ML18072A059

Attachment - Vogtle Unit 4 LAR 17-018

ML18072A059
Person / Time
Site:	Vogtle
Issue date:	04/18/2018
From:	NRC/NRO/DNRL/LB4
To:	Whitley B Southern Nuclear Operating Co
habib d/415-1035
Shared Package
ML18072A051	List: ML17320A798 ML18072A053 ML18072A054 ML18072A055 ML18072A056 ML18072A057 ML18072A058 ML18072A059
References
EPID L-2017-LLA-0092, LAR 17-018
Download: ML18072A059 (4)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 120 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-334 C-334 C-342 C-342 (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, for Changes and SNC shall report the change to the Director of NRO, or the 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. 120, 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. 120 C-334 Amendment No. 120 2.6.3 Class 1E dc and Uninterruptible Power Supply System Design Description The Class 1E dc and uninterruptible power supply system (IDS) provides dc and uninterruptible ac electrical power for safety-related equipment during normal and off-normal conditions. The IDS is as shown in Figure 2.6.3-1 and the component locations of the IDS are as shown in Table 2.6.3-4. 1. 2. 3. 4. a) b) c) d) e) f) g) h) i) j) 5. a) b) c)

C-342 Amendment No. 120 Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 608 2.6.03.04h 609 2.6.03.04i 876 2.6.03.04j Type tests, analyses, or a combination of type tests and analyses of the isolation devices will be performed. A report exists and concludes that the battery monitor fuse isolation panels prevent credible faults from propagating into the Class 1E portions of the IDS. 610 2.6.03.05a 611 2.6.03.05b 612 2.6.03.05c 613 2.6.03.05d.i