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, 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. 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

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 Not used per Amendment No. 85 441 2.3.10.06a Not used per Amendment No. 85 442 2.3.10.06b Not used per Amendment No. 85 443 2.3.10.07a.i Not used per Amendment No. 113 444 2.3.10.07a.ii 7.a) The WLS provides the nonsafety- i) Inspection will be performed i) Nonsafety-related displays related function of detecting leaks for retrievability of the displays of WLS containment sump within containment to the containment of containment sump level level channels WLS-034, sump. channels WLS-034, WLS-035, WLS-035, and WLS-036 can and WLS-036 in the MCR. be retrieved in the MCR.

ii) Testing will be performed by ii) A report exists and adding water to the sump and concludes that sump level observing display of sump level. channels WLS-034, WLS-035, and WLS-036 can detect a change of 1.34 +/- 0.5 inches.

7.b) The WLS provides the nonsafety- Tests will be performed to A simulated high radiation related function of controlling releases confirm that a simulated high signal causes the discharge of radioactive materials in liquid radiation signal from the control isolation valve effluents. discharge radiation monitor, WLS-PL-V223 to close.

WLS-RE-229, causes the discharge isolation valve WLS-PL-V223 to close.

8. Controls exist in the MCR to cause Stroke testing will be performed Controls in the MCR operate the remotely operated valve identified on the remotely operated valve to cause the remotely operated in Table 2.3.10-3 to perform its active listed in Table 2.3.10-3 using valve to perform its active function. controls in the MCR. function.

9. The check valves identified in Table Exercise testing of the check Each check valve changes 2.3.10-1 perform an active safety- valves with active safety position as indicated on Table related function to change position as functions identified in Table 2.3.10-1.

indicated in the table. 2.3.10-1 will be performed under pre-operational test pressure, temperature and flow conditions.

10. Displays of the parameters Inspection will be performed for Displays identified in Table identified in Table 2.3.10-3 can be retrievability of the displays 2.3.10-3 can be retrieved in retrieved in the MCR. identified in Table 2.3.10-3 in the MCR.

the MCR.

445 2.3.10.07b Not used per Amendment No. 113 446 2.3.10.08 Not used per Amendment No. 113 447 2.3.10.09 Not used per Amendment No. 113 C-255 Amendment No. 140