ML19133A174

Attachment - Vogtle Electric Generating Plant Unit 4 Amendment 160(LAR-18-030)

ML19133A174
Person / Time
Site:	Vogtle
Issue date:	06/12/2019
From:	Paul Kallan NRC/NRO/DLSE/LB2
To:	Southern Nuclear Operating Co
KALLAN P/NRO
Shared Package
ML19133A167	List: ML19133A168 ML19133A169 ML19133A170 ML19133A171 ML19133A172 ML19133A173 ML19133A174 ML19133A175
References
EPID L-2018-LLA-0569, LAR 18-030
Download: ML19133A174 (4)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 160 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-295 C-295 C-311 C-311

(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. 160, 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. 160

Table 2.5.2-5 Minimum Inventory of Displays, Alerts, and Fixed Position Controls in the MCR Description Control Display Alert(1)

Neutron Flux - Yes Yes Neutron Flux Doubling(2) - No Yes Startup Rate - Yes Yes Reactor Coolant System (RCS) Pressure - Yes Yes Wide-range Hot Leg Temperature - Yes No Wide-range Cold Leg Temperature - Yes Yes RCS Cooldown Rate Compared to the Limit Based on RCS - Yes Yes Pressure Wide-range Cold Leg Temperature Compared to the Limit - Yes Yes Based on RCS Pressure Change of RCS Temperature by more than 5°F in the last - No Yes 10 minutes Containment Water Level - Yes Yes Containment Pressure - Yes Yes Pressurizer Water Level - Yes Yes Pressurizer Water Level Trend - Yes No Pressurizer Reference Leg Temperature - Yes No Reactor Vessel-Hot Leg Water Level - Yes Yes Pressurizer Pressure - Yes No Core Exit Temperature - Yes Yes RCS Subcooling - Yes Yes RCS Cold Overpressure Limit - Yes Yes IRWST Water Level - Yes Yes PRHR Flow - Yes Yes PRHR HX Outlet Temperature - Yes Yes PRHR HX Inlet Isolation and Control Valve Status - Yes Yes Note: Dash (-) indicates not applicable.

1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the main control room, the visual alerts are embedded in the safety-related displays as visual signals.

C-295 Amendment No. 160

Table 2.5.4-1 (cont.)

Minimum Inventory of Controls, Displays, and Alerts at the RSW Description Control Display Alert(1)

PRHR HX Outlet Temperature - Yes Yes PRHR HX Inlet Isolation and Control Valve Status - Yes Yes Passive Containment Cooling System (PCS) Storage Tank - Yes No Water Level PCS Cooling Flow - Yes No IRWST to Normal Residual Heat Removal System (RNS) - Yes Yes Suction Valve Status Remotely Operated Containment Isolation Valve Status - Yes No Containment Area High-range Radiation Level - Yes Yes Containment Pressure (Extended Range) - Yes No Core Makeup Tank (CMT) Level - Yes No Manual Reactor Trip (also initiates turbine trip) Yes - -

Manual Safeguards Actuation Yes - -

Manual CMT Actuation Yes - -

Manual Automatic Depressurization System (ADS) Stages 1, Yes - -

2, and 3 Actuation Manual ADS Stage 4 Actuation Yes - -

Manual PRHR Actuation Yes - -

Manual Containment Cooling Actuation Yes - -

Manual IRWST Injection Actuation Yes - -

Manual Containment Recirculation Actuation Yes - -

Manual Containment Isolation Yes - -

Manual Main Steam Line Isolation Yes - -

Manual Feedwater Isolation Yes - -

Manual Containment Hydrogen Igniter (Nonsafety-related)(2) Yes - -

Manual Vacuum Control Relief Yes - -

Note: Dash (-) indicates not applicable.

1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the RSW, the visual alerts are embedded in the nonsafety-related displays as visual signals.

2. Containment hydrogen igniter control is provided as a soft control.

C-311 Amendment No. 160