ML19113A258

Attachment - Vogtle Electric Generating Plant, Unit 4 Amendment 159(LAR-18-028)

ML19113A258
Person / Time
Site:	Vogtle
Issue date:	05/20/2019
From:	NRC/NRO/DLSE/LB2
To:	Southern Nuclear Operating Co
HEARN P/NRO
Shared Package
ML19113A253	List: ML19113A254 ML19113A255 ML19113A256 ML19113A257 ML19113A258 ML19113A259 ML19113A260 ML19113A261
References
EPID L-2018-LLA-0310, LAR 18-028
Download: ML19113A258 (3)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 159 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 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-92 REMOVE INSERT 7 7 Appendix C to Facility Combined License No. NPF-92 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 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. 159, 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. 159

Table 3.3-3 Class 1E Divisions in Nuclear Island Fire Areas Class 1E Divisions Fire Area Number 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 - -

Yes Yes Note 2 Note 2 1201 AF 03 - -

Yes Yes Note 2 Note 2 1201 AF 04 - - Yes Yes 1201 AF 05 - - Yes Yes 1201 AF 06 - - Yes Yes 1202 AF 03 - - -

Yes Note 2 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.

C-421 Amendment No. 159