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

Amendment No. 156 (Unit 4)

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and associated 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.

D.1 Initiate action to open the RCS pressure boundary.

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

In accordance with applicable SRs

Technical Specifications MSSVs 3.7.1 VEGP Units 3 and 4 3.7.1 - 2 Amendment No. 158 (Unit 3)

Amendment No. 156 (Unit 4)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2

- NOTE -

Only required in MODE 1.

Reduce the Overpower T 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.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> B.

One or both steam generators with one or more MSSVs inoperable for closing.

B.1 Restore MSSV to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.

Required Action and associated Completion Time of Condition A not met.

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

C.1 AND C.2 Be in MODE 3.

Be in MODE 4 with the RCS cooling provided by the RNS.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 24 hours D.

Required Action and associated Completion Time of Condition B not met.

D.1 AND D.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 36 hours

C-40 Amendment No. 156 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-101 Amendment No. 156 Figure 2.2.1-1 Containment System

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

C-249a 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 Table 2.3.9-2 perform the listed function after receiving a manual signal from DAS.

Testing will be performed on the igniters using the DAS controls.

The igniters energize after receiving a 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-259 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 seismic design requirements in Table 2.3.11-1 can withstand seismic design basis loads without loss of its structural integrity function.

i) Inspection will be performed to verify that the equipment identified as having seismic design requirements in Table 2.3.11-1 is located on the Nuclear Island.

i) The equipment identified as having seismic design requirements in Table 2.3.11-1 is located on the Nuclear Island.

ii) Type tests, analyses, or a combination of type tests and analyses of seismically designed equipment will be performed.

ii) A report exists and concludes that the seismically designed equipment can withstand appropriate seismic design basis loads without loss of its structural integrity function.

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

iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or 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-related function of processing radioactive gases prior to discharge.

Inspection will be performed to verify the contained volume of each of the activated carbon delay beds, WGS-MV-02A and WGS-MV-02B.

A report exists and concludes that the contained volume in each of the activated carbon delay beds, WGS-MV-02A and WGS-MV-02B, is at least 80 ft3.

454 2.3.11.03b 3.b) The WGS provides the nonsafety-related function of controlling the releases of radioactive materials in gaseous effluents.

Tests will be performed to confirm that the presence of a simulated high radiation signal from the discharge radiation monitor, WGS-017, causes the discharge control isolation valve WGS-PL-V051 to close.

A simulated high radiation signal causes the discharge control isolation valve WGS-PL-V051 to close.

455 2.3.11.03c 3.c) The WGS is purged with nitrogen on indication of high oxygen levels in the system.

Tests will be performed to confirm that the presence of a simulated high oxygen level signal from the oxygen monitors (WGS-025A, -025B) causes the nitrogen purge valve (WGS-PL-V002) to open and the WLS degasifier vacuum pumps (WLS-MP-03A, -03B) to stop.

A simulated high oxygen level signal causes the nitrogen purge valve (WGS-PL-V002) to open and the WLS degasifier vacuum pumps (WLS-MP-03A, -03B) to stop.

C-292 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-326 Amendment No. 156 Figure 2.6.1-1 (Sheet 1 of 4)

Main ac Power System

C-334 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without recharging.

d) Each IDS 72-hour battery bank supplies a dc switchboard bus load for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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-340 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 independence between the Class 1E divisions.

Testing will be performed on the IDS by providing a simulated test signal in each Class 1E division.

A simulated test signal exists at the Class 1E equipment identified in Table 2.6.3-1 when the assigned Class 1E division is provided the test signal.

602 2.6.03.04b 4.b) The IDS provides electrical isolation between itself and the non-Class 1E ac power system and the non-Class 1E lighting in the MCR.

Type tests, analyses, or a combination of type tests and analyses of the isolation devices will be performed.

A report exists and concludes that the battery chargers, regulating transformers, and isolation fuses prevent credible faults from propagating into the IDS.

603 2.6.03.04c 4.c) Each IDS 24-hour battery bank supplies a dc switchboard bus load for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without recharging.

Testing of each 24-hour as-built battery bank will be performed by applying a simulated or real load, or a combination of simulated or real loads which envelope the battery bank design duty cycle. The test will be 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the test.

The battery terminal voltage is greater than or equal to 210 V after a period of no less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with an equivalent load that equals or exceeds the battery bank design duty cycle capacity.

4.d) Each IDS 72-hour battery bank supplies a dc switchboard bus load for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> without recharging.

Testing of each 72-hour as-built battery bank will be performed by applying a simulated or real load, or a combination of simulated or real loads which envelope the battery bank design duty cycle. The test will be 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the test.

The battery terminal voltage is greater than or equal to 210 V after a period of no less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with an equivalent load that equals or exceeds the battery bank design duty cycle capacity.

C-356 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 grounding system for:

(1) instrument/computer grounding; (2) electrical system grounding of the neutral points of the main generator, 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.

i) An inspection for the instrument/computer grounding system connection to the station grounding grid will be performed.

i) A connection exists between the instrument/computer grounding system and the station grounding grid.

ii) An inspection for the electrical system grounding connection to the station grounding grid will be performed.

ii) A connection exists between the electrical system grounding and the station grounding grid.

iii) An inspection for the equipment grounding system connection to the station grounding grid will be performed.

iii) A connection exists between the equipment grounding system and the station grounding grid.

iv) An inspection for the lightning protection system connection to the station grounding grid will be performed.

iv) A connection exists between the lightning protection system and the station grounding grid.

638 2.6.06.01.ii Not used per Amendment No. 112

C-371 Amendment No. 156 Table 2.7.1-3 Equipment Tag No.

Display Control Function Division "B" and "D" Class 1E Electrical Room AHU D Fans VBS-MA-05D VBS-MA-06D Yes (Run Status)

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

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

Start MCR Ancillary Fans VBS-MA-10A VBS-MA-10B No 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 VBS is as described in the Design Description of this subsection 2.7.1 Inspection of the as-built system will be performed.

The as-built VBS conforms with the functional arrangement described in the Design Description of this subsection 2.7.1.

678 2.7.01.02a 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.

2.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.

Inspection will be conducted of the as-built components and piping as documented in the ASME design reports.

The ASME Code Section III design reports exist for the as-built components and piping identified in Tables 2.7.1-1 and 2.7.1-2 as ASME Code Section III.

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.

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

Inspection of the as-built pressure boundary welds will be performed in accordance with the ASME Code Section III.

A report exists and concludes that the ASME Code Section III requirements are met for nondestructive examination of pressure boundary welds.

C-421 Amendment No. 156 Table 3.3-3 Class 1E Divisions in Nuclear Island Fire Areas Fire Area Number Class 1E Divisions 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 Note 2 Note 2 Yes Note 2 1201 AF 03 Note 2 Note 2 Note 2 Yes 1201 AF 04 Yes Yes 1201 AF 05 Yes Yes 1201 AF 06 Yes Yes 1202 AF 03 Note 2 Yes 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.