ML18051A668

Attachment - Vogte Electric Generating Plant Unit 3 Amendment 114 (LAR-17-025)

ML18051A668
Person / Time
Site:	Vogtle
Issue date:	03/08/2018
From:	NRC/NRO/DNRL/LB4
To:
References
EPID L-2017-LLA-0134, LAR 17-025
Download: ML18051A668 (3)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 114 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-64a C-64a

(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 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. 114, 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. 114

Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 39 2.1.02.08d.viii Not used per Amendment No. 113 40 2.1.02.08e 8.e) The RCS provides emergency letdown Inspections of the reactor A report exists and during design basis events. vessel head vent valves and concludes that the capacity inlet and outlet piping will be of the reactor vessel head conducted. vent is sufficient to pass not less than 9.0 lbm/sec at 2500 psia in the RCS.

C-64a Amendment No. 114