATR control.
2.0-2(1) A.1(1), A.3(3), Note 3. N A.5(1) 2.0-2(2) A.1(4) Note 3. N 2.0-3(1) Introduction, Note 3. N A.1(1)(3),
B.14(1)(2) 2.0-3(2) A.1(6) Note 3. N 7
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 2.0-3(3) A.1(6), B.14(1) Note 3. N 2.0-4 A.2(3), C.1(2), Note 3. N C.3(1)(3),
A.2.2.1.h 2.0-5(1) A.5(1) Note 3. N 2.0-5.A A.5(1) Note 3. N 2.0-5.B A.5(1) Note 3. N 2.0-5.C A.5(1) Note 3. N 2.0-5.D A.5(1) Note 3. N 2.0-5.E A.5(1) Note 3. N 3.0(1) B.2 Note 3. Plant Physical Change Program not N addressed by name in the QATR. QATR Section B.2 and B.3 encompass the aspects of the Plant Physical Change Program described in the OQAPD.
3.0.1 B.2(1) Note 2. N 3.0.2 B.2(1) Note 2. N 3.0.3 B.2(1) Note 2. N 3.0.4 B.2(2) Note 2. N 3.0.5 B.17 Note 2. I 3.0.6 B.2(2), B.3(1) Note 2. N 3.0.7 B.2(1) Note 2. N 4.0(1) B.4(1)(5) Note 2. N 8
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 4.0(2) B.4(6)(8) Note 2. N 5.0(1) A.1(6), B.14(1) Note 2. N 5.0(2) A.1(6), B.1, Note 3. Plant Physical Change Program (e.g., plant R Although the name Plant Physical B.14(1) design and modifications) is not addressed by name Change Program is not in the QATR, in QATR. as stated in QATR Section B.1, activities governed by the QAP are performed as directed by documented instructions, procedures and drawings.
Because the aspects of plant design and modification are covered by QATR section B.2 and B.3, the KNPP OQAPD requirement for design modifications to be made with implementing procedures is contained within the QATR.
Therefore, the necessary elements of design control as required by 10CFR50 Appendix B are contained within the QATR.
6.0(1) B.1(1), B.14 Note 3 . N 7.0(1) B.4(4) Note 2. N 7.0(2) B.4(4)(6) A Qualified Suppliers List is not identified in the R Any prospective supplier will be QATR. evaluated to ensure that only qualified suppliers are used. The identification of a Qualified Supplier List does not impact the commitment to evaluate and ensure that only qualified suppliers are used. As such, the QATR meets the requirements of 10CFR50 Appendix B.
8.0 B.4(5)(6)(8) Note 2. N 9.0 B.11 Note 2. N 10.0(1) B.4(6), B.12(1), Note 2. N A.2.2.1.h 9
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 10.0(2) B.7(5), B.8(1), Note 2. Physical Change Program is not addressed R Although the name Plant Physical B.9(1), B.10(1), in QATR. Change Program is not in the QATR, B.12(1)(2) the referenced areas (i.e., special processes, test, measuring and test equipment, and cleanliness) are all activities governed by the QATR.
Because the aspects of plant design and modification are also covered by QATR, the KNPP OQAPD requirement for design modification process to contain these specific areas is contained within the QATR. Therefore, the requisite elements of design control as required by 10CFR50 Appendix B are contained within the QATR.
10.0(2) (cont.) B.7(5), B.8(1), Review by NOS personnel is not addressed in the R The QATR states that inspections are B.9(1), B.10(1), QATR. carried out by properly qualified B.12(1)(2) persons independent of those who performed or directly supervised the work. This is commensurate with the KNPP OQAPD commitment for Nuclear Oversight to perform this activity.
Appendix B does not stipulate the need for NOS personnel to review work packages. Therefore, this change is not a reduction in commitment and the QATR meets Appendix B.
10.0(3) A.5(3) Note 2. N 10.0(4) A.5(3) Note 2. NQA-1 replaces N45.2.6, as endorsed by RG N 1.28. See also Enclosure 3, NMC QATR Exceptions/
Alternatives.
10.0(5) A.1(1), A.5(1) Note 2. N 11.0(1) B.8 Note 2. N 10
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 11.0(2) B.8(1), B.13(1) Note 2. Plant Physical change program not R Although the name Plant Physical addressed QATR. Change Program is not in the QATR, the referenced areas (i.e., testing and evaluation of testing results) are all activities governed by the QATR.
Because the aspects of plant design and modification are also covered by QATR, the KNPP OQAPD requirement for design modification process to contain these specific areas is contained within the QATR. Therefore, the requisite elements of design control as required by 10CFR50 Appendix B are contained within the QATR.
12.0 B.9 Note 2. N 13.0(1) B.7(1)(2) Note 2. N 13.0(2) B.7(1)(2) Note 2. N 13.0(3) B.7(1)(2)(3)(5) Note 2. N 14.0(1) B.10 Note 2. N 14.0.1 A.6, B.4(6), B.10 Note 2. N 11
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 14.0.2 B.16, B.10, Note 2. Review by NOS personnel is not addressed R The QATR states that inspection B.12(2) in the QATR. planning identifies required hold points, beyond which work is not to proceed without the consent of the inspection organization. This is commensurate with the KNPP OQAPD commitment for Nuclear Oversight to perform this activity. Appendix B does not stipulate the need for NOS personnel to review work packages. Therefore, this change is not a reduction in commitment and the QATR meets Appendix B.
15.0 A.6(3), B.13 Note 2. N 16.0(1) A.6(1)(2) Note 2. N 16.0(2) A.6(2) Note 2, Reportability is not addressed in the QATR. R Appendix B does not address reportability requirements associated with other NRC regulations. As such, removal does not constitute a reduction in commitment with respect to the QATR meeting Appendix B.
16.0(3) A.2.2.1.h, C.3(2) Note 3. N 16.0(4) B.13 Note 2. Note 3. N 17.0(1) B.15(1)(2) Note 2. N 17.0(2) B.15(1)(2) Note 2. Note 3. N 17.0(3) B.15(2) Note 2. N 12
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 18.0(1) C.3(1), B.4(4), Note 2. Two year frequency replaced in QATR by a R Appendix B requires a system of A.5 performance based approach. Technical planned and periodic audits. The Specification assessments not addressed specifically provisions of the QATR provide for in the QATR. such a system in a manner that assures appropriate topic coverage using both a defined frequency and a performance-based approach.
18.0(2) C.3(2) Note 2. N App A ANSI N18.7 A.7.3(4)(7) NQA-1 replaces N18.7 in the NMC QATR as N General(1) described in RG1.28 and 1.33. Note 2.
ANSI N18.7 A.1(7) Note 2. The QATR does not allow for a method of N General(2) interpretation. Explanatory section regarding how interpretations are made not in QATR. Exception not retained in the QATR.
ANSI N18.7 A.6, A.1(7) Note 2. N General(3)
ANSI N18.7 Policy Although the QATR does not address the instance N General(4) Statement(1) where conflicting requirements co-exist, the QATR policy statement does require operation in compliance with the requirements of the facility operating license.
Because the TS are part of the operating license, the OQAPD statement is provided for within the QATR.
N18.7.3.1 NA Explanatory section. The QATR establishes both QA N and Administrative controls.
N18.7, 5.2.2 B.14(3) The QATR provides same requirement. N N18.7, 5.2.7.2 B.3(3)(4) Note 2, NQA-1 replaces N45.2.11 and applies to any I design activity.
13
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B N18.7, 5.2.9 NA Security is not directly addressed in the QATR since R Although security is not directly such measures are directly governed by 10CFR73. addressed in the QATR, QATR Section A.1(5) states that selected elements of the QAP are applied to certain activities that are not safety related, but support safe and reliable operations, including security. Implementing documents will establish program element applicability.
As such, the QATR meets Appendix B.
N18.7, 5.2.12 B.15(3) Note 2. NQA-1 replaces N45.2.9 to establish records I requirements, nature and scope limitation in case not retained in QATR.
N18.7, 5.2.15 B.14(2) Note 2. QATR retains alternative to 2 year procedure R Experience has shown that programs reviews but does not specifically identify/retain a 2 do keep procedures current, regardless year review requirement for specific procedure types. of their type or usage frequency.
Appendix B requires that documents controlling activities be kept current and distributed to and used on the job. The QATR establishes controls that meet Appendix B.
N45.2.9, 4.3/4.4 B.15(1) Note 2. NQA-1 replaces N45.2.9 N N45.2.9, 5.6(1) B.15(1)(2)(3) Note 2. NQA-1 replaces N45.2.9. The QATR does N Appendix B does not address transport not address transport. of records.
N45.2.9, 5.6(2) B.15(1)(3) Note 2. N N45.2.9, 5.6(3) NA Explanatory text providing basis for earlier paragraphs N not needed in QATR.
Fig 1 A.2 The QATR does not provide charts. The descriptions N provide explicit reporting relationships. Note 2.
Fig 2 A.2 The QATR does not provide charts. The descriptions N provide explicit reporting relationships. Note 2.
Fig 3 A.2 The QATR does not provide charts. The descriptions N provide explicit reporting relationships. Note 2.
None B.16 Control of Plant Maintenance is not addressed in the I current program.
14
Enclosure 2, Number 2 QA Program Comparison Matrix Kewaunee Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B None B.17 Control of Computer Software is not addressed in the I current program.
None A.7.3 (RIS 2000- Electronic records are not addressed in the current I
- 18) program.
None C.2 Self-assessment is not addressed in the current I program.
NOTES:
- 1. R = Reduction in Commitment.
N = Not a Reduction in Commitment.
I = Increase in commitment.
- 2. Wording in the QATR and commitments to detailed requirements of NQA-1-1994 establish equivalent requirements or commitments. Any wording difference is the result of format needs associated with changing to Standard Review Plan 17.3 format. 10CFR50.54(a)(3)(i) or (v) apply.
- 3. Methodology details in the current program description may not be included in the NMC QATR. The intent of the QATR is to describe appropriate/sufficient requirements to establish how the quality assurance program meets 10CFR50, Appendix B, but to allow flexibility in the manner by which a requirement is met. Therefore, this change in methodology detail is not considered to be a reduction in commitment.
15
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Ref: Xcel Energy - Operational Quality Assurance Plan, Revision 25, effective date: 5/08/2003 NMC QATR [NMC-1, Rev. 0a, October 10, 2003]
General Note - The Xcel OQAP included Fire Protection Program requirements throughout the body of the document. Fire Protection Program requirements are not part of the NMC QATR. Therefore, all references to Fire Protection will be transferred to separate site documents. Specific Fire Protection references are not detailed in the Table below. QATR commitment to Quality Assurance requirements for Fire Protection is made in A.7.3, Branch Technical Position CMEB 9.5-1.
Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 1.1 Policy Statement Note 2 N 1.2 Policy Note 2 N Statement, A.7.1
& A.7.2 1.3 A.7.3 Note 2 N The OQAP commitments to ANSI N18.7 and the ANSI N45.2 series of standards are replaced as described in the QATR by commitment to NQA-1-1994.
1.4 A.1 (1, 3) Note 2 N 1.5 A.1, A.5 Note 2 N 1.6 A.3 (2) Note 2 N C.1 (1, 3) Referenced sections equivalent to CNO periodic review of C.3 (3) OQAP.
2.0 A.1 (2) Note 2 N 3.1 A.1, A.2, A.4 Note 2 N 3.2 A.2.1, A.2.2, A.3, Note 2 N A.4 The QATR does not provide charts. The descriptions provide explicit reporting relationships.
4.1 Policy Note 2 N Statement, A.1, A.5, A.3, B.7, B.11, B.12, C.1 4.2 A.1, A.2 Note 2 N 4.3 A.1, A.2, A.2.1, Note 2 N B.1, B.14, C.1 (1, Referenced sections equivalent to 4.3.2 periodic review of 3), C.3 (3) OQAP.
4.4 A.1, B.1 Note 2, Note 3 N 4.5 A.1 (3, 4) Note 2, Note 3 N 4.6 A.1 (3, 4) Note 2 N 1
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 4.7 A.2, A.2.1.2.b Note 2, Note 3 R Dispute resolution is not discussed in 4.7.2 - Dispute resolution not discussed in QATR. Appendix B. The QATR specifies organization and responsibilities that meet Appendix B.
4.8 A.1 (4), B.14 (1) List of structure system components has been removed from R Programs (lists) are included in plant QATR. Criteria provided for determining list are included in specific documents. This meets A.1 (4). Appendix B requirements to identify applicable SSCs.
4.9 A.3 (3), A.5 (1) Note 2 N 5.1 B.2 Note 2 N 5.2 A.1, B.2, B.3 Note 2 N 6.1 B.4 (1) Note 2 N 6.2 A.1, A.7.1, A.7.3, Note 2 N B.4 (1, 4), B.5 (1) Note 3 6.3 B.4 Note 2, Note 3 R Reviews imply approvals. This is an Approvals by management are not specifically stated in the administrative requirement. The QATR QATR. provides for reviews of procurement documents to assure the requirements of Appendix B are met.
6.4 A.7.3 (BTP Note 2 N CMEB 9.5-1) 7.1 A.1 (3, 6) Note 2 N 7.2 A.1 (3), B.14 (1), Note 2 N Appendix B (2) 7.3 A.1 (8), B.14 (1), Note 2 N Appendix B, B.11 (1) 7.4 A.1 (6) Note 2 N 8.1 B.14 (1, 2), B.16 Note 2 N 8.2 A.3 (5), B.1, Note 2 N B.14 (1, 2) 8.3 A.3 (5), B.1, Note 2 N B.14 (1, 2) 8.4 B.14 (1, 2, 3) Note 2, Note 3 N 8.5 A.1 (6), B.14 (1) Note 2, Note 3 N 8.6 B.2 (1) Note 2 N 2
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 8.7 A.1 (4), B.14, Note 2 N A.7.3 (Reg Guide 7.10),
Appendix B 8.8 B.14 Note 2 N 8.9 B.14 (1) Note 2 N 9.1 B.4, B.5 (1) Note 2 N 9.2 A.1, B.4 Note 2 N 9.3 B.4 (3rd bullet) Note 2 N 9.4 B.12 (1), B.4 (5th Note 2 N bullet) 10.1 B.6 (1) Note 2 N 10.2 B.6 (1), B.7 (1) Note 2 N 10.3 B.6 (1), B.7 (1) Note 2 N 10.4 B.12 (1), B.4 (5th Note 2 N bullet), B.13 10.5 None No specific reference for protection against theft or diversion R Meets 10CFR50 App. B requirements.
in new QATR. Security Plan addresses theft/diversion of nuclear fuel.
11.1 B.11 (1) Note 2 N 11.2 A.1 (6), B.11 Note 2, Note 3 R The definition of Special Processes in the QATR encompasses the examples Brazing not specifically referenced in QATR not listed, and the list included matches 10 CFR 50, App. B.
11.3 A.5 (1), B.11 (2) Note 2 N NQA-1, Basic Requirement 9, Supplement 9S-1 requires qual of personnel.
11.4 A.1 (6), Note 2, Note 3 R The definition of Special Processes in B.11 (1, 2) the QATR encompasses the examples Heat Treating not specifically referenced in QATR not listed, and the list included matches 10 CFR 50, App. B.
12.1 A.1 (4, 5), B.10 Note 2 N (1), B.12 (1, 2),
App. B (Test &
Inspection Proc.)
12.2 B.10 (1), B.12 (1, Note 2 N 2), App. B (Fuel Handling Proc.)
3
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 12.3 A.5 (1), Note 2 N B.12 (1, 2) NMC commits to NQA-1 for qualifications 12.4 B.12 (1), B.16 Note 2, Note 3 N 12.5 A.5 (1, 2), Note 2 N B.12 (1, 3), B.16 Qualifications per NQA-1 12.6 A.5 (1), B.12 (1) Note 2, Note 3 R Technical Services are not specified in Technical Services not specifically mentioned in QATR Appendix B. The QATR provides for inspections that meet Appendix B.
12.7 A.5 (1), Note 2 N B.4 (5th bullet) Qualifications per NQA-1 12.8 A.5, B.4 (1), Note 2 N B.5 (1), B.12 Qualifications per NQA-1 12.9 A.7.3 Note 2 N General inspection measures listed in B.4, B.10 and B.12.
12.10 A.1 (4) Note 2 N 12.11 A.1 (5) Note 3 R The QATR establishes requirements A.12 Emergency Equipment inspections not specifically addressed for inspections that meet Appendix B.
in QATR 12.12 A.5, B.7 (2 - 3rd Note 2 N bullet 12.13 A.5 (2), B.11 Note 2, Note 3 N Specific NDE methods are not listed in the QATR, but are as listed in SNT-TC-1A and/or CP-189.
12.14 B.12, App. B Note 2 N (Test & Insp.
Procedures) 13.1 B.8, B.10, Note 2 N Appendix B (Test
& Insp.
Procedures) 13.2 A.5, B.8 (1), Note 2 N Appendix B (Test
& Insp.
Procedures) 13.3 B.8 (1) Note 2 N 13.4 B.4 (5th bullet), Note 2 R Appendix B, Criterion VII, requires tests B.8 (1) OQAP - requires completion of proof tests prior to installation. prior to installation or use. The QATR QATR - requires proof test completion prior to operability. meets this requirement.
4
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 13.5 B.8, Appendix B Note 2 N (Test & Insp. Note 3 Procedures) 13.6 A.5 (1) Note 2 N 14.1 B.9 (1) Note 2 N 14.2 B.9 (1) Note 2 N 14.3 B.9 (1 - 4th Note 2 R Appendix B requires that M&TE be bullet) National Institute of Standards & Technology (NIST) is properly controlled, calibrated, etc, to specified in OQAP, but not QATR. However, the national maintain accuracy within specified standards wording in the QATR provides necessary control. limits. The QATR provides controls that meet this requirement.
15.1 B.7 (1) Note 2 N 15.2 B.7 Note 2 N 15.3 B.7 Note 2 R 10CFR50 App. B does not specify fuel No specific reference to nuclear fuel storage in QATR storage requirements.
15.4 B.7 Note 2 R 10 CFR 20 encompasses radioactive No specific reference to radioactive material storage in QATR material storage requirements.
15.5 B.7 Note 2 N 15.6 B.7 Note 2 N 15.7 A.1 (4), Note 2 N B.7 (3rd bullet) 16.1 B.10 Note 2 N 16.2 B.16 Note 2, Note 3 N See NQA-1, subpart 2.18, para. 2.5(c for ref to ALARA 16.3 B.8, B.10 Note 2 N 16.4 B.10 Note 2, Note 3 N 16.5 B.10 Note 2, Note 3 R Security related Key control is covered No specific reference to key control in QATR in the Site Security Plan. The QATR provides for control measures that meet Appendix B, Criterion 14.
16.6 B.2(4) Note 2, Note 3 N B.10 16.7 A.7.1 Note 2, Note 3 R This is not an Appendix B topic. Site Radioactive Material control is not detailed in the QATR. program procedures include rad material control.
16.8 App. B (Start-up Note 2 N Procedures) 17.1 A.6 (3), B.6, B.13 Note 2 N 5
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 17.2 B.4 (4th and 5th Note 2, Note 3 N bullets), B.13 (3) 17.3 B.13 (3) Note 2, Note 3 N 17.4 B.13 Note 2, Note 3 N 17.5 A.6, B.13 Note 2 N 17.6 A.7.1, A.2.1.2 Note 2 N 18.1 A.6 (2), B.13 Note 2 N 18.2 A.6 (2), B.13 Note 2, Note 3 N 18.3 C.3 (2) Note 2 N 19.1 B.15 (1, 2) Note 2, Note 3 N 19.2 B.15 (3) Note 2, Note 3 N 19.3 B.15 (1) Note 2 N 19.4 B.15 (1) Note 2 N 19.5 A.5 (1), B.15 (1) Note 2 N 19.6 B.4 (4th bullet), Note 2 N B.15 (1) 19.7 B.8, B.15 (1) Note 2 N 19.8 C.3 (3), B.15 (1) Note 2 N 19.9 B.15 Note 2, Note 3 N 19.10 B.2 (3), B.14 (1), Note 2 N B.15 (1) 19.11 B.15 Note 2 N 19.12 B.15 (2) Note 2, Note 3 R Retention times are required to be Retention times for operating records are not specified in specified in RMS procedures, per NQA-QATR, but are specified in OQAP. 1, Supplement 17S-1, 2.8. The requirements of NQA-1, for records maintenance, have been endorsed by the NRC, via RG 1.28, as meeting Appendix B requirements. Therefore, the QATR, which commits to NQA-1, continues to meet Appendix B.
20.1 C.1 (2), Note 2 N C.3 (2, 3) 20.2 C.3 (1, 3) Note 2 N 6
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 20.3 C.3 (1) Note 2 R 10CFR50, App. B requires a system of The QATR replaces audits at defined frequencies (maximum planned and periodic audits. The of 2 years) with performance-based assessments (dynamic provisions of the QATR provide for schedule frequencies). Certain topics retain designated such a system in a manner that frequencies where required by regulation. assures appropriate topic coverage using both a defined frequency and a performance-based approach.
20.4 C.1 (2, 4) Note 2 N 20.5 C.3 (2, 3) Note 2 N 20.6 C.3 (3) Note 2, Note 3 R Dispute resolution is not discussed in QATR does not specify who resolves disputes. Appendix B. See 4.7, above.
21.0 N/A The QATR does not provide requirements for Offsite Safety R See Enclosure 6.
Review Committee.
22.1 Appendix A (2.0, Note 2, Note 3 N 3.0) QATR requires member appointment by the Plant Manager.
22.2 Appendix A (3.0) Note 2, Note 3 R Previous industry guidance for PORC QATR says minimal frequency will be specified in procedures. did not address meeting frequency.
Appendix B does not address onsite reviews, therefore the QATR continues to meet Appendix B.
22.3 Appendix A (3.0) Note 2, Note 3 R Previous industry guidance for PORC QATR references quorum will be established per procedure. did not address quorum requirements.
Appendix B does not address onsite review, therefore the QATR continues to meet Appendix B.
22.4 App A (4.0), Note 2, Note 3 R 10CFR50, App. B does not specify any B.14 (1) QATR does not cover topics in 2.2.7/8/9/10, nor results of required reviews, however, the reviews tests and experiments per 22.4.1. specified are consistent with previous industry guidance for what offsite PORC review of procedures is deleted based on NRC SER reviews should cover.
dated August 11, 1999, Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 190 Deletion of PORC review of procedures to Facility Operating License No. DPR-24 and Amendment is consistent with the provisions of the No. 195 to Facility Operating License No. DPR-27, Wisconsin cited SER, and the necessary review Electric Power Company Point Beach Nuclear Plant, Units 1 requirements are included in section and 2, Docket Nos. 50-266 and 50-301. B.14 of the QATR. The provisions for procedure review and approval continue to meet Appendix B requirements.
7
Enclosure 2, Number 3 QA Program Comparison Matrix MONTICELLO Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 22.5 Appendix A (5.0) Note 2, Note 3 R This is not addressed by Appendix B.
QATR does not describe the process to resolve disagreements. QATR does not require notification of disagreement to OSRC.
22.6 Appendix A (6.0) Note 2, Note 3 R Appendix B does not specify QATR doesnt specify the additional distribution requirements requirements for onsite reviews.
cited in the OQAP.
22.7 Appendix A (1.0) Note 2, Note 3 N Appendix A - A.1 (4) Note 2, Note 3 R List will be relocated at MNGP, outside Systems, and QATR references A list, or other means of identification, of of the QATR.
Components Subject safety related Systems, Structures, and Components (SSC) to Appendix B of under the control of the QAP is established and maintained 10CFR50 for each operating plant.
Appendix C - Fire Protection Note 2, Note 3 R Fire Protection program will be Nuclear Plant Fire Program is not relocated at MNGP, outside of the Protection Program included in the QATR.
QATR.
The change in fire protection frequency Table 2 for Fire The previous 1, 2 and 3-year fire protection assessments, per is supported by NRC approval on Protection Audit 14.0, are replaced by a 2-year assessment using a qualified 8/30/96 for the same change made by frequency. offsite fire protection specialist. PECO Nuclear for its Limerick and Peach Bottom plants.
None B.16 Control of Plant Maintenance is not addressed in the OQAP. I None B.17 Computer Software Control is not addressed in the OQAP. I None A.7.3 (RIS 200- Electronic records are not addressed in the OQAP. I 18)
None C.2 Self-assessment is not addressed in the OQAP. I NOTES:
- 1. R = Reduction in Commitment.
N = Not a Reduction in Commitment.
I = Increase in commitment.
- 2. Wording in the QATR establishes equivalent requirements or commitments. Any wording difference is the result of format needs associated with changing to Standard Review Plan 17.3 format. 10 CFR 50.54(a)(3)(i) and/or (v) apply.
- 3. Methodology details in the current program description may not be included in the NMC QATR. The intent of the QATR is to describe appropriate/sufficient requirements to establish how the quality assurance program meets 10CFR50, Appendix B, but to allow flexibility in the manner by which a requirement is met. Therefore, this change in methodology detail is not considered to be a reduction in commitment.
8
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B Statement of Policy Note 2. N Resp. Introduction A.1(4) The QPD commitments to ANSI N18.7 and the ANSI A.2.1.2 N45.2 series of standards are replaced as described A.2.1.2.b in the QATR by commitment to NQA-1-1994..
1.1(1) A.1(1) Note 2. N A.4(1) 1.1(2) A.2(1)(3) Note 2. N A.2.1.2.b.1 1.1(3) A.2(3) Note 2. N B.1 C.3(1) 1.2.1(1) A.2(2) Note 2. N A.2.1.2 A.2.1.2.b 1.2.2(1) A.2.1.1 Note 2. N A.2.1.2 A.2.2.1 1.2.2.a A.2.2.1 Note 2. N A.2.2.1.a Note 3. N A.2.2.1.b A.2.2.1.c A.2.2.1.d A.2.2.1.e A.2.2.1.f A.2.2.1.g 1.2.3 A.2(1) Note 2. N A.2.2.1.b Note 3. N A.2.1.2.b.1 A.2.2.1.h Org chart NA The QATR does not provide charts. The descriptions N provide explicit reporting relationships. Note 2.
2.1(1) A.1(1) Note 2. N 1
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 2.1(2) A.1(4) Note 2. N A.5(1)
B.1 2.1(3) C.1(1) Note 2. N C.1(2)
C.3 2.2.1 Policy Statement Note 2. N 2.2.2 A.2(3) Note 2. N 2.2.3(a-b) N/A QATR becomes effective after NRC approval. N 2.2.3(c) A.1(4) Decommissioning excluded from QATR. R NMC only operates plants. QATR still meets App B criteria.
2.2.4(1) A.1(7) Note 2. N Introduction 2.2.4(2) A.7.3 Note 2. Instead of a list of exceptions at the end, the N QATR includes exceptions/alternatives within the body at the appropriate points.
2.2.4(3) A.1(7) Note 2. N 2.2.5(a) A.1(3) Note 2. N 2.2.5(b) A.1(1) Note 2. N A.2(5)
B.4(4) 2.2.5(c) A.1(4)(5) Note 2. The QATR wording is less explicit but more N encompassing, and is deemed to include the QPD items.
2.2.6(1) A.1(4) Note 2. N 2.2.6(2) A.1(4) Note 2. N 2.2.6(3) A.1(4) Note 2. Note 3. N 2.2.6(4) A.1(4) Note 2. N B.6 2
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 2.2.7(a) A.5(1) Note 2. N 2.2.7(b) B.1(1) Note 2. N 2.2.7(c) B.16(2) Note 2. N 2.2.7(d) B.6(1) Note 2. N 2.2.7(e) B.16(1) Note 2. N 2.2.7(f) B.1 Note 2. N 2.2.7(g) B.7(2) Commitment to NQA-1-1994 especially Subparts 2.1, N B.16(1) 2.4 and 2.8 establish same requirement. Wording not in QATR.
2.2.7(h) B.8(1) Note 2. N B.11(1)-12(1) 2.2.8 B.17 Note 2. QATR commitment to NQA-1-1994 subpart I 2.7 is an increase.
2.2.9(1) A.2.2.1.a Note 2. N A.2.2.1.c 2.2.9(a) A.5(1) Note 2. N 2.2.9(b) A.5(2) Note 2. N 2.2.9(c) A.5(2) Note 2. N 2.2.9(d) A.5(1) Note 2. N 2.2.9(e) A.5(2) Note 2. Commitment to NQA-1-1994 includes the N requirement, which is not restated in the QATR.
2.2.9(f) A.5(1) Note 2. Note 3. N 2.2.9(g) A.5(1) Note 2. N 3
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 2.2.10(a) C.3(2) Note 2. N 2.2.10(b) NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
3.1(1) B.2(1) Note 2. Note 3. N 3.2.1 A.2 Note 2. Note 3. N 3.2.2 A.6(1) Note 2. N 3.2.3 B.2(1) Note 2. N B.4(7)
B.3(1) 3.2.4 B.4(5) Note 2. N 3.2.5 B.2(1) Note 2. N 3.2.6 B.3(4) Note 2. N 3.2.7 B.3(1) Note 2. Note 3. N 3.2.8(1-5) B.3(4) Note 2. Note 3. N 3.2.9(1) B.3(3) Note 2. 3.2.9(3.b) not retained. I Deletion of allowance for procedure control in lieu of individual approval is an increase. Design verification process still meets Appendix B.
3.2.9(2) B.3(3) Note 2. N 3.2.10 B.3(2) Note 2. N 3.2.11 B.17 Note 2. Commitment to NQA-1-1994, subpart 2.7 is I an increase.
3.2.12 B.2(2) Note 2. N B.2(4) 4.1(1) B.4(5) Note 2. N 4
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 4.2.1 B.4(8) Note 2. N 4.2.2 B.4(4) Note 2. N 4.2.3(a-h) B.4 Note 2. Note 3. Details of QPD are covered in NQA N 1994 and are not repeated in the QATR.
4.2.4(a-c) B.4(8) Note 2. Note 3. Details of QPD are covered in NQA N 1994 and are not repeated in the QATR.
4.2.5 B.4(8) Note 2. Note 3. Details of QPD are covered in NQA N 1994 and are not repeated in the QATR.
5.1(1) A.1(6) Note 2. N 5.2(1) A.2 Note 2. N 5.2(2) A.1(6) Note 2. N 5.2(3) A.1 Note 2. N App B 5.2(1-15) A.1(6) Note 2. QATR refers to RG1.33 Appendix A. N Item 15, Modification Procedures, is not App B Item 15 not retained. R specifically required by App B. The QATR requires procedures of a type appropriate to the circumstances, which is the same as required by App B.
6.1(1) B.14(1) Note 2. N 6.1(2) B.14(2) Note 2. N 6.1* None Note 3. See B.14 R Level of approval authority is established as part of document control provisions of B.14. The detail is not specifically required by 10CFR App B.
6.2.1 A.2 Note 2. N 6.2.2(a) B.14(1) Note 2. N 6.2.2(b) B.14(1) Note 2. N 5
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 6.2.2c B.14(1) Note 2. N B.4(1) 6.2.2(d) B.14(1) Note 2. N 6.2.2(e) B.14(1) Note 2. N 6.2.2(f) A.6(1) Note 2. N B.13(1) 6.2.2(g) B.14(1) Note 2. N 6.2.3(a-c) B.14(1)(2) Note 2. N 6.2.4(a,b) B.14(1`) Note 2. N 6.2.5 B.14(1) Note 2. Note 3. N 6.2.6 B.2(3) Note 2. N 7.1(1) B.4(4)(5)(8) Note 2. N B.5(1) 7.2.1 A.2 Note 2. N 7.2.2 B.4(4) Note 2. Note 3. Level of detail deferred to NQA N 1994 and Regulatory Guide 1.28.
7.2.3 A.1(6) Note 2. Note 3. Level of detail deferred to NQA N B.4(6)(7) 1994.
B.5(1) 7.2.4(1) B.4(2) Note 2. N 7.2.4(a) B.4(2) Note 2. N 7.2.4(b) B.4(7) Note 2. N 7.2.(c) B.4(2) Note 2. N 6
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 7.2.4d B.4(1)(2) Note 2. N 7.2.5 B.4(6) Note 2. N B.5 7.2.6(a-d) B.4(5) Note 2. N 7.2.6(2) B.4(6) Note 2. N B.5 7.2.7 B.4 Note 2. N 8.1(1) B.6 Note 2. N 8.2.1 B.6 Note 2. N 8.2.2 B.6 Note 2. N 8.2.3 B.6 Note 3. Verification of traceability not addressed. R QATR controls regarding identifying Level of detail deferred to NQA-1. and controlling items to prevent use of incorrect or defective items are consistent with 10CFR50, App B.
Verification is applied as required by NQA-1.
9.1(1) B.11 Note 2. N 9.2.1 B.11 Note 3. The list in the QATR does not include R The definition of Special Processes in application of protective coatings or concrete the QATR encompasses the examples placement. not listed, and the list included matches Appendix B.
9.2.2 A.2 Note 2. N 9.2.3 A.5 Note 2. N B.11 9.2.4 A.5 Note 2. N 9.2.5 B.11 Note 2. N 7
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 9.2.6 A.5 Note 2. N 9.2.7 C.3(1)Table 1 Note 2. N 10.1 B.12(1) Note 2. N 10.2.1 A.2 Note 2. N 10.2.2(1) B.12(1) Note 2. Inspection is not applied to decommissioning, R Appendix B does not include as NMC does not perform this activity and the QATR decommissioning in its scope.
specifically excludes it (see A.1).
10.2.2(a-f) B.12(2) Note 2. N 10.2.2(2)(3) B.12(5) Note 2. N 10.2.3(1) A.5(1) Note 2. N 10.2.3(2) A.5(1) Note 2. N 10.2.3(3) A.5(1)(4) Note 2. N 10.2.4 B.12(1)(4) Note 2. N 10.2.5 B.12(4) Note 2. N 10.2.6(1) B.12(3) Note 2. N 10.2.6(2) B.12(4) Note 2. N 10.2.7 A.5(3) Note 2. Alternate qualification option retained as an N B.12(1) exception to NQA-1.
10.2.8 B.12(3) Note 2. N 10.2.9 A.2.2.1.e Note 2. N A.4(2) 8
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 10.2.10 A.5(3) Note 2. N 11.1 B.8(1) Note 2. N 11.2.1 A.2 Note 2. N 11.2.2(1) B.8(1) Note 2. N 11.2.2(a-f) B.8(1) Note 2. N 11.2.3(1)(a-f) B.8(1)(2) Note 2. N 11.2.3(2) B.14(1) Note 2. N 11.2.3(3) B.8(1) Note 2. N 12.1(1) B.9(1) Note 2. N 12.2.1 A.2 Note 2. N 12.2.2 A.1(6) Note 2. N B.9(7) 12.2.3 B.9(3) Note 2. N 12.2.4 B.9(3) Note 2. N 12.2.5(1) B.9(2) Note 2. N 12.2.5(2) B.9(4) Note 3. Authorization is not specifically addressed in R Authorization is an expected part of the the QATR or NQA-1; however documented control established in the QATR. The justification is required. controls provided meet Appendix B.
12.2.5(3) B.9(4)(5) Note 3. Authorization is not specifically addressed in R Authorization is an expected part of the the QATR or NQA-1; however documented control established in the QATR. The justification is required. controls provided meet Appendix B.
12.2.6 B.9(5) Note 3. Authorization is not specifically addressed in R Authorization is an expected part of the the QATR or NQA-1; however documented control established in the QATR. The justification is required. controls provided meet Appendix B.
9
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 12.2.7 B.9(5) Note 2. N 12.2.8 B.9(6) Note 2. N 13.1(1) B.7(1) Note 2. N 13.2.1 A.2 Note 2. N 13.2.2(1) B.7(1) Note 2. N 13.2.2(a-d) B.7(1)(2) Note 2. N 14.1(1) B.10(1) Note 2. N 14.2.1 A.2 Note 2. N 14.2.2 B.4(3) Note 2. N B.10(1) 14.2.3 B.10(1) Note 2. N 14.2.4 A.1(6) Note 2. N B.14(1) 14.2.5 A.6(4) Note 2. N B.10(2) 15.1(1) A.6(1)(2) Note 2. N B.13(3) 15.2.1(1) B.13(3) Note 2. N 15.2.1(a) A.6(3) Note 2. N B.13(3) 15.2.1(b B.13(1) Note 2. N 15.2.1(c) B.13(1) Note 2. N 15.2.1(d) B.13(3) Note 2. N 10
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 15.2.2 B.13(3) Note 2. N 15.2.3 B.8(2) Note 2. N B.13(1) 15.2.4 A.6(a) Note 2. N 16.1(1) A.6(1) Note 2. N 16.1(2) A.6(1) Note 2. N 16.2.1 A.2 Note 2. N 16.2.2 A.6(1) Note 2. N B.13(1) 16.2.3 A.6(1) Note 3. QATR does not explicitly address extent of N the condition. However, extent is covered as a normal part of the evaluation.
17.1(1) B.15(1) Note 2. N 17.2.1 A.2 Note 2. N 17.2.2(1) B.15(1) Note 2. N 17.2.2(a-i) B.15(2) Note 2. Note 3. N 17.2.3(a-f) B.8(2) Note 2. N B.12(9) 17.2.4 B.15(2) Note 2. Appendix E from QPD replaced with RG 1.28 N and NQA-1 guidance for retention periods.
17.2.5 NA Note 2. N 17.2.6 B.15(3) Note 2. N 17.2.7 B.15(3) Note 2. N 11
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 17.2.8 B.15(3) Note 2. QATR, via NQA-1, allows for single records R Appendix B requires protection of storage facility. records. The requirements of NQA-1 for records maintenance have been endorsed by NRC in RG 1.28 as meeting the Appendix B requirements.
Therefore, the QATR, which commits to NQA-1, continues to meet Appendix B.
18.1(1) C.1(1) Note 2. N C.3(1) 18.2.1 A.2 Note 2. N 18.2.2 C.3(1) Note 2. The QATR replaces audits at defined R Appendix B requires a system of frequencies with performance-based assessments. planned and periodic audits. The provisions of the QATR provide for such a system in a manner that assures appropriate topic coverage using both a defined frequency and a performance-based approach.
18.2.3 B.4(4) Note 2. N 18.2.4 B.5(1)(2) Note 2. N 18.2.5 C.3(1) Note 2. N 18.2.6 C.3(1) Note 2. N 18.2.7 C.3(3) Note 2. N 18.2.8 C.1(2) Note 2. N C.3(1) 18.2.9 C.3(3) Note 2. N 18.2.10 C.3(2) Note 2. N 12
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B Appendix A, A.7 The list of items addressed is effectively the same R Appendix B does not require Part 1 with the update to NQA-1 and the addition of RG commitment to Appendix R. 10CFR50 1.28. Item 21, 10CFR50, App R, is not listed in the does require this, as specifically QATR. addressed in the UFSAR. Thus the QATR continues to meet Appendix B, and the plant continues its commitment to Appendix R as required.
Appendix A, NA Part 2
- 1. A.7.3(1) Note 2. N B.4(5)
- 2. NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
2a. A.2.2.1 Site Vice President replaces Plant Manager. N 2b. NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
2c. NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
2d. NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
2e. NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
2f. NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
2g. A.2.2, A.3, A.4 Note 2. Exception not retained. N 2h. B.14(3) Note 2. Review by PORC within 30 days not retained. R Appendix B does not address an onsite Appendix A, 4.0 review function. Previous industry standards included significantly less detail in describing the onsite review function and its involvement with review of selected documents or changes.
2i. A.6(2)(3), B.6(1), Note 2. N B.10(1), B.13 2j. A.5(3) Note 2. N 2k. B.8(1) Note 2. N 13
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 2l. B.4(5)(8) Exception retained. Note 2. N 2m. B.4(8) Note 2. N 2n. B.14(2), C.3(1) Note 2. Body of exception retained. No two-year R Experience has shown that programs reviews required for specific procedure types. do keep procedures current, regardless of their type or usage frequency.
Appendix B requires that documents controlling activities be kept current and distributed to and used on the job. The QATR establishes controls that meet Appendix B.
2o. B.9(3)(7) Note 2. N 2p. A.5(3), B.12(4), Note 2. N B.16(2) 2q. B.12(2) Exception not retained. Note 3. N 2r. B.16(1) Note 2. N 2s. B.14(1), B.16(2) Note 2. N 3a. C.3(1) See discussion for Appendix C of the QAPD. R See Enclosure 6.
14
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 3b. C.3(1) Exception not retained. Note 3. The QATR does not R The exception was related to previous establish a standard frequency for assessing audit type and frequency Technical Specification compliance. recommendations in RG 1.33 for the auditing of compliance to plant Technical Specifications. In QATR section C.3, NMC establishes a system of planned and periodic assessments (audits) that meet Appendix B requirements and provide for coverage of surveillance testing and other activities where Tech Specs would form part of the requirements set being assessed. Since the assessment program will include verification of Tech Spec compliance as appropriate, the QATR continues to meet Appendix B, Criterion 18.
4a. A.5 Exception not retained. Commitment to RG 1.8 is N A.7.3(2) addressed in A.7.3(2).
5a. A.7.3(2) Exception not retained. Commitment to RG 1.8 is N addressed in A.7.3(2).
5b. A.5 Note 2. N 6a. A.5(2) Exception retained. Note 2. N45.2.1 replaced with N NQA-1-1994, Subpart 2.1.
6b. B.7(4) Exception retained. Note 2. N 6c. B.7(4) Exception not retained. Note 2. N 7a. B.7(2) Exception retained. Note 2. N45.2.2 replaced with N NQA-1-1994, Subpart 2.2.
7b. A.5, B.5 Exception not retained. Note 2. N 7c. B.7(2) Exception not retained. Note 2. N 7d. B.7(2) Exception not retained. Note 2. N 15
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 7e. B.7(2) Exception retained. Note 2. N 7f. B.7(1)(2) Exception not retained. Note 2. N 7g. B.7(2) Exception not retained. Note 2. N 7h. B.7(2) Exception not retained. Note 2. N 8a. B.7(4) Exception retained. Note 2. N45.2.3 replaced with N NQA-1-1994, Subpart 2.3.
9a. A.5, B.2, B.7, Exception not retained. Note 2. N45.2.4 replaced with N B.14 NQA-1-1994, Subpart 2.4.
9b. B.4(8) Exception retained. Note 2. N 9c. B.9(1)(3)(7) Exception retained. Note 2. N 10a. A.5 Exception not retained. Note 2. N45.2.5 replaced N with NQA-1-1994, Subpart 2.5.
10b. B.9(6) Exception retained. Note 2. N 10c. B.9(2) Exception retained. Note 2. N 11a. A.5 Exception not retained. Note 2. N45.2.6 incorporated N into Basic and Supplemental Requirement of NQA-1.
12a. A.5 Exception not retained. RG 1.58 withdrawn. N 12b. A.5 Exception not retained. RG 1.58 withdrawn. N 12c. A.5 Exception not retained. RG 1.58 withdrawn. N 12d. A.5 Exception not retained. RG 1.58 withdrawn. N 13a. A.5, A.7.3(2) Exception not retained. N45.2.8 replaced with NQA N 1994, Subpart 2.8.
13b. B.16(2) Exception not retained. Note 2. N45.2.8 replaced with N NQA-1-1994, Subpart 2.8.
13c. B.4(8) Exception not retained. Note 2. N45.2.8 replaced N with NQA-1-1994, Subpart 2.8.
13d. B.3(2) Exception not retained. Note 2. N45.2.8 replaced N with NQA-1-1994, Subpart 2.8.
13e. B.7(4) Exception not retained. Note 2. N45.2.8 replaced with N NQA-1-1994, Subpart 2.8.
14a. B.15(3) Exception retained. Note 2. N45.2.9 incorporated into N Basic and Supplement Requirement of NQA-1.
16
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B 14b. B.15(1) Exception not retained. Note 2. N 14c. B.15(3) Exception not retained. Note 2. N 15a. B.3(3) Exception not retained. Note 2. RG 1.64 withdrawn. I Deletion of allowance for procedure control in lieu of individual approval is an increase. Design verification process still meets Appendix B.
16a. C.3(1) Exception not retained. RG 1.144 withdrawn N 16b. B.4, C.3 Exception not retained. RG 1.144 withdrawn. N 16c. B.4(4) Exception retained consistent with RG 1.28. RG 1.144 N withdrawn.
16d. B.4(4) Exception retained. RG 1.144 withdrawn. N 17a. B.4(2)(7) Exception retained. Note 2. N45.2.13 incorporated N into Basic and Supplemental Requirements of NQA-1.
17b. B.4(5)(8) See QAPD item 2.l. N 17c. B.4(8) Exception not retained. Note 2. N45.2.13 incorporated N into Basic and Supplemental Requirements of NQA-1.
17d. B.4(3) Exception not retained. Note 2. N45.2.13 incorporated N into Basic and Supplemental Requirements of NQA-1.
17e. A.5 Exception not retained. N45.2.13 incorporated into N Basic and Supplemental Requirements of NQA-1.
17f. B.4(8) Exception retained. N45.2.13 incorporated into Basic N and Supplemental Requirements of NQA-1.
17g. B.8 Exception not retained. N45.2.13 incorporated into N Basic and Supplemental Requirements of NQA-1.
18a. A.5(2) Exception retained. N45.2.23 incorporated into Basic N and Supplemental Requirements of NQA-1.
19a. A.1(4), A.7.3(3) Exception retained. Note 2. N 20a. A.7.3(18) Note 2. Reference to 10CFR50, Appendix R is not in R Appendix R commitments are the QATR. addressed in the UFSAR and are not required by Appendix B. Therefore the QATR meets applicable requirements.
21a. A.1(4), A.7.3(5) Exception retained. N 21b. A.1(4), A.7.3(5) Exception retained. N
- 22. NA See discussion for Appendix C of the QAPD. R See Enclosure 6.
17
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B Appendix B B1 App A, 1.0 Site Vice President replaced by Plant Manager. R Previous industry guidance provided for onsite reviews established the Plant Manager as the focal point. Appendix B does not address onsite reviews, therefore the QATR continues to meet Appendix B.
B2 App A, 2.0 Note 2 R 10CFR50 Appendix B does not address A.7.3 PORC. QATR provides for establishing (similar) requirements at the procedure level.
B3 App A, 2.0, 3.0 Note 3. N B4 App A, 3.0 Note 3. Minimum meeting frequency to be established R Previous industry guidance for PORC in implementing procedures. did not address meeting frequency.
Appendix B does not address onsite reviews, therefore the QATR continues to meet Appendix B.
B5 App A, 3.0 Note 3. Quorum requirements to be established in R Previous industry guidance for PORC implementing procedures. did not address quorum requirements.
Appendix B does not address onsite reviews, therefore the QATR continues to meet Appendix B.
18
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B B6(a) App A, 4.0(1) Note 2. PORC review of procedures is deleted based R Deletion of PORC review of procedures B.14(1) on NRC SER dated August 11, 1999, Safety is consistent with the provisions of the Evaluation by the Office of Nuclear Reactor cited SER, and the necessary review Regulation Related to Amendment No. 190 to Facility requirements are included in section Operating License No. DPR-24 and Amendment No. B.14 of the QATR. The provisions for 195 to Facility Operating License No. DPR-27, procedure review and approval Wisconsin Electric Power Company Point Beach continue to meet Appendix B Nuclear Plant, Units 1 and 2, Docket Nos. 50-266 and requirements.
50-301.
PORC review of programs reduced to those Appendix B does not address PORC common to all current QAPDs at NMC plants. activities. The previous industry guidance for this function was not explicit regarding PORC review of specific programs. Reduction to the set common to all NMC plants provides consistency. The QATR continues to meet Appendix B.
B6(b) App A, 4.0(2) Note 2. N B6 (c) App A, 4.0(6) Requirement for report to CNO shifted to onsite R Appendix B does not address PORC management positions above the Plant Manager. activities, so the QATR continues to See discussion for QAPD Appendix C regarding meet Appendix B.
OSRC.
B6(d)(e) App A, 4.0(7) Note 3. N B6(f)(g)(h) App A, 4.0(1) Note 3 PORC review of programs reduced to those N Appendix B does not address PORC common to all current QAPDs at NMC plants. activities. The previous industry guidance for this function was not explicit regarding PORC review of specific programs. Reduction to the set common to all NMC plants provides consistency. The QATR continues to meet Appendix B.
B6(i) App A, 5.0 New QATR requires subcommittees report to full N committee. This is equivalent to previous requirement.
B6(j) App A, 4.0(9) QATR adds modifier significant. N B6(2) NA Note 3. Allowance for routing review neither specified N App A, 5.0 nor prohibited by new QATR.
19
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B B7(a) App A, 5.0 Plant Manager replaces SVP. N B7(b) App A, 5.0 Note 2. N B7 (c) App A, 5.0 Note 3. 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> timing not retained. R Appendix B does not address PORC or the specifics of notifying senior management of disagreements. Thus the QATR continues to meet Appendix B.
B7(2-4) App A, 5.0 Routing review allowance not addressed (nor R Appendix B does not address PORC or prohibited) in QATR. Note 3. the specifics of how its reviews should be conducted. Thus the QATR continues to meet Appendix B.
B8 App A. 6.0 See discussion for QAPD Appendix C regarding N OSRC.
B9 App A, 5.0 Note 3. N B9.1 App A, 5.0 Note 3. N B9.2 App A, 5.0 Note 3. N B9.3 App A, 5.0 Note 3. N B9.4 App A, 5.0 Monthly periodicity not retained. Instead, regular R Appendix B does not address PORC reporting is required. activities. Thus the QATR continues to meet Appendix B.
Appendix C NA The QATR does not provide requirements for Offsite R See Enclosure 6.
Safety Review Committee.
Appendix D C.3(1) The QATR replaces most audits at defined R Appendix B requires a system of Table 1 frequencies with performance based assessments. planned and periodic audits. The Table 2 Certain topics retain designated frequencies where provisions of the QATR provide for required by regulation. In addition, the previous 1, 2 such a system in a manner that and 3-year fire protection assessments are replaced assures appropriate topic coverage by a 2-year assessment using a qualified fire using both a defined frequency and a protection specialist. performance-based approach. The See discussion for QAPD Appendix C regarding change in fire protection frequency is OSRC. supported by NRC approval on 8/30/96 for the same change made by PECO Nuclear for its Limerick and Peach Bottom plants.
20
Enclosure 2, Number 4 QA Program Comparison Matrix Palisades Nuclear Plant Current QAPD Section QATR Section R/N/I Basis for QATR as Changed (paragraph) (paragraph) s (Note 1) Continuing to Meet Appendix B Appendix E B.15 This list of records and retention periods is replaced R NRC has endorsed the requirements of by NQA-1-1994, Basic Requirement 17 and 17S-1, NQA-1, via RG 1.28, as an acceptable with the guidance of RG 1.28. However, the explicit means of compliance with Criterion 17 items and retention periods of the QAPD are not of Appendix B. Therefore, the QATR presented in the QATR. Note 2. will continue to meet applicable records requirements.
B.16 The current QAPD does not address Plant I Maintenance as specifically as this section and its commitment to NQA-1, Subpart 2.18.
B.17 The current QAPD does not address Computer I Software Quality Assurance as explicitly as this section and its commitment to NQA-1, Subpart 2.7.
A.7.3 The current QAPD does not address use of electronic I RIS-2000-18 media for records management or storage. This is a new commitment.
NOTES:
- 1. R = Reduction in Commitment.
N = Not a Reduction in Commitment.
I = Increase in commitment.
- 2. Wording in the QATR and commitments to detailed requirements of NQA-1-1994 establish equivalent requirements or commitments. Any wording difference is the result of format needs associated with changing to Standard Review Plan 17.3 format. 10CFR50.54(a)(3)(i) or (v) apply.
- 3. Methodology details in the current program description may not be included in the NMC QATR. The intent of the QATR is to describe appropriate/sufficient requirements to establish how the quality assurance program meets 10CFR50, Appendix B, but to allow flexibility in the manner by which a requirement is met. Therefore, this change in methodology detail is not considered to be a reduction in commitment.
21
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B 1.4(1) Introduction Note 2 N A.1(1)
A.7.1 A.7.2 1.4(2) A.1(3) Note 2 N A.1(4)
A.1(5) 1.4(3) A.1(7) Note 2 N 1.4(4) A.7.3 The list of items addressed is effectively N 1.4(5) the same with the update to NQA-1 and 1.4(6) the addition of RG 1.2. Administrative controls associated with N18.7 are included within the text of the QATR (see 18.7 Matrix). FSAR 1.4(6) states that the PBNP SSCP meets or exceeds N18.17. Since PBNPs SSCP has been approved by the NRC and is outside the scope of Appendix B, there is no reduction in commitment.
1.4.1 A.2 Note 2. QATR does not have a chart or N Figure 1.4-1 A.2.1 figure, but establishes responsibilities A.2.2 and reporting relationships in text.
B.1 1.4.2(1) None The QATR does not describe site R FSAR 1.4.2 establishes a CNO-NMC specific sub-tier implementing approval authority for the NQAP.
documents by name nor their approval This is a reduction commitment. The NQAP process implements FSAR 1.4. It is not the PBNP QA Program. Therefore not including its description in the QATR is not a reduction in commitment.
1.4.2(2) A.2(2) Note 2 N A.2.1.2 1.4.2(2) None The QATR does not provide R See Enclosure 6.
requirements for OSRC 1
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B 1.4.2(3) A.1(3) Note 2 N A.1(4) 1.4.2(4) A.1(4) Note 2 N 1.4.2(5) A.1(5) 1.4.2(6) A.5 Note 2 N A.7.3 B.15 1.4.2(7) B.7(3) Note 2 N 1.4.2(8) B.7(3) The QATR does not assign R Appendix B does not require site working B.7(4) housekeeping areas to site working groups be assigned housekeeping areas.
groups. The QATR establishes the necessary commitment to housekeeping practices.
1.4.2(9) B.7(4) Note 2 N B.12(1)
B.16 1.4.2(10) B.7 Note 2 N 1.4.2(11) None QATR does not describe commitment R Appendix B does not require sites to to physical safety and environmental establish physical safety and environmental conditions of work places. conditions of work places. The applicable requirements from other sources are met in site implementing procedures.
1.4.3(1) B.2(1) Note 2 N B.2(2)
B.2(4)
B.3(3)
B.16(1)
B.17 1.4.3(2) B.2(1) Note 2 N B.3(1) 1.4.3(3) B.3(1) Note 2 N B.3(3) 1.4.3(4) B.3(1) Note 2 N B.17 2
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B 1.4.3(4) B.2(2) Note 2 N B.2(4) 1.4.4 B.4 Note 2 N B.5 B.15 1.4.5(1) B.2(1) Note 2 N B.14 1.4.5(2) Appendix C The QATR does not specify Supervisor R Personnel are trained on how to use responsibilities of acceptance criteria procedures, including those containing data taking and verification of the data acceptance criteria. Development of and the use of OE to establish acceptance criteria is performed using acceptance criteria. internal and external operating experience and vendor information. See Note 3.
1.4.5(3) B.14(2) Note 2 1.4.5(4)(5)(6) B.14 Note 2 N 1.4.5(7) C.3(1) The QATR requires assessments be R Procedures will continue to be assessed as based on status, performance, and part of regular assessments scheduled per effect on safety of the activity. QATR C.3. As such, a random sample of procedures to be audited every two years will be accomplished on a continuing basis.
1.4.5(8) B.14(1) The QATR does not specifically define R IPTEs. Note 3.
1.4.5(9) None Various applicable CFRs and Technical N Specifications define review frequency requirements for these specific procedures.
1.4.5(10) B.14(1) Note 2 N Appendix C 1.4.6(1)(2) B.14 Note 2 N 1.4.6(3) B.15(1) Note 2 N B.15(2) 1.4.7 A.5 Note 2 N B.4 3
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B B.5 C.5 1.4.8 B.6 Note 2 N B.7(1)
B.12(1) 1.4.9 B.5 FSAR 1.4.9 requires copies of R The QATR states that special processes are B.11 qualifications to be on site during accomplished using qualified personnel.
B.12(3) process performance. For the remainder, see Note 2, 3.
1.4.10(1) B.12(1) Note 2 N 1.4.10(1)bullets 1-4 B.12(2) Note 2 N 1.4.10(1) bullet 5 B.12(3) Note 2 N 1.4.10(2) B.12(4) Note 2 N 1.4.10(3) A.5 Note 2 N B.12(1) 1.4.10(4) B.4 Note 2 N B.5 1.4.10(5) B.12(1) Note 3 N 1.4.10(6 and 7) B.12(X) Note 2 N 1.4.10(8) B.4 Note 2 N B.12(X) 1.4.10(9) B.12(1) Note 3 N 1.4.10(10) B.12(1) Note 2 N 1.4.10(11) B.12 Note 3 N 1.4.11 A.5(1) Note 2 N The last sentence of QATR B.8 is does not B.2(1) establish a new or different require-ment. It 4
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B B.8 states the commitment to assure applicable B.14(1) equipment is not put into service until Appendix C successfully tested. This concept is inclusive to FSAR 1.4.11.
1.4.12 B.9 The bullets in B.9 are not explicitly I described in FSAR 1.4.12. They are industry standard practices not described in FSAR 1.4.12.
1.4.13 A.5(1) Methodology details described in QATR I B.7 B.7 are not explicitly described in FSAR B.16 1.4.13.
1.4.14 B.10 Note 2 N B.16(1) B.10 states that workmens protection provisions comply with federal, state, and OSHA regulations. Although not QA related, federal and state safety regulations are implemented via site procedures.
1.4.15 A.6(3) Note 2 N A.6(4)
B.2(1)
B.2(2)
B.13(1) 1.4.16 A.2 Note 2. The QATR does not explicitly N Documentation close-out and retention is A.6 address follow-up reviews to close required by QATR B.15, which meets B.13(1) out the corrective action criterion 17 of Appendix B.
documentation.
1.4.17(1) B.2(3) Note 2 N B.15 1.4.17(2) A.5(1) Note 2 N B.15 1.4.17(3) B.15(2) Note 2 N 1.4.18(1) C.3(1) Note 2 N 1.4.18(2) C.3(1) 1.4.18 states that NOS performs audits R See Enclosure 6 under the cognizance of the JOSRC (or 5
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B OSRC). The QATR does not require a OSRC be established 1.4.18(3) C.3(1) Note 2 N 1.4.18(4) C.3(2) Note 2 N 1.4.18(5) A.5 QATR replaces audits at defined R Appendix B requires a system of planned C.3(1) frequencies with performance-based and periodic audits. The provisions of the Table 1 assessments unless required by QATR provide for such a system in manner Table 2 regulation. In addition, the previous 1, that assures appropriate topic coverage 2, and 3 year fire protection using both a defined frequency and a assessments are replaced by a 2 year performance-based approach. The change assessment using a qualified fire in fire protection frequency is supported by protection specialist. NRC approval on 8/30/96 for the same change made by PECO Nuclear for its Limerick and Peach Bottom plants.
QATR replaces auditor qualifications The QATR process for auditor qualification per N45.2.23 with NQA-1, 2S-3, with an establishes a performance based exception regarding the number of qualification process. Appendix B does not audits needed for qualification. require a qualification process based on the number of assessment conducted by the lead auditor candidate. See Enclosure 3.
None B.16(1) QATR explicitly describes various I Appendix B does not explicitly describe maintenance activities. Activities maintenance activities.
affecting maintenance are implied in applicable sections of FSAR 1.4.
1.4.19.1 Appendix A Note 2 N 1.0 1.4.19.2 Appendix A 1.4.19.2 lists Licensing and Training as R Appendix B does not address PORC. The 6
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B 2.0 possible members of PORC. The Plant Manager may require qualified QATR does not list these groups. Note individuals from Licensing and Training, or 3 other disciplines, be members of PORC. If so, their membership will be documented in implementing procedures.
1.4.19.3 A.5(1) Note 2 N A.7.3(1) 1.4.19.4 A.5(1) Note 2 N A.7.3(1) 1.4.19.5 App A 3.0 Note 3. Minimum meeting frequency to R Previous industry guidance for PROC did be established in implementing not address meeting frequency. Appendix B procedures. does not address onsite reviews, therefore the QATR continues to meet Appendix B.
1.4.19.6 App A 3.0 Note 3 Quorum requirements to be R Previous industry guidance for PROC did established in implementing procedures not address quorum requirements.
Appendix B does not address onsite reviews, therefore the QATR continues to meet Appendix B.
1.4.19.7 None Requiring a List of PORC members be R Appendix B does not address PORC.
maintained and updated annually is not QATR Appendix A, 2.0 establishes described in the QATR. PORC membership requirements.
membership is documented in implementing procedures. Note 3 1.4.19.8 B.14 (1) PORC review of procedures is deleted R Deletion of PORC review of procedures is App A 4.0 based on NRC SER dated August 11, consistent with the provisions of the cited 1999, Safety Evaluation by the Office SER, and the necessary review of Nuclear Reactor Regulation Related requirements are included n Section B.14 of to Amendment No. 190 to Facility the QATR. The provisions for procedure Operating Licensing No. DPR-27, review and approval continue to meet Wisconsin Electric Power Company Appendix B requirements.
Point Beach Nuclear Plant, Unit s 1 and 2, Docket Nos. 50-266 and 50-301.
PORC review of programs reduced to those common to all current QAPDs at Appendix B does not address PORC 7
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B NMC plants. activities. The previous industry guidance for this function was not explicit regarding PORC review of specific programs.
Reduction to the set common to all NMC plants provides consistency. The QATR continues to meet Appendix B.
1.4.19.9 App A 1.0 Note 2 N App A 5.0 1.4.19.9 describes the JOSRC (or R See Enclosure 6.
App A 6.0 OSRC) relationship to PORC. The B.15 QATR does not require the establishment of a JOSRC.
The QATR requires subcommittees I report to full committee.
QATR establishes routing of PORC R Appendix B does not address PORC or the minutes to the onsite management specifics of how its reviews should be above the Plant Manager. conducted or routed. Thus the QATR continues to meet Appendix B.
1.4.20 None The QATR does not require the R See Enclosure 6.
establishment of a JOSRC (or OSRC).
Table 1.4-1 A.7.3 The list of items addressed is effectively N the same with the update to NQA-1 and its effect on Regulatory Guides.
Table 1.4-2 A.1(4 and 5) The table describes augmented quality R Note 3 characteristics assigned to the process or system.
Table 1.4-3 A.1(4 and 5) The table describes augmented quality R Note 3 characteristics assigned to the process or system.
Table 1.4-4 A.1(4 and 5) The table describes augmented quality R Note 3 characteristics assigned to the process or system.
Table 1.4-5 1.A B.14(1) Note 2 N B.14(2)
Table 1.4-5 1.B A.5 Note 2 N 8
Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B A.7.3(3)
B.14(1)
B.14(2)
Table 1.4-5 1.C A.5 Note 2 N A.7.3(3)
B.14(1)
B.14(2)
Table 1.4-5 1.D B.14(1) Note 2 N B.14(2)
Table 1.4-5 2.A B.14(1) Note 2 N B.14(2)
Table 1.4-5 2.B B.14(3) Note 2 N Table 1.4-5 2.C B.14(3) The additional approval requirements R Appendix B does not require subsequent within the two week period described in reviews of temporary procedure changes as Table 1.4-5 2.C is not contained in the described in the first sentence of Table 1.4-QATR. 5 2.C. Temporary change review process is Approval of temporary procedure described in B.14. Therefore, the QATR will changes is described in B.14 continue to meet applicable temporary procedure change review and approval requirements.
Table 1.4-6 B.15 The list of records and retention periods R/N/I NRC has endorsed the requirements of is replaced by NQA-1-1994, Basic NQA-1, via RG 1.28, as an acceptable Requirement 17 and 17S-1, with the means of compliance with Criterion 17 of guidance of RG 1.28. However, the Appendix B. Therefore, the QATR will explicit items and retention periods of continue to meet applicable record the QAPD are not presented in the requirements.
QATR. Note 2 Figure 1.4-1 None The QATR does not provide charts. N The descriptions provided in A.2 provide explicit reporting relationships.
Note 2 None B.17 The current QAPD does not address I Computer Software Quality Assurance as explicitly as this section and its commitment to NQA-1, Subpart 2.7.
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Enclosure 2, Number 5 QA Program Comparison Matrix Point Beach Nuclear Plant Current FSAR 1.4 QATR Section (Paragraph) Section s R/N/I (Note 1) Basis for QATR as Changed Continuing (Paragraph) to Meet Appendix B None A.7.3 The current QAPD does not address I RIS-2000-18 use of electronic media for records management or storage. This is a new commitment.
NOTES:
- 1. R = Reduction in Commitment N = Not a Reduction in Commitment I = Increase in Commitment
- 2. Wording in the QATR and commitments to detailed requirements of NQA-1-1994 established equivalent requirements or commitments.
Any wording difference is the result of format needs associated with changing to Standard Review Plan 17.3 format. 10 CFR 50.54(a)(3)(i) or (v) apply.
- 3. Methodology details in the current description may not be included in the NMC QATR. The intent of the QATR is to describe appropriate/sufficient requirements to establish how the quality assurance program meets 10 CFR 50, Appendix B, but to allow flexibility in the manner by which a requirement is met. Therefore, this change in methodology detail is not considered to be a reduction in commitment.
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Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Ref: Xcel Energy - Operational Quality Assurance Plan, Revision 25, effective date: 5/08/2003 NMC QATR [Rev. 0a, October 10,2003]
General Note - The Xcel OQAP included Fire Protection Program requirements throughout the body of the document. Fire Protection Program requirements are not part of the NMC QATR. Therefore, all references to Fire Protection will be transferred to separate site documents. Specific Fire Protection references are not detailed in the Table below. QATR commitment to Quality Assurance requirements for Fire Protection made in A.7.3, Branch Technical Position CMEB 9.5-1.
Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 1.1 Policy Statement Note 2 N 1.2 Policy Note 2 N Statement, A.7.1
& A.7.2 1.3 A.7.3 Note 2 N The OQAP commitments to ANSI N18.7 and the ANSI N45.2 series of standards are replaced as described in the QATR by commitment to NQA-1-1994.
1.4 A.1 (1, 3) Note 2 N 1.5 A.1, A.5 Note 2 N 1.6 A.3(2) Note 2 N C.1 (1, 3) Referenced sections equivalent to CNO periodic review of C.3 (3), OQAP.
2.0 A.1 (2) Note 2 N 3.1 A.1, A.2, A.4 Note 2 N 3.2 A.2.1, A.2.2, A.3, Note 2 The QATR does not provide charts. The descriptions N A.4 provide explicit reporting relationships.
4.1 Policy Note 2 N Statement, A.1, A.5, A.3, B.7, B.11, B.12, C.1 4.2 A.1, A.2 Note 2 N 4.3 A.1, A.2, A.2.1, Note 2 N B.1, B.14, C.1 (1, Referenced sections equivalent to 4.3.2 periodic review of 3), C.3 (3), OQAP.
4.4 A.1, B.1 Note 2, Note 3 N 4.5 A.1 (3, 4) Note 2 , Note 3 N 4.6 A.1 (3, 4) Note 2 N 1
Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 4.7 A.2, A.2.1.2.b Note 2, Note 3 R Dispute resolution is not discussed in 4.7.2 - Dispute resolution not discussed in QATR. Appendix B. The QATR specifies organization and responsibilities that meet Appendix B.
4.8 A.1 (4), B.14(1) List of structure system components has been removed from R Programs (lists) are included in plant QATR. Criteria provided for determining list are included in specific documents.
A.1(4). This meets Appendix B requirements to identify applicable SSCs.
4.9 A.3 (3), A.5 (1) Note 2 N 5.1 B.2 Note 2 N 5.2 A.1, B.2, B.3 Note 2 N 6.1 B.4 (1) Note 2 N 6.2 A.1, A.7.1, A.7.3, Note 2 N B.4 (1, 4), B.5 (1) Note 3 6.3 B.4 Note 2, Note 3 R Reviews imply approvals. This is an Approvals by management are not specifically stated in the administrative requirement. The QATR QATR. provides for reviews of procurement documents to assure the requirements of Appendix B are met.
6.4 A.7.3 (BTP Note 2 N CMEB 9.5-1) 7.1 A.1 (3, 6) Note 2 N 7.2 A.1 (3), B.14 (1), Note 2 N Appendix B(2) 7.3 A.1 (8), B.14 (1), Note 2 N Appendix,B B.11 (1) 7.4 A.1 (6) Note 2 N 8.1 B.14 (1, 2), B.16 Note 2 N 8.2 A.3 (5), B.1, Note 2 N B.14 (1, 2) 8.3 A.3 (5), B.1, Note 2 N B.14 (1, 2) 8.4 B.14 (1, 2, 3) Note 2, Note 3 N 8.5 A.1 (6), B.14 (1) Note 2, Note 3 N 8.6 B.2 (1) Note 2 N 2
Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 8.7 A.1 (4), B.14, Note 2 N A.7.3 (Reg Guide 7.10),
Appendix B 8.8 B.14 Note 2 N 8.9 B.14 (1) Note 2 N 9.1 B.4, B.5 (1) Note 2 N 9.2 A.1, B.4 Note 2 N 9.3 B.4 (3rd bullet) Note 2 N 9.4 B.12 (1), B.4 (5th Note 2 N bullet) 10.1 B.6 (1) Note 2 N 10.2 B.6 (1), B.7 (1) Note 2 N 10.3 B.6 (1), B.7 (1) Note 2 N 10.4 B.12 (1), B.4 (5th Note 2 N bullet), B.13 10.5 None No specific reference for protection against theft or diversion R Meets 10CFR50 App. B requirements.
in new QATR. Security Plan addresses theft/diversion of nuclear fuel.
11.1 B.11 (1) Note 2 N 11.2 A.1 (6), B.11 Note 2, Note 3 R The definition of Special Processes in the QATR encompasses the examples Brazing not specifically referenced in QATR not listed, and the list included matches 10 CFR 50, App. B.
11.3 A.5 (1), B.11 (2) Note 2 N NQA-1, Basic Requirement 9, Supplement 9S-1 requires qual of personnel.
11.4 A.1 (6), Note 2, Note 3 R The definition of Special Processes in B.11 (1, 2) the QATR encompasses the examples Heat Treating not specifically referenced in QATR not listed, and the list included matches 10 CFR 50, App. B.
12.1 A.1 (4, 5), B.10 Note 2 N (1), B.12 (1, 2),
App. B(Test &
Inspection Proc.)
12.2 B.10 (1), B.12 (1, Note 2 N 2), App. B(Fuel Handling Proc.)
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Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 12.3 A.5 (1), Note 2 N B.12 (1, 2) NMC commits to NQA-1 for qualifications 12.4 B.12 (1), B.16 Note 2, Note 3 N 12.5 A.5 (1, 2), Note 2 N B.12 (1, 3), B.16 Qualifications per NQA-1 12.6 A.5 (1), B.12 (1) Note 2, Note 3 R Technical Services are not specified in Technical Services not specifically mentioned in QATR Appendix B. The QATR provides for inspections that meet Appendix B.
12.7 A.5 (1), Note 2 N B.4 (5th bullet) Qualifications per NQA-1 12.8 A.5, B.4 (1), Note 2 N B.5 (1), B.12 Qualifications per NQA-1 12.9 A.7.3 Note 2 N General inspection measures listed in B.4, B.10 and B.12.
12.10 A.1 (4) Note 2 N 12.11 A.1(5) Note 3 R The QATR established requirements A.12 Emergency Equipment inspections not specifically addressed for inspections that meet Appendix B.
in QATR 12.12 A.5, B.7 (2 - 3rd Note 2 N bullet 12.13 A.5 (2), B.11 Note 2, Note 3 N Specific NDE methods are not listed in the QATR, but are as listed in SNT-TC-1A and/or CP-189.
12.14 B.12, App. Note 2 N B(Test & Insp.
Procedures) 13.1 B.8, B.10, Note 2 N Appendix B (Test & Insp.
Procedures) 13.2 A.5, B.8 (1), Note 2 N Appendix B (Test & Insp.
Procedures) 13.3 B.8 (1) Note 2 N 13.4 B.4 (5th bullet), Note 2 R Appendix B, Criterion VII, requires tests B.8 (1) OQAP - requires completion of proof tests prior to installation. prior to installation or use, The QATR QATR - requires proof test completion prior to operability. meets this requirement..
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Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 13.5 B.8, Appendix B Note 2 N (Test & Insp. Note 3 Procedures) 13.6 A.5 (1) Note 2 N 14.1 B.9 (1) Note 2 N 14.2 B.9 (1) Note 2 N 14.3 B.9 (1 - 4th Note 2 R Appendix B requires that M&TE be bullet) National Institute of Standards & Technology (NIST) is properly controlled, calibrated, etc, to specified in OQAP, but not QATR. However, the national maintain accuracy within specified standards wording in the QATR provides necessary control. limits. The QATR provides controls that meet this requirement.
15.1 B.7 (1) Note 2 N 15.2 B.7 Note 2 N 15.3 B.7 Note 2 R 10CFR50 App. B does not specify fuel No specific reference to nuclear fuel storage in QATR storage requirements.
15.4 B.7 Note 2 R 10 CFR 20 encompasses radioactive No specific reference to radioactive material storage in QATR material storage requirements.
15.5 B.7 Note 2 N 15.6 B.7 Note 2 N 15.7 A.1 (4), Note 2 N B.7 (3rd bullet) 16.1 B.10 Note 2 N 16.2 B.16 Note 2, Note 3 N See NQA-1, Subpart 2.18, para 2.5(c for ref to ALARA 16.3 B.8, B.10 Note 2 N 16.4 B.10 Note 2, Note 3 N 16.5 B.10 Note 2, Note 3 R Security related Key control is covered No specific reference to key control in QATR in the Site Security Plan. The QATR provides for control measures that meet Appendix B, Criterion 14.
16.6 B.2(4) Note 2, Note 3 N B.10 16.7 A.7.1 Note 2, Note 3 R This is not an Appendix B topic. Site Radioactive Material control is not detailed in the QATR. program procedures include rad material control.
16.8 App. B (Start-up Note 2 N Procedures) 17.1 A.6 (3), B.6, B.13 Note 2 N 5
Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 17.2 B.4 (4th and 5th Note 2, Note 3 N bullets), B.13 (3) 17.3 B.13 (3) Note 2 , Note 3 N 17.4 B.13 Note 2 , Note 3 N 17.5 A.6, B.13 Note 2 N 17.6 A.7.1, A.2.1.2 Note 2 N 18.1 A.6 (2), B.13 Note 2 N 18.2 A.6 (2), B.13 Note 2, Note 3 N 18.3 C.3 (2) Note 2 N 19.1 B.15 (1, 2) Note 2, Note 3 N 19.2 B.15 (3) Note 2, Note 3 N 19.3 B.15 (1) Note 2 N 19.4 B.15 (1) Note 2 N 19.5 A.5 (1), B.15 (1) Note 2 N 19.6 B.4 (4th bullet), Note 2 N B.15 (1) 19.7 B.8, B.15 (1) Note 2 N 19.8 C.3 (3), B.15 (1) Note 2 N 19.9 B.15 Note 2, Note 3 N 19.10 B.2 (3), B.14 (1), Note 2 N B.15 (1) 19.11 B.15 Note 2 N 19.12 B.15 (2) Note 2, Note 3 R Retention times are required to be Retention times for operating records are not specified in specified in RMS procedures, per NQA-QATR, but are specified in OQAP. 1, Supplement 17S-1, 2.8. The requirements of NQA-1 for records maintenance have been endorsed by the NRC via RG 1.28 as meeting Appendix B requirements. Therefore, the QATR, which commits to NQA-1, continues to meet Appendix B.
20.1 C.1 (2), Note 2 N C.3 (2, 3) 20.2 C.3 (1, 3) Note 2 N 6
Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 20.3 C.3 (1) Note 2 R 10CFR50, App. B requires a system of The QATR replaces audits at defined frequencies (maximum planned and periodic audits. The of 2 years) with performance-based assessments (dynamic provisions of the QATR provide for schedule frequencies). Certain topics retain designated such a system in a manner that frequencies where required by regulation. assures appropriate topic coverage using both a defined frequency and a performance-based approach.
20.4 C.1 (2, 4) Note 2 N 20.5 C.3 (2, 3) Note 2 N 20.6 C.3 (3) Note 2, Note 3 R Dispute resolution is not discussed in QATR does not specify who resolves disputes. Appendix B. See 4.7, above.
21.0 N/A The QATR does not provide requirements for Offsite Safety R See Enclosure 6.
Review Committee.
22.1 Appendix A (2.0, Note 2, Note 3 N 3.0) QATR requires member appointment by the Plant Manager.
22.2 Appendix A (3.0) Note 2, Note 3 R Previous industry guidance for PORC QATR says minimal frequency will be specified in procedures. did not address meeting frequency.
Appendix B does not address onsite reviews, therefore the QATR continues to meet Appendix B.
22.3 Appendix A (3.0) Note 2, Note 3 R Previous industry guidance for PORC QATR references quorum will be established per procedure. did not address quorum requirements.
Appendix B does not address onsite review, therefore the QATR continues to meet Appendix B.
22.4 Appendix A (4.0) Note 2, Note 3 R 10CFR50, App. B does not specify any QATR does not cover topics in 2.2.7/9/10/11/13, nor results of required reviews, however, the reviews tests and experiments per 22.4.1. specified are consistent with previous industry guidance for what offsite PORC review of procedures is deleted based on NRC SER reviews should cover.
dated August 11, 1999, Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 190 Deletion of PORC review of procedures to Facility Operating License No. DPR-24 and Amendment is consistent with the provisions of the No. 195 to Facility Operating License No. DPR-27, Wisconsin cited SER, and the necessary review Electric Power Company Point Beach Nuclear Plant, Units 1 requirements are included in section and 2, Docket Nos. 50-266 and 50-301. B.14 of the QATR. The provisions for procedure review and approval continue to meet Appendix B requirements.
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Enclosure 2, Number 6 QA Program Comparison Matrix PRAIRIE ISLAND Nuclear Plant Current OQAP QATR Section R/N/I Basis for QATR as Changed Section (paragraph) s (Note 1) Continuing to Meet Appendix B 22.5 Appendix A (5.0) Note 2, Note 3 R This is not addressed by Appendix B.
QATR does not describe the process to resolve disagreements. QATR does not require notification of disagreement to OSRC.
22.6 Appendix A (6.0) Note 2, Note 3 R Appendix B does not specify QATR doesnt specify the additional distribution requirements requirements for onsite reviews.
cited in the OQAP 22.7 Appendix A (1.0) Note 2, Note 3 N Appendix B - A.1 (4) Note 2, Note 3 R List will be relocated at PINGP, outside Systems, and QATR references A list, or other means of identification, of of the QATR.
Components Subject safety related Systems, Structures, and Components (SSC) to Appendix B of under the control of the QAP is established and maintained 10CFR50 for each operating plant.
Appendix C - Fire Protection Note 2, Note 3 R Fire Protection program will be Nuclear Plant Fire Program is not relocated at PINGP outside of the Protection Program included in the The previous 1, 2 and 3-year fire protection assessments, per QATR.
QATR. 14.0, are replaced by a 2-year assessment using a qualified offsite fire protection specialist. The change in fire protection frequency Table 2 for Fire is supported by NRC approval on Protection Audit 8/30/96 for the same change made by frequency. PECO Nuclear for its Limerick and Peach Bottom plants.
None B.16 Control of Plant Maintenance is not addressed in the OQAP. I None B.17 Computer Software Control is not addressed in the OQAP. I None A.7.3 (RIS 200- Electronic records are not addressed in the OQAP. I 18)
None C.2 Self-assessment is not addressed in the OQAP. I NOTES:
- 1. R = Reduction in Commitment.
N = Not a Reduction in Commitment.
I = Increase in commitment.
- 2. Wording in the QATR establishes equivalent requirements or commitments. Any wording difference is the result of format needs associated with changing to Standard Review Plan 17.3 format. 10 CFR 50.54(a)(3)(i) and/or (v) apply.
- 3. Methodology details in the current program description may not be included in the NMC QATR. The intent of the QATR is to describe appropriate/sufficient requirements to establish how the quality assurance program meets 10CFR50, Appendix B, but to allow flexibility in the manner by which a requirement is met. Therefore, this change in methodology detail is not considered to be a reduction in commitment.
8