ML18351A194
| ML18351A194 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| 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) | |
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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 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)
- 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 VEGP Units 3 and 4 ii Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
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
Technical Specifications VEGP Units 3 and 4 iii Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
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
Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 VEGP Units 3 and 4 3.3.14 - 1 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4) 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 Level - Low 2 channel inoperable.
A.1 Place channel in trip.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 VEGP Units 3 and 4 3.3.14 - 2 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
Required Action and associated Completion Time of Condition A not met.
OR One or more IRWST Wide Range Level -
Low channels inoperable.
- NOTE -
Penetration flow path(s) may be unisolated intermittently under administrative controls.
B.1 AND Isolate affected penetration flow paths.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR Two or more Spent Fuel Pool Level - Low 2 channels inoperable.
B.2.1 Isolate affected penetration flow paths 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.
7 days OR B.2.2 Verify affected penetration flow paths are isolated.
Once per 7 days C.
Required Action and associated Completion Time of Condition B not met.
C.1 Declare the IRWST inoperable.
Immediately
Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 VEGP Units 3 and 4 3.3.14 - 3 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.14.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.14.2 Perform CHANNEL OPERATIONAL TEST (COT) in accordance with Setpoint Program.
92 days 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 with Setpoint Program.
24 months SR 3.3.14.4 Verify ESF RESPONSE TIME is within limit.
24 months on a STAGGERED TEST BASIS
Technical Specifications ESFAS IRWST and Spent Fuel Pool Level Instrumentation 3.3.14 VEGP Units 3 and 4 3.3.14 - 4 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
Table 3.3.14-1 (page 1 of 1)
Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED 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.
Technical Specifications ESFAS Actuation Logic
- Shutdown 3.3.16 VEGP Units 3 and 4 3.3.16 - 4 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
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 isolation position on an actual or simulated actuation signal.
24 months
Technical Specifications IRWST - Shutdown, MODE 5 3.5.7 VEGP Units 3 and 4 3.5.7 - 3 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
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 isolation valves are closed.
31 days SR 3.5.7.2 For the IRWST and flow paths required to be OPERABLE, the following SRs are applicable:
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 In accordance with applicable SRs 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 OPERABLE, the following SR is applicable:
SR 3.5.6.3 In accordance with applicable SR
Technical Specifications IRWST - Shutdown, MODE 6 3.5.8 VEGP Units 3 and 4 3.5.8 - 3 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
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 isolation valves are closed.
31 days SR 3.5.8.4 Verify the IRWST and refueling cavity boron concentration is 2600 ppm and 2900 ppm.
31 days AND Once within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 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 OPERABLE, the following SRs are applicable:
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 In accordance with applicable SRs
Technical Specifications SFS Containment Isolation Valves 3.7.13 VEGP Units 3 and 4 3.7.13 - 1 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4) 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 penetration flow paths with one or more SFS containment isolation valves inoperable.
A.1 Isolate affected penetration flow path.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND A.2.1 Isolate affected penetration 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.
7 days OR A.2.2 Verify affected penetration flow path is isolated.
Once per 7 days B.
Required Action and associated Completion Time not met.
B.1 Declare the In-containment Refueling Water Storage Tank inoperable.
Immediately
Technical Specifications SFS Containment Isolation Valves 3.7.13 VEGP Units 3 and 4 3.7.13 - 2 Amendment No. 150 (Unit 3)
Amendment No. 149 (Unit 4)
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 For SFS containment isolation valves required to be OPERABLE, the following SRs are applicable:
SR 3.6.3.4 SR 3.6.3.5 In accordance with applicable SRs