ML17305A015

Attachment - Vogtle Unit 3 Amendment 105 (LAR-17-019)

ML17305A015
Person / Time
Site:	Vogtle
Issue date:	01/09/2018
From:	Manny Comar NRC/NRO/DNRL
To:	Southern Nuclear Operating Co
COMAR M/415-3863
References
CAC RP9268, LAR 17-019
Download: ML17305A015 (4)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 105 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 A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 3.4.8-1 3.4.8-1 3.4.8-2 3.4.8-2

(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 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. 105, 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. 105

Technical Specifications Minimum RCS Flow 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Minimum RCS Flow LCO 3.4.8 At least one Reactor Coolant Pump (RCP) shall be in operation with a total flow through the core of 3,000 gpm.

- NOTES -

1. a. All RCPs may be removed from operation for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period for the purpose of testing; or

b. With no RCPs in operation, an unborated water source through the chemical mixing tank may be unisolated under administrative controls for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for the purpose of chemical addition to the pressurizer; provided:

i. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and ii. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. No RCP shall be started when the RCS temperature is 350°F unless pressurizer level is < 92%.

3. No RCP shall be started with any RCS cold leg temperature 350°F unless the secondary side water temperature of each steam generator (SG) is 50°F above each of the RCS cold leg temperatures and the RCP is started at 25% of RCP speed.

APPLICABILITY: MODES 3, 4, and 5 with Plant Control System incapable of rod withdrawal, all rods fully inserted, and unborated water sources not isolated from the RCS.

VEGP Units 3 and 4 3.4.8 - 1 Amendment No. 105 (Unit 3)

Amendment No. 104 (Unit 4)

Technical Specifications Minimum RCS Flow 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- A.1 Isolate all sources of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

- NOTE - unborated water.

Required Action A.2 shall be completed prior AND to starting any RCP whenever this Condition A.2 Perform SR 3.1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is entered.

No RCP in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify at least one RCP is in operation with total flow 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> through the core 3,000 gpm.

VEGP Units 3 and 4 3.4.8 - 2 Amendment No. 105 (Unit 3)

Amendment No. 104 (Unit 4)