ML18156A146: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
(2 intermediate revisions by the same user not shown) | |||
Line 3: | Line 3: | ||
| issue date = 07/10/2018 | | issue date = 07/10/2018 | ||
| title = Attachment - Vogtle Electric Generating Plant 3 (LAR 17-044) | | title = Attachment - Vogtle Electric Generating Plant 3 (LAR 17-044) | ||
| author name = Comar | | author name = Comar M | ||
| author affiliation = NRC/NRO/DNRL/LB4 | | author affiliation = NRC/NRO/DNRL/LB4 | ||
| addressee name = Whitley B | | addressee name = Whitley B | ||
| addressee affiliation = Southern Nuclear Operating Co, Inc | | addressee affiliation = Southern Nuclear Operating Co, Inc | ||
| docket = 05200025, 05200026 | | docket = 05200025, 05200026 | ||
Line 15: | Line 15: | ||
| page count = 3 | | page count = 3 | ||
| project = EPID:L-2017-LLA-0422 | | project = EPID:L-2017-LLA-0422 | ||
| stage = | | stage = Acceptance Review | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 130 | {{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 130 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO. 52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. | ||
Facility Combined License No. NPF-91 REMOVE INSERT 7 7 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-176 C-176 | |||
(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d). | |||
(b) SNC shall report any violation of a requirement in Section 2.D.(3), | |||
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within [[estimated NRC review hours::24 hours]]. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73. | |||
(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 130, are hereby incorporated into this license. | |||
(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g). | |||
(10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones: | |||
(a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program | |||
: 1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 130 | |||
Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 253 2.2.05.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.2.5-1 as ASME Code Section the as-built components and design reports exist for the as-III are designed and constructed in piping as documented in the built components and piping accordance with ASME Code Section ASME design reports. identified in Tables 2.2.5-1 III requirements. and 2.2.5-2 as ASME Code 2.b) The piping identified in Table Section III. | |||
2.2.5-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements. | |||
3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes components identified in Table 2.2.5-1 pressure boundary welds will be that the ASME Code Section as ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. non-destructive examination 3.b) Pressure boundary welds in piping of pressure boundary welds. | |||
identified in Table 2.2.5-2 as ASME Code Section III meet ASME Code Section III requirements. | |||
4.a) The components identified in Table A pressure test will be performed A report exists and concludes 2.2.5-1 as ASME Code Section III on the components and piping that the results of the pressure retain their pressure boundary integrity required by the ASME Code test of the components and at their design pressure. Section III to be pressure tested. piping identified in Tables 2.2.5-1 and 2.2.5-2 as ASME 4.b) The piping identified in Table Code Section III conform with 2.2.5-2 as ASME Code Section III the requirements of the ASME retains its pressure boundary integrity at Code Section III. | |||
its design pressure. | |||
5.b) Each of the lines identified in Table Inspection will be performed for A report exists and concludes 2.2.5-2 for which functional capability the existence of a report that each of the as-built lines is required is designed to withstand verifying that the as-built piping identified in Table 2.2.5-2 for combined normal and seismic design meets the requirements for which functional capability is basis loads without a loss of its functional capability. required meets the functional capability. requirements for functional capability. | |||
254 2.2.05.02b Not used per Amendment No. 85 255 2.2.05.03a Not used per Amendment No. 85 256 2.2.05.03b Not used per Amendment No. 85 257 2.2.05.04a Not used per Amendment No. 85 258 2.2.05.04b Not used per Amendment No. 85 C-176 Amendment No. 130}} |
Latest revision as of 04:55, 7 March 2020
ML18156A146 | |
Person / Time | |
---|---|
Site: | Vogtle |
Issue date: | 07/10/2018 |
From: | Manny Comar NRC/NRO/DNRL/LB4 |
To: | Whitley B Southern Nuclear Operating Co |
comar m/415-3863 | |
Shared Package | |
ML18156A141 | List: |
References | |
EPID L-2017-LLA-0422 | |
Download: ML18156A146 (3) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 130 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO.52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Combined License No. NPF-91 REMOVE INSERT 7 7 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-176 C-176
(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).
(b) SNC shall report any violation of a requirement in Section 2.D.(3),
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.
(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 130, are hereby incorporated into this license.
(9) Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).
(10) Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:
(a) Environmental Qualification Program implemented before initial fuel load; (b) Reactor Vessel Material Surveillance Program implemented before initial criticality; (c) Preservice Testing Program implemented before initial fuel load; (d) Containment Leakage Rate Testing Program implemented before initial fuel load; (e) Fire Protection Program
- 1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7 Amendment No. 130
Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 253 2.2.05.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.2.5-1 as ASME Code Section the as-built components and design reports exist for the as-III are designed and constructed in piping as documented in the built components and piping accordance with ASME Code Section ASME design reports. identified in Tables 2.2.5-1 III requirements. and 2.2.5-2 as ASME Code 2.b) The piping identified in Table Section III.
2.2.5-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.
3.a) Pressure boundary welds in Inspection of the as-built A report exists and concludes components identified in Table 2.2.5-1 pressure boundary welds will be that the ASME Code Section as ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. non-destructive examination 3.b) Pressure boundary welds in piping of pressure boundary welds.
identified in Table 2.2.5-2 as ASME Code Section III meet ASME Code Section III requirements.
4.a) The components identified in Table A pressure test will be performed A report exists and concludes 2.2.5-1 as ASME Code Section III on the components and piping that the results of the pressure retain their pressure boundary integrity required by the ASME Code test of the components and at their design pressure. Section III to be pressure tested. piping identified in Tables 2.2.5-1 and 2.2.5-2 as ASME 4.b) The piping identified in Table Code Section III conform with 2.2.5-2 as ASME Code Section III the requirements of the ASME retains its pressure boundary integrity at Code Section III.
its design pressure.
5.b) Each of the lines identified in Table Inspection will be performed for A report exists and concludes 2.2.5-2 for which functional capability the existence of a report that each of the as-built lines is required is designed to withstand verifying that the as-built piping identified in Table 2.2.5-2 for combined normal and seismic design meets the requirements for which functional capability is basis loads without a loss of its functional capability. required meets the functional capability. requirements for functional capability.
254 2.2.05.02b Not used per Amendment No. 85 255 2.2.05.03a Not used per Amendment No. 85 256 2.2.05.03b Not used per Amendment No. 85 257 2.2.05.04a Not used per Amendment No. 85 258 2.2.05.04b Not used per Amendment No. 85 C-176 Amendment No. 130