ML18351A194

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Attachment - Vogtle Electric Generating Plant Unit 4 LAR 18-017
ML18351A194
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 01/15/2019
From: Jordan Hoellman
NRC/NRO/DLSE/LB4
To:
Southern Nuclear Operating Co
hoellman j/415-5481
Shared Package
ML18351A189 List:
References
EPID L-2018-LLA-0206, LAR 18-017
Download: ML18351A194 (13)
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Text

ATTACHMENT TO LICENSE AMENDMENT NO. 149 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 A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT ii ii iii iii 3.3.14-1 3.3.14-1 3.3.14-2 3.3.14-2

--- 3.3.14-3

--- 3.3.14-4 3.3.16-4 3.3.16-4 3.5.7-3 3.5.7-3 3.5.8-3 3.5.8-3

--- 3.7.13-1

--- 3.7.13-2

(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. 149, 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. 149

Technical Specifications TABLE OF CONTENTS Page 3.3 INSTRUMENTATION (continued) 3.3.8 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation ..................................................................................... 3.3.8 - 1 3.3.9 Engineered Safety Feature Actuation System (ESFAS)

Manual Initiation ................................................................................... 3.3.9 - 1 3.3.10 Engineered Safety Feature Actuation System (ESFAS)

Reactor Coolant System (RCS) Hot Leg Level Instrumentation ......... 3.3.10 - 1 3.3.11 Engineered Safety Feature Actuation System (ESFAS)

Startup Feedwater Flow Instrumentation ............................................ 3.3.11 - 1 3.3.12 Engineered Safety Feature Actuation System (ESFAS)

Reactor Trip Initiation.......................................................................... 3.3.12 - 1 3.3.13 Engineered Safety Feature Actuation System (ESFAS)

Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization.......................................................... 3.3.13 - 1 3.3.14 Engineered Safety Feature Actuation System (ESFAS)

In-containment Refueling Water Storage Tank (IRWST) and Spent Fuel Pool Level Instrumentation ........................................ 3.3.14 - 1 3.3.15 Engineered Safety Feature Actuation System (ESFAS)

Actuation Logic - Operating ............................................................... 3.3.15 - 1 3.3.16 Engineered Safety Feature Actuation System (ESFAS)

Actuation Logic - Shutdown ............................................................... 3.3.16 - 1 3.3.17 Post Accident Monitoring (PAM) Instrumentation ..................................... 3.3.17 - 1 3.3.18 Remote Shutdown Workstation (RSW) .................................................... 3.3.18 - 1 3.3.19 Diverse Actuation System (DAS) Manual Controls.................................. 3.3.19 - 1 3.3.20 Automatic Depressurization System (ADS) and In-containment Refueling Water Storage Tank (IRWST) Injection Blocking Device ... 3.3.20 - 1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits .............................................................. 3.4.1 - 1 3.4.2 RCS Minimum Temperature for Criticality .................................................. 3.4.2 - 1 3.4.3 RCS Pressure and Temperature (P/T) Limits ............................................. 3.4.3 - 1 3.4.4 RCS Loops ................................................................................................. 3.4.4 - 1 3.4.5 Pressurizer ................................................................................................. 3.4.5 - 1 3.4.6 Pressurizer Safety Valves........................................................................... 3.4.6 - 1 3.4.7 RCS Operational LEAKAGE....................................................................... 3.4.7 - 1 3.4.8 Minimum RCS Flow .................................................................................... 3.4.8 - 1 3.4.9 RCS Leakage Detection Instrumentation ................................................... 3.4.9 - 1 3.4.10 RCS Specific Activity ................................................................................ 3.4.10 - 1 3.4.11 Automatic Depressurization System (ADS) - Operating .......................... 3.4.11 - 1 3.4.12 Automatic Depressurization System (ADS) - Shutdown, RCS Intact ...... 3.4.12 - 1 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Open ...... 3.4.13 - 1 3.4.14 Low Temperature Overpressure Protection (LTOP) ................................. 3.4.14 - 1 3.4.15 RCS Pressure Isolation Valve (PIV) Integrity ........................................... 3.4.15 - 1 3.4.16 Reactor Vessel Head Vent (RVHV) .......................................................... 3.4.16 - 1 3.4.17 Steam Generator (SG) Tube Integrity ....................................................... 3.4.17 - 1 VEGP Units 3 and 4 ii Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications TABLE OF CONTENTS Page 3.5 PASSIVE CORE COOLING SYSTEM (PXS) 3.5.1 Accumulators .............................................................................................. 3.5.1 - 1 3.5.2 Core Makeup Tanks (CMTs) - Operating ................................................... 3.5.2 - 1 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact ................................ 3.5.3 - 1 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) -

Operating .............................................................................................. 3.5.4 - 1 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) -

Shutdown, Reactor Coolant System (RCS) Intact ................................ 3.5.5 - 1 3.5.6 In-containment Refueling Water Storage Tank (IRWST) -

Operating .............................................................................................. 3.5.6 - 1 3.5.7 In-containment Refueling Water Storage Tank (IRWST) -

Shutdown, MODE 5 .............................................................................. 3.5.7 - 1 3.5.8 In-containment Refueling Water Storage Tank (IRWST) -

Shutdown, MODE 6 .............................................................................. 3.5.8 - 1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment ............................................................................................... 3.6.1 - 1 3.6.2 Containment Air Locks................................................................................ 3.6.2 - 1 3.6.3 Containment Isolation Valves ..................................................................... 3.6.3 - 1 3.6.4 Containment Pressure ................................................................................ 3.6.4 - 1 3.6.5 Containment Air Temperature ..................................................................... 3.6.5 - 1 3.6.6 Passive Containment Cooling System (PCS)............................................. 3.6.6 - 1 3.6.7 Containment Penetrations .......................................................................... 3.6.7 - 1 3.6.8 pH Adjustment ............................................................................................ 3.6.8 - 1 3.6.9 Vacuum Relief Valves ................................................................................. 3.6.9 - 1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) .......................................................... 3.7.1 - 1 3.7.2 Main Steam Line Flow Path Isolation Valves .............................................. 3.7.2 - 1 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Control Valves (MFCVs) ....................................................................... 3.7.3 - 1 3.7.4 Secondary Specific Activity ......................................................................... 3.7.4 - 1 3.7.5 Spent Fuel Pool Water Level ...................................................................... 3.7.5 - 1 3.7.6 Main Control Room Habitability System (VES) .......................................... 3.7.6 - 1 3.7.7 Startup Feedwater Isolation and Control Valves ......................................... 3.7.7 - 1 3.7.8 Main Steam Line Leakage .......................................................................... 3.7.8 - 1 3.7.9 Spent Fuel Pool Makeup Water Sources .................................................... 3.7.9 - 1 3.7.10 Steam Generator (SG) Isolation Valves.................................................... 3.7.10 - 1 3.7.11 Spent Fuel Pool Boron Concentration ...................................................... 3.7.11 - 1 3.7.12 Spent Fuel Pool Storage .......................................................................... 3.7.12 - 1 3.7.13 Spent Fuel Pool Cooling System (SFS)

Containment Isolation Valves ............................................................. 3.7.13 - 1 VEGP Units 3 and 4 iii Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 3.3 INSTRUMENTATION 3.3.14 Engineered Safety Feature Actuation System (ESFAS) In-containment Refueling Water Storage Tank (IRWST) and Spent Fuel Pool Level Instrumentation LCO 3.3.14 The ESFAS IRWST and Spent Fuel Pool Level instrumentation channels for each Function in Table 3.3.14-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.14-1.

ACTIONS

- NOTE -

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One Spent Fuel Pool A.1 Place channel in trip. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Level - Low 2 channel inoperable.

VEGP Units 3 and 4 3.3.14 - 1 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action -----------------------------------------------

and associated - NOTE -

Completion Time of Penetration flow path(s) may be Condition A not met. unisolated intermittently under administrative controls.

OR One or more IRWST B.1 Isolate affected penetration 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> Wide Range Level - flow paths.

Low channels AND inoperable.

OR B.2.1 Isolate affected penetration 7 days flow paths by use of at Two or more Spent Fuel least one closed and Pool Level - Low 2 deactivated automatic channels inoperable. valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

OR B.2.2 Verify affected penetration Once per 7 days flow paths are isolated.

C. Required Action and C.1 Declare the IRWST Immediately associated Completion inoperable.

Time of Condition B not met.

VEGP Units 3 and 4 3.3.14 - 2 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.14.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.14.2 Perform CHANNEL OPERATIONAL TEST (COT) in 92 days accordance with Setpoint Program.

SR 3.3.14.3 -----------------------------------------------------------------------

- NOTE -

This surveillance shall include verification that the time constants are adjusted to within limits.

Perform CHANNEL CALIBRATION in accordance 24 months with Setpoint Program.

SR 3.3.14.4 Verify ESF RESPONSE TIME is within limit. 24 months on a STAGGERED TEST BASIS VEGP Units 3 and 4 3.3.14 - 3 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 Table 3.3.14-1 (page 1 of 1)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS

1. Spent Fuel Pool Level - Low 2 6(a) 3
2. IRWST Wide Range Level - Low 1,2,3,4 2 (a) With refueling cavity and spent fuel pool volumes in communication.

VEGP Units 3 and 4 3.3.14 - 4 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications ESFAS Actuation Logic

- Shutdown 3.3.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.16.4 -----------------------------------------------------------------------

- NOTES -

1. Not required to be met in MODE 5 above the P-12 (Pressurizer Level) interlock.
2. Not required to be met in MODE 6 with water level > 23 feet above the top of the reactor vessel flange.

Verify CVS letdown isolation valves actuate to the 24 months isolation position on an actual or simulated actuation signal.

VEGP Units 3 and 4 3.3.16 - 4 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications IRWST - Shutdown, MODE 5 3.5.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.7.1 -----------------------------------------------------------------------

- NOTE -

Penetration flow path(s) may be unisolated intermittently under administrative controls.

Verify Spent Fuel Pool Cooling System containment 31 days isolation valves are closed.

SR 3.5.7.2 For the IRWST and flow paths required to be In accordance with OPERABLE, the following SRs are applicable: applicable SRs SR 3.5.6.1 SR 3.5.6.2 SR 3.5.6.4 SR 3.5.6.5 SR 3.5.6.6 SR 3.5.6.7 SR 3.5.6.8 SR 3.5.6.9 SR 3.5.6.10 SR 3.5.6.11 SR 3.5.7.3 -----------------------------------------------------------------------

- NOTE -

Not required to be met during RCS vacuum fill operations.

For the IRWST and flow paths required to be In accordance with OPERABLE, the following SR is applicable: applicable SR SR 3.5.6.3 VEGP Units 3 and 4 3.5.7 - 3 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications IRWST - Shutdown, MODE 6 3.5.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.8.3 -----------------------------------------------------------------------

- NOTES -

1. Penetration flow path(s) may be unisolated intermittently under administrative controls.
2. Only required to be met with refueling cavity and spent fuel pool volumes not in communication.

Verify Spent Fuel Pool Cooling System containment 31 days isolation valves are closed.

SR 3.5.8.4 Verify the IRWST and refueling cavity boron 31 days concentration is 2600 ppm and 2900 ppm.

AND Once within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> after each solution volume increase of 15,000 gal SR 3.5.8.5 For the IRWST and flow paths required to be In accordance with OPERABLE, the following SRs are applicable: applicable SRs SR 3.5.6.3 SR 3.5.6.6 SR 3.5.6.8 SR 3.5.6.10 SR 3.5.6.5 SR 3.5.6.7 SR 3.5.6.9 SR 3.5.6.11 VEGP Units 3 and 4 3.5.8 - 3 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications SFS Containment Isolation Valves 3.7.13 3.7 PLANT SYSTEMS 3.7.13 Spent Fuel Pool Cooling System (SFS) Containment Isolation Valves LCO 3.7.13 The SFS containment isolation valves shall be OPERABLE.

APPLICABILITY: MODE 6 with refueling cavity and spent fuel pool volumes in communication.

ACTIONS

- NOTES -

1. Penetration flow path(s) may be unisolated intermittently under administrative controls.
2. Separate Condition entry is allowed for each SFS penetration flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Isolate affected penetration 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> penetration flow paths flow path.

with one or more SFS containment isolation AND valves inoperable.

A.2.1 Isolate affected penetration 7 days flow path by use of at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

OR A.2.2 Verify affected penetration Once per 7 days flow path is isolated.

B. Required Action B.1 Declare the In-containment Immediately and associated Refueling Water Storage Completion Time not Tank inoperable.

met.

VEGP Units 3 and 4 3.7.13 - 1 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

Technical Specifications SFS Containment Isolation Valves 3.7.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 For SFS containment isolation valves required to be In accordance with OPERABLE, the following SRs are applicable: applicable SRs SR 3.6.3.4 SR 3.6.3.5 VEGP Units 3 and 4 3.7.13 - 2 Amendment No. 150 (Unit 3)

Amendment No. 149 (Unit 4)

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