ML18026A770: Difference between revisions
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| author name = Hoellman J | | author name = Hoellman J | ||
| 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 | ||
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| page count = 2 | | page count = 2 | ||
| project = EPID:L-2017-LLA-0103 | | project = EPID:L-2017-LLA-0103 | ||
| stage = | | stage = Acceptance Review | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 109 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO. 52-025 Replace the following page of the Facility Combined License No. NPF-91 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change. | {{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 109 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO. 52-025 Replace the following page of the Facility Combined License No. NPF-91 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change. | ||
Facility Combined License No. NPF-91 REMOVE INSERT | Facility Combined License No. NPF-91 REMOVE INSERT 7 7 | ||
(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR 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, | (7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR 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. 109, 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: | |||
: 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. 109}} | (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. 109}} |
Latest revision as of 22:52, 7 March 2020
ML18026A770 | |
Person / Time | |
---|---|
Site: | Vogtle |
Issue date: | 02/22/2018 |
From: | Jordan Hoellman NRC/NRO/DNRL/LB4 |
To: | Whitley B Southern Nuclear Operating Co |
hoellman j/415-5481 | |
Shared Package | |
ML18026A765 | List: |
References | |
EPID L-2017-LLA-0103, LAR 17-035 | |
Download: ML18026A770 (2) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 109 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO.52-025 Replace the following page of the Facility Combined License No. NPF-91 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the area of change.
Facility Combined License No. NPF-91 REMOVE INSERT 7 7
(7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR 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. 109, 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. 109