ML18220B101

Attachment - Vogtle Electric Generating Plant Unit 3 Amendment 140 (LAR-18-014)

ML18220B101
Person / Time
Site:	Vogtle
Issue date:	08/24/2018
From:	Manny Comar NRC/NRO/DLSE/LB1
To:	Whitley B Southern Nuclear Operating Co
Comar M/415-3863
Shared Package
ML18220B095	List: ML18220B096 ML18220B097 ML18220B098 ML18220B099 ML18220B100 ML18220B101 ML18220B103 ML18220B104
References
EPID L-2018-LLA-0115 LAR 18-014
Download: ML18220B101 (3)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 140 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-255 C-255 (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, 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. 140, 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. 140 C-255 Amendment No. 140 Table 2.3.10-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 440 2.3.10.05b 441 2.3.10.06a 442 2.3.10.06b 443 2.3.10.07a.i 444 2.3.10.07a.ii i) Inspection will be performed for retrievability of the displays of containment sump level channels WLS-034, WLS-035, and WLS-036 in the MCR. i) Nonsafety-related displays of WLS containment sump level channels WLS-034, WLS-035, and WLS-036 can be retrieved in the MCR. 7.b) The WLS provides the nonsafety-related function of controlling releases of radioactive materials in liquid effluents. Tests will be performed to confirm that a simulated high radiation signal from the discharge radiation monitor, WLS-RE-229, causes the discharge isolation valve WLS-PL-V223 to close. A simulated high radiation signal causes the discharge control isolation valve WLS-PL-V223 to close. 8. Controls exist in the MCR to cause the remotely operated valve identified in Table 2.3.10-3 to perform its active function. Stroke testing will be performed on the remotely operated valve listed in Table 2.3.10-3 using controls in the MCR. Controls in the MCR operate to cause the remotely operated valve to perform its active function. 9. The check valves identified in Table 2.3.10-1 perform an active safety-related function to change position as indicated in the table. Exercise testing of the check valves with active safety functions identified in Table 2.3.10-1 will be performed under pre-operational test pressure, temperature and flow conditions. Each check valve changes position as indicated on Table 2.3.10-1. 10. Displays of the parameters identified in Table 2.3.10-3 can be retrieved in the MCR. Inspection will be performed for retrievability of the displays identified in Table 2.3.10-3 in the MCR. Displays identified in Table 2.3.10-3 can be retrieved in the MCR. 445 2.3.10.07b 446 2.3.10.08 447 2.3.10.09