ML18085A625

Attachment - Vogtle Electric Generating Plant Unit 3 (LAR-17-023)

ML18085A625
Person / Time
Site:	Vogtle
Issue date:	04/20/2018
From:	Paul Kallan NRC/NRO/DNRL/LB4
To:	Whitley B Southern Nuclear Operating Co
kallan p/415-2809
Shared Package
ML18085A620	List: ML18085A621 ML18085A622 ML18085A623 ML18085A624 ML18085A625 ML18085A626 ML18085A627 ML18085A628
References
EPID L-2017-LLA-0093, LAR 17-023
Download: ML18085A625 (12)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 123 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 ii ii 3.3.13-1 3.3.13-1 3.3.13-2 3.3.13-2

--- 3.3.13-3 3.7.4-1 3.7.4-1 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-167 C-167 C-168 C-168 C-173 C-173 C-178 C-178 C-367 C-367

(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. 123, 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. 123

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)

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 3.4 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. 123 (Unit 3)

Amendment No. 122 (Unit 4)

Technical Specifications ESFAS Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization 3.3.13 3.3 INSTRUMENTATION 3.3.13 Engineered Safety Feature Actuation System (ESFAS) Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization LCO 3.3.13 Two channels of each of the following Functions shall be OPERABLE:

a. Main Control Room Air Supply Iodine or Particulate Radiation -

High 2; and

b. Main Control Room Differential Pressure - Low.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies.

ACTIONS

- NOTE -

Separate condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 -----------------------------------

with one channel - NOTE -

inoperable in MODE 1, Not applicable to an 2, 3, or 4. inoperable Main Control Room Differential Pressure - Low channel.

Verify alternate radiation 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> monitors are OPERABLE.

AND VEGP Units 3 and 4 3.3.13 - 1 Amendment No. 123 (Unit 3)

Amendment No. 122 (Unit 4)

Technical Specifications ESFAS Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization 3.3.13 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Verify main control room 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> isolation, air supply initiation, and electrical load de-energization manual controls are OPERABLE.

B. One or more Functions B.1 Restore channel to 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> with one channel OPERABLE status.

inoperable during movement of irradiated fuel assemblies.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time of Condition A not AND met.

C.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> OR One or more Functions with two channels inoperable in MODE 1, 2, 3, or 4.

D. Required Action D.1 Suspend movement of Immediately and associated irradiated fuel assemblies.

Completion Time of Condition B not met.

OR One or more Functions with two channels inoperable during movement of irradiated fuel assemblies.

VEGP Units 3 and 4 3.3.13 - 2 Amendment No. 123 (Unit 3)

Amendment No. 122 (Unit 4)

Technical Specifications ESFAS Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization 3.3.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.13.1 Perform CHANNEL CHECK. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> SR 3.3.13.2 Perform CHANNEL OPERATIONAL TEST (COT) in 92 days accordance with Setpoint Program.

SR 3.3.13.3 -----------------------------------------------------------------------

- 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 3.3.13.4 Verify ESF RESPONSE TIME is within limit. 24 months on a STAGGERED TEST BASIS VEGP Units 3 and 4 3.3.13 - 3 Amendment No. 123 (Unit 3)

Amendment No. 122 (Unit 4)

Technical Specifications Secondary Specific Activity 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Secondary Specific Activity LCO 3.7.4 The specific activity of the secondary coolant shall be < 0.01 Ci/gm DOSE EQUIVALENT I-131.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not A.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> within limit.

AND A.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify the specific activity of the secondary coolant 31 days 0.01 Ci/gm DOSE EQUIVALENT I-131.

VEGP Units 3 and 4 3.7.4 - 1 Amendment No. 123 (Unit 3)

Amendment No. 122 (Unit 4)

2.2.5 Main Control Room Emergency Habitability System Design Description The main control room emergency habitability system (VES) provides a supply of breathable air for the main control room (MCR) occupants and maintains the MCR at a positive pressure with respect to the surrounding areas whenever ac power is not available to operate the nuclear island nonradioactive ventilation system (VBS), MCR differential pressure is not maintained, or high radioactivity is detected in the MCR air supply. (See Section 3.5 for Radiation Monitoring).

The VES also limits the heatup of the MCR, the 1E instrumentation and control (I&C) equipment rooms, and the Class 1E dc equipment rooms by using the heat capacity of surrounding structures.

The VES is as shown in Figure 2.2.5-1 and the component locations of the VES are as shown in Table 2.2.5-6.

1. The functional arrangement of the VES is as described in the Design Description of this Section 2.2.5.

2. a) The components identified in Table 2.2.5-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

b) The piping identified in Table 2.2.5-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3. a) Pressure boundary welds in components identified in Table 2.2.5-1 as ASME Code Section III meet ASME Code Section III requirements.

b) Pressure boundary welds in piping identified in Table 2.2.5-2 as ASME Code Section III meet ASME Code Section III requirements.

4. a) The components identified in Table 2.2.5-1 as ASME Code Section III retain their pressure boundary integrity at their design pressure.

b) The piping identified in Table 2.2.5-2 as ASME Code Section III retains its pressure boundary integrity at its design pressure.

5. a) The seismic Category I equipment identified in Table 2.2.5-1 can withstand seismic design basis loads without loss of safety function.

b) Each of the lines identified in Table 2.2.5-2 for which functional capability is required is designed to withstand combined normal and seismic design basis loads without a loss of its functional capability.

6. a) The Class 1E components identified in Table 2.2.5-1 are powered from their respective Class 1E division.

b) Separation is provided between VES Class 1E divisions, and between Class 1E divisions and non-Class 1E cable.

7. The VES provides the following safety-related functions:

a) The VES provides a 72-hour supply of breathable quality air for the occupants of the MCR.

C-167 Amendment No. 123

b) The VES maintains the MCR pressure boundary at a positive pressure with respect to the surrounding areas. There is a discharge of air through the MCR vestibule.

c) The heat loads within the MCR, the I&C equipment rooms, and the Class 1E dc equipment rooms are within design basis assumptions to limit the heatup of the rooms identified in Table 2.2.5-4.

d) The system provides a passive recirculation flow of MCR air to maintain main control room dose rates below an acceptable level during VES operation.

e) The system provides shielding below the VES filter that is sufficient to ensure main control room doses are below an acceptable level during VES operation.

8. Safety-related displays identified in Table 2.2.5-1 can be retrieved in the MCR.

9. a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.5-1 to perform their active functions.

b) The valves identified in Table 2.2.5-1 as having protection and safety monitoring system (PMS) control perform their active safety function after receiving a signal from the PMS.

c) The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS.

10. After loss of motive power, the remotely operated valves identified in Table 2.2.5-1 assume the indicated loss of motive power position.

11. Displays of the parameters identified in Table 2.2.5-3 can be retrieved in the MCR.

12. The background noise level in the MCR does not exceed 65 dB(A) at the operator workstations when the VES is operating.

C-168 Amendment No. 123

Table 2.2.5-1 (cont.)

ASME Class 1E/ Loss of Code Remotely Qual. for Safety- Motive Section Seismic Operated Harsh Related Control Active Power Equipment Name Tag No. III Cat. I Valve Envir. Display PMS Function Position MCR Air Filtration Line VES-PY-N01 Yes Yes - - - - - -

Eductor MCR Air Filtration Line VES-MY-F01 No Yes - - - - - -

Charcoal Filter MCR Air Filtration Line VES-MY-F02 No Yes - - - - - -

HEPA Filter MCR Air Filtration Line VES-MY-F03 No Yes - - - - - -

Postfilter MCR Filter Shielding 12401-NS-01 No Yes - - - - - -

MCR Gravity Relief VES-MD- No Yes - - - - - -

Dampers D001A MCR Gravity Relief VES-MD- No Yes - - - - - -

Dampers D001B MCR Air Filtration Line VES-MD-D002 No Yes - - - - - -

Supply Damper MCR Air Filtration Line VES-MD-D003 No Yes - - - - - -

Supply Damper MCR Air Filtration Line VES-MY-Y01 No Yes - - - - - -

Silencer MCR Air Filtration Line VES-MY-Y02 No Yes - - - - - -

Silencer MCR Air Delivery Line VES-003A No Yes - Yes/No Yes - - -

Flow Sensor MCR Air Delivery Line VES-003B No Yes - Yes/No Yes - - -

Flow Sensor C-173 Amendment No. 123

Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 270 2.2.05.07c 7.c) The heat loads within the MCR, An analysis will be performed to A report exists and concludes the I&C equipment rooms, and the determine that the heat loads that: the heat loads within Class 1E dc equipment rooms are from as-built equipment within rooms identified in Table within design basis assumptions to limit the rooms identified in 2.2.5-4 are less than or equal the heatup of the rooms identified in Table 2.2.5-4 are less than or to the specified values or that Table 2.2.5-4. equal to the design basis an analysis report exists that assumptions. concludes:

- The temperature and humidity in the MCR remain within limits for reliable human performance for the 72-hour period.

- The maximum temperature for the 72-hour period for the I&C rooms is less than or equal to 120°F.

- The maximum temperature for the 72-hour period for the Class 1E dc equipment rooms is less than or equal to 120°F.

271 2.2.05.07d Not used per Amendment No. 113 880 2.2.05.07e 7e) Shielding below the VES filter is Inspection will be performed for A report exists and concludes capable of providing attenuation that is the existence of a report that the as-built shielding sufficient to ensure main control room verifying that the as-built identified in Table 2.2.5-1 doses are below an acceptable level shielding meets the requirements meets the functional during VES operation. for functional capability. requirements and exists below the filtration unit, and within its vertical projection.

272 2.2.05.08 Not used per Amendment No. 113 273 2.2.05.09a Not used per Amendment No. 113 274 2.2.05.09b Not used per Amendment No. 113 877 2.2.05.09c 9.c) The MCR Load Shed Panels Testing will be performed on the The MCR Load Shed Panels identified in Table 2.2.5-1 perform their MCR Load Shed Panels listed in identified in Table 2.2.5-1 active safety function after receiving a Table 2.2.5-1 using real or perform their active safety signal from the PMS. simulated signals into the PMS. function identified in the table after receiving a signal from the PMS.

C-178 Amendment No. 123

2.7 HVAC Systems 2.7.1 Nuclear Island Nonradioactive Ventilation System Design Description The nuclear island nonradioactive ventilation system (VBS) serves the main control room (MCR), control support area (CSA), Class 1E dc equipment rooms, Class 1E instrumentation and control (I&C) rooms, Class 1E electrical penetration rooms, Class 1E battery rooms, remote shutdown room (RSR), reactor coolant pump trip switchgear rooms, adjacent corridors, and passive containment cooling system (PCS) valve room during normal plant operation. The VBS consists of the following independent subsystems: the main control room/control support area HVAC subsystem, the class 1E electrical room HVAC subsystem, and the passive containment cooling system valve room heating and ventilation subsystem. The VBS provides heating, ventilation, and cooling to the areas served when ac power is available. The system provides breathable air to the control room and maintains the main control room and control support area areas at a slightly positive pressure with respect to the adjacent rooms and outside environment during normal operations. The VBS monitors the main control room supply air for radioactive particulate and iodine concentrations and provides filtration of main control room/control support area air during conditions of abnormal High-1 airborne radioactivity. In addition, the VBS isolates the HVAC penetrations in the main control room boundary on High-2 particulate or iodine radioactivity in the main control room supply air duct or on a loss of ac power for more than 10 minutes or if main control room differential pressure is below the Low setpoint for more than 10 minutes. The Sanitary Drainage System (SDS) also isolates a penetration in the main control room boundary on High-2 particulate or iodine radioactivity in the main control room supply air duct or on a loss of ac power for more than 10 minutes or if main control room differential pressure is below the Low setpoint for more than 10 minutes. Additional penetrations from the SDS and Potable Water System (PWS) into the main control room boundary are maintained leak tight using a loop seal in the piping, and the Waste Water System (WWS) is isolated using a normally closed safety related manual isolation valve. These features support operation of the main control room emergency habitability system (VES), and have been included in Tables 2.7.1-1 and 2.7.1-2.

The VBS is as shown in Figure 2.7.1-1 and the component locations of the VBS are as shown in Table 2.7.1-5.

1. The functional arrangement of the VBS is as described in the Design Description of this subsection 2.7.1.

2. a) The components identified in Table 2.7.1-1 as ASME Code Section III are designed and constructed in accordance with ASME Code Section III requirements.

b) The piping identified in Table 2.7.1-2 as ASME Code Section III is designed and constructed in accordance with ASME Code Section III requirements.

3. a) Pressure boundary welds in components identified in Table 2.7.1-1 as ASME Code Section III meet ASME Code Section III requirements.

b) Pressure boundary welds in piping identified in Table 2.7.1-2 as ASME Code Section III meet ASME Code Section III requirements.

C-367 Amendment No. 123