ML19003A484

Attachment to Amendment 152 - Vogtle Electric Generating Plant Unit 3

ML19003A484
Person / Time
Site:	Vogtle
Issue date:	01/28/2019
From:	Office of New Reactors
To:	Southern Nuclear Operating Co
PATEL C/415-3025
Shared Package
ML19003A479	List: ML19003A480 ML19003A481 ML19003A482 ML19003A483 ML19003A484 ML19003A485 ML19003A486 ML19003A487
References
EPID L-2018-LLA--0205, LAR 18-016
Download: ML19003A484 (3)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 152 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-226 C-226

(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. 152, 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. 152

Table 2.3.6-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 375 2.3.06.09b.ii 9.b) The RNS provides heat removal ii) Testing will be performed to ii) When tested individually, from the reactor coolant during confirm that the RNS can each RNS pump provides at shutdown operations. provide flow through the RNS least 1400 gpm net flow to the heat exchangers when the pump RCS when the hot leg water suction is aligned to the RCS hot level is at an elevation leg and the discharge is aligned 15.5 inches +/- 2 inches above to both PXS DVI lines with the the bottom of the hot leg.

RCS at atmospheric pressure.

iii) Inspection will be performed iii) The RCS cold legs piping of the reactor coolant loop centerline is 17.5 inches +/- 2 piping. inches above the hot legs piping centerline.

iv) Inspection will be performed iv) The RNS pump suction of the RNS pump suction piping. piping from the hot leg to the pump suction piping low point does not form a local high point (defined as an upward slope with a vertical rise greater than 3 inches).

v) Inspection will be performed v) The RNS suction line of the RNS pump suction nozzle connection to the RCS is connection to the RCS hot leg. constructed from 20-inch Schedule 140 pipe.

9.c) The RNS provides low pressure Testing will be performed to When tested individually, makeup flow from the cask loading pit confirm that the RNS can each RNS pump provides at to the RCS for scenarios following provide low pressure makeup least 1100 gpm net flow to the actuation of the ADS. flow from the cask loading pit to RCS with the water level the RCS when the pump suction maintained within the range of is aligned to the cask loading pit > 10 ft and < 15 ft from the and the discharge is aligned to bottom of the cask loading pit.

both PXS DVI lines with RCS at atmospheric pressure.

9.d) The RNS provides heat removal Testing will be performed to Two operating RNS pumps from the in-containment refueling water confirm that the RNS can provide at least 2000 gpm to storage tank (IRWST). provide flow through the RNS the IRWST.

heat exchangers when the pump suction is aligned to the IRWST and the discharge is aligned to the IRWST.

12.a) The motor-operated and check iii) Tests of the motor-operated iii) Each motor-operated valves identified in Table 2.3.6-1 valves will be performed under valve changes position as perform an active safety-related preoperational flow, differential indicated in Table 2.3.6-1 function to change position as indicated pressure and temperature under preoperational test in the table. conditions. conditions.

C-226 Amendment No. 152