ML19063C641

Attachment - VEGP U4 Amendment 156 (LAR-18-027)

ML19063C641
Person / Time
Site:	Vogtle
Issue date:	04/11/2019
From:	Office of New Reactors
To:	Southern Nuclear Operating Co
References
EPID L-2018-LLA-0311
Download: ML19063C641 (16)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 156 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 3.4.12-2 3.4.12-2 3.7.1-2 3.7.1-2 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-40 C-40 C-101 C-101 C-240 C-240 C-249a C-249a C-259 C-259 C-292 C-292 C-326 C-326 C-334 C-334 C-340 C-340 C-356 C-356 C-371 C-371 C-421 C-421

(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. 156, 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. 156

Technical Specifications ADS - Shutdown, RCS Intact 3.4.12 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action D.1 Initiate action to open the Immediately and associated RCS pressure boundary.

Completion Time of Condition A, B, or C not met.

OR Condition A and Condition B entered concurrently.

OR Three or more required flow paths in ADS stage 1, 2, and 3 inoperable.

OR LCO not met for reasons other than Condition A, B, or C.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 For flow paths required to be OPERABLE, the SRs of In accordance with LCO 3.4.11, Automatic Depressurization System applicable SRs (ADS) - Operating are applicable.

VEGP Units 3 and 4 3.4.12 - 2 Amendment No. 158 (Unit 3)

Amendment No. 156 (Unit 4)

Technical Specifications MSSVs 3.7.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ------------------------------------

- NOTE -

Only required in MODE 1.

Reduce the Overpower T 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> reactor trip setpoints to less than or equal to the Maximum Allowable %

RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.

B. One or both steam B.1 Restore MSSV to 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> generators with one or OPERABLE status.

more MSSVs inoperable for closing.

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

C.2 Be in MODE 4 with the 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> OR RCS cooling provided by the RNS.

One or both steam generators with 5 MSSVs inoperable for opening.

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

D.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> VEGP Units 3 and 4 3.7.1 - 2 Amendment No. 158 (Unit 3)

Amendment No. 156 (Unit 4)

1.4 List of Acronyms and Abbreviations The acronyms presented in this section are provided for information.

ac Alternating Current AC Acceptance Criteria ADS Automatic Depressurization System AHU Air Handling Units ANS Alert and Notification System ASME American Society of Mechanical Engineers atm Atmoshpere BTU British Thermal Unit CAS Compressed and Instrument Air System CAV Cumulative Absolute Velocity cc Cubic Centimeter CCS Component Cooling Water System CDE Committed Dose Equivalent CDS Condensate System cfm Cubic Feet per Minute CFR Code of Federal Regulations Ci Curie CIM Component Interface Module CMT Core Makeup Tank CNS Containment System COL Combined License CRDM Control Rod Drive Mechanism CSA Control Support Area CST Condensate Storage Tank CVS Chemical and Volume Control System CWS Circulating Water System DAS Diverse Actuation System DBT Design Basis Threat dc Direct Current DCD Design Control Document DDS Data Display and Processing System DOS Standby Diesel Fuel Oil System D-RAP Design Reliability Assurance Program DTS Demineralized Water Treatment System DVI Direct Vessel Injection DWS Demineralized Water Transfer and Storage System EAL Emergency Action Level ECS Main ac Power System EDS Non-Class 1E dc and Uninterruptible Power Supply System EFS Communication System EGS Grounding and Lightning Protection System C-40 Amendment No. 156

Figure 2.2.1-1 Containment System C-101 Amendment No. 156

Figure 2.3.7-1 Spent Fuel Pool Cooling System C-240 Amendment No. 156

Table 2.3.9-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 427 2.3.09.04a Not used per Amendment No. 112 428 2.3.09.04b 4.b) The components identified in Testing will be performed on the The igniters energize after Table 2.3.9-2 perform the listed igniters using the DAS controls. receiving a signal from DAS.

function after receiving a manual signal from DAS.

429 2.3.09.05 Not used per Amendment No. 112 2.3.10 Liquid Radwaste System Design Description The liquid radwaste system (WLS) receives, stores, processes, samples and monitors the discharge of radioactive wastewater.

C-249a Amendment No. 156

Table 2.3.11-2 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 450 2.3.11.02.i 2. The equipment identified as having i) Inspection will be performed i) The equipment identified as seismic design requirements in to verify that the equipment having seismic design Table 2.3.11-1 can withstand seismic identified as having seismic requirements in Table 2.3.11-1 design basis loads without loss of its design requirements in is located on the Nuclear structural integrity function. Table 2.3.11-1 is located on the Island.

Nuclear Island.

ii) Type tests, analyses, or a ii) A report exists and combination of type tests and concludes that the seismically analyses of seismically designed designed equipment can equipment will be performed. withstand appropriate seismic design basis loads without loss of its structural integrity function.

iii) Inspection will be performed iii) A report exists and for the existence of a report concludes that the as-built verifying that the as-built equipment including equipment including anchorage anchorage is seismically is seismically bounded by the bounded by the tested or tested or analyzed conditions. analyzed conditions.

451 2.3.11.02.ii Not used per Amendment No. 84 452 2.3.11.02.iii Not used per Amendment No. 84 453 2.3.11.03a 3.a) The WGS provides the nonsafety- Inspection will be performed to A report exists and concludes related function of processing verify the contained volume of that the contained volume in radioactive gases prior to discharge. each of the activated carbon each of the activated carbon delay beds, WGS-MV-02A and delay beds, WGS-MV-02A WGS-MV-02B. and WGS-MV-02B, is at least 80 ft3.

454 2.3.11.03b 3.b) The WGS provides the nonsafety- Tests will be performed to A simulated high radiation related function of controlling the confirm that the presence of a signal causes the discharge releases of radioactive materials in simulated high radiation signal control isolation valve gaseous effluents. from the discharge radiation WGS-PL-V051 to close.

monitor, WGS-017, causes the discharge control isolation valve WGS-PL-V051 to close.

455 2.3.11.03c 3.c) The WGS is purged with nitrogen Tests will be performed to A simulated high oxygen level on indication of high oxygen levels in confirm that the presence of a signal causes the nitrogen the system. simulated high oxygen level purge valve (WGS-PL-V002) signal from the oxygen monitors to open and the WLS (WGS-025A, -025B) causes degasifier vacuum pumps the nitrogen purge valve (WLS-MP-03A, -03B) to stop.

(WGS-PL-V002) to open and the WLS degasifier vacuum pumps (WLS-MP-03A, -03B) to stop.

C-259 Amendment No. 156

b) The PMS two-out-of-four initiation logic reverts to a two-out-of-three coincidence logic if one of the four channels is bypassed. All bypassed channels are alarmed in the MCR.

c) The PMS does not allow simultaneous bypass of two redundant channels.

d) The PMS provides the interlock functions identified in Table 2.5.2-7.

10. Setpoints are determined using a methodology which accounts for loop inaccuracies, response testing, and maintenance or replacement of instrumentation.

11. The PMS hardware and software is developed using a planned design process which provides for specific design documentation and reviews during the following life cycle stages:

a) Design requirements phase, may be referred to as conceptual or project definition phase (Complete) b) System definition phase c) Hardware and software development phase, consisting of hardware and software design and implementation d) System integration and test phase e) Installation phase

12. The PMS software is designed, tested, installed, and maintained using a process which incorporates a graded approach according to the relative importance of the software to safety and specifies requirements for:

a) Software management including documentation requirements, standards, review requirements, and procedures for problem reporting and corrective action.

b) Software configuration management including historical records of software and control of software changes.

c) Verification and validation including requirements for reviewer independence.

13. The use of commercial grade hardware and software items in the PMS is accomplished through a process that specifies requirements for:

a) Review of supplier design control, configuration management, problem reporting, and change control.

b) Review of product performance.

c) Receipt acceptance of the commercial grade item.

d) Final acceptance based on equipment qualification and software validation in the integrated system.

14. The Component Interface Module (CIM) is developed using a planned design process which provides for specific design documentation and reviews.

C-292 Amendment No. 156

Figure 2.6.1-1 (Sheet 1 of 4)

Main ac Power System C-326 Amendment No. 156

2.6.3 Class 1E dc and Uninterruptible Power Supply System Design Description The Class 1E dc and uninterruptible power supply system (IDS) provides dc and uninterruptible ac electrical power for safety-related equipment during normal and off-normal conditions.

The IDS is as shown in Figure 2.6.3-1 and the component locations of the IDS are as shown in Table 2.6.3-4.

1. The functional arrangement of the IDS is as described in the Design Description of this Section 2.6.3.

2. The seismic Category I equipment identified in Table 2.6.3-1 can withstand seismic design basis loads without loss of safety function.

3. Separation is provided between Class 1E divisions, and between Class 1E divisions and non-Class 1E cables.

4. The IDS provides the following safety-related functions:

a) The IDS provides electrical independence between the Class 1E divisions.

b) The IDS provides electrical isolation between iself and the non-Class 1E ac power system and the non-Class 1E lighting in the MCR.

c) Each IDS 24-hour battery bank supplies a dc switchboard bus load for a period of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> without recharging.

d) Each IDS 72-hour battery bank supplies a dc switchboard bus load for a period of 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> without recharging.

e) The IDS spare battery bank supplies a dc load equal to or greater than the most severe switchboard bus load for the required period without recharging.

f) Each IDS 24-hour inverter supplies its ac load.

g) Each IDS 72-hour inverter supplies its ac load.

h) Each IDS 24-hour battery charger provides the protection and safety monitoring system (PMS) with two loss-of-ac input voltage signals.

i) The IDS supplies an operating voltage at the terminals of the Class 1E motor-operated valves identified in subsections 2.1.2, 2.2.1, 2.2.2, 2.2.3, 2.2.4, 2.3.2, 2.3.6, and 2.7.1 that is greater than or equal to the minimum design voltage.

j) The IDS provides electrical isolation between the non-Class 1E battery monitors and the Class 1E battery banks

5. The IDS provides the following nonsafety-related functions:

a) Each IDS 24-hour battery charger supplies a dc switchboard bus load while maintaining the corresponding battery charged.

b) Each IDS 72-hour battery charger supplies a dc switchboard bus load while maintaining the corresponding battery charged.

c) Each IDS regulating transformer supplies an ac load when powered from the 480 V motor control center (MCC).

C-334 Amendment No. 156

Table 2.6.3-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 599 2.6.03.02.iii Not used per Amendment No. 84 600 2.6.03.03 Not used per Amendment No. 84 601 2.6.03.04a 4.a) The IDS provides electrical Testing will be performed on the A simulated test signal exists independence between the Class 1E IDS by providing a simulated at the Class 1E equipment divisions. test signal in each Class 1E identified in Table 2.6.3-1 division. when the assigned Class 1E division is provided the test signal.

602 2.6.03.04b 4.b) The IDS provides electrical Type tests, analyses, or a A report exists and concludes isolation between itself and the non- combination of type tests and that the battery chargers, Class 1E ac power system and the analyses of the isolation devices regulating transformers, and non-Class 1E lighting in the MCR. will be performed. isolation fuses prevent credible faults from propagating into the IDS.

603 2.6.03.04c 4.c) Each IDS 24-hour battery bank Testing of each 24-hour as-built The battery terminal voltage is supplies a dc switchboard bus load for a battery bank will be performed greater than or equal to 210 V period of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> without recharging. by applying a simulated or real after a period of no less than load, or a combination of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> with an equivalent simulated or real loads which load that equals or exceeds the envelope the battery bank design battery bank design duty cycle duty cycle. The test will be capacity.

conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> prior to the test.

4.d) Each IDS 72-hour battery bank Testing of each 72-hour as-built The battery terminal voltage is supplies a dc switchboard bus load for a battery bank will be performed greater than or equal to 210 V period of 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> without recharging. by applying a simulated or real after a period of no less than load, or a combination of 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> with an equivalent simulated or real loads which load that equals or exceeds the envelope the battery bank design battery bank design duty cycle duty cycle. The test will be capacity.

conducted on a battery bank that has been fully charged and has been connected to a battery charger maintained at 270+/-2 V for a period of no less than 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> prior to the test.

C-340 Amendment No. 156

Table 2.6.6-1 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 637 2.6.06.01.i 1. The EGS provides an electrical i) An inspection for the i) A connection exists grounding system for: instrument/computer grounding between the (1) instrument/computer grounding; system connection to the station instrument/computer (2) electrical system grounding of the grounding grid will be grounding system and the neutral points of the main generator, performed. station grounding grid.

main step-up transformers, auxiliary transformers, load center transformers, and onsite standby diesel generators; and (3) equipment grounding of equipment enclosures, metal structures, metallic tanks, ground bus of switchgear assemblies, load centers, motor control centers, and control cabinets. Lightning protection is provided for exposed structures and buildings housing safety-related and fire protection equipment. Each grounding system and lightning protection system is grounded to the station grounding grid.

ii) An inspection for the ii) A connection exists electrical system grounding between the electrical system connection to the station grounding and the station grounding grid will be grounding grid.

performed.

iii) An inspection for the iii) A connection exists equipment grounding system between the equipment connection to the station grounding system and the grounding grid will be station grounding grid.

performed.

iv) An inspection for the iv) A connection exists lightning protection system between the lightning connection to the station protection system and the grounding grid will be station grounding grid.

performed.

638 2.6.06.01.ii Not used per Amendment No. 112 C-356 Amendment No. 156

Table 2.7.1-3 Equipment Tag No. Display Control Function Division "B" and "D" Class 1E VBS-MA-05D Yes Start Electrical Room AHU D Fans VBS-MA-06D (Run Status)

Division "A" and "C" Class 1E VBS-MA-07A Yes Start Battery Room Exhaust Fans VBS-MA-07C (Run Status)

Division "B" and "D" Class 1E VBS-MA-07B Yes Start Battery Room Exhaust Fans VBS-MA-07D (Run Status)

MCR Ancillary Fans VBS-MA-10A No -

VBS-MA-10B Division B Room Ancillary Fan VBS-MA-11 No -

Division C Room Ancillary Fan VBS-MA-12 No -

Table 2.7.1-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 677 2.7.01.01 1. The functional arrangement of the Inspection of the as-built system The as-built VBS conforms VBS is as described in the Design will be performed. with the functional Description of this subsection 2.7.1 arrangement described in the Design Description of this subsection 2.7.1.

678 2.7.01.02a 2.a) The components identified in Inspection will be conducted of The ASME Code Section III Table 2.7.1-1 as ASME Code the as-built components and design reports exist for the Section III are designed and constructed piping as documented in the as-built components and in accordance with ASME Code ASME design reports. piping identified in Section III requirements. Tables 2.7.1-1 and 2.7.1-2 as 2.b) The piping identified in Table ASME Code Section III.

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 Inspection of the as-built A report exists and concludes components identified in Table 2.7.1-1 pressure boundary welds will be that the ASME Code Section as ASME Code Section III meet ASME performed in accordance with III requirements are met for Code Section III requirements. the ASME Code Section III. nondestructive examination of 3.b) Pressure boundary welds in piping pressure boundary welds.

identified in Table 2.7.1-2 as ASME Code Section III meet ASME Code Section III requirements.

C-371 Amendment No. 156

Table 3.3-3 Class 1E Divisions in Nuclear Island Fire Areas Class 1E Divisions Fire Area Number A C B D Auxiliary Building Radiologically Controlled 1200 AF 01 Yes Yes - -

1204 AF 01 Yes - - -

1220 AF 02 - - - Yes Auxiliary Building Non-Radiologically Controlled 1200 AF 03 - - Yes Yes 1201 AF 02 - - -

Yes Note 2 Note 2 Note 2 1201 AF 03 - - -

Yes Note 2 Note 2 Note 2 1201 AF 04 - - Yes Yes 1201 AF 05 - - Yes Yes 1201 AF 06 - - Yes Yes 1202 AF 03 - - -

Yes Note 2 Note 2 Note 2 1202 AF 04 - - -

Yes Note 2 Note 2 Note 2 1220 AF 01 - - Yes Yes 1230 AF 01 Yes Yes - -

1230 AF 02 - - Yes Yes 1240 AF 01 Yes Yes - -

1242 AF 02 Yes -

Note 1: Dash (-) indicates not applicable.

Note 2: Cables from this division in this fire area are limited to interdivisional cables terminating in this fire area.

Table 3.3-4 is not used.

C-421 Amendment No. 156