ML19113A256
| ML19113A256 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/20/2019 |
| From: | Peter Hearn NRC/NRO/DLSE/LB2 |
| To: | Southern Nuclear Operating Co |
| HEARN P/NRO | |
| Shared Package | |
| ML19113A253 | List: |
| References | |
| EPID L-2018-LLA-0310, LAR 18-028 | |
| Download: ML19113A256 (3) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 161 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-421 C-421
(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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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. 161, 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)
- 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. 161
C-421 Amendment No. 161 Table 3.3-3 Class 1E Divisions in Nuclear Island Fire Areas Fire Area Number Class 1E Divisions A
C B
D Auxiliary Building Radiologically Controlled 1200 AF 01 Yes Yes 1220 AF 02 Yes Auxiliary Building Non-Radiologically Controlled 1200 AF 03 Yes Yes 1201 AF 02 Note 2 Note 2 Yes Yes 1201 AF 03 Note 2 Note 2 Yes Yes 1201 AF 04 Yes Yes 1201 AF 05 Yes Yes 1201 AF 06 Yes Yes 1202 AF 03 Note 2 Yes Note 2 Note 2 1202 AF 04 Yes Note 2 Note 2 Note 2 1220 AF 01 Yes Yes 1230 AF 01 Yes Yes 1230 AF 02 Yes Yes 1240 AF 01 Yes Yes 1242 AF 02 Yes Yes 1250 AF 01 Yes Yes Note 1: Dash (-) indicates not applicable.
Note 2: Cables from this division in this fire area are limited to interdivisional cables terminating in this fire area.
Table 3.3-4 is not used.