ND-17-2126, ITAAC Closure Notification on Completion of ITAAC 3.7.00.01 (Index Number 841)

ITAAC Closure Notification on Completion of ITAAC 3.7.00.01 (Index Number 841)

ML17363A285
Person / Time
Site:	Vogtle
Issue date:	12/29/2017
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-17-2126
Download: ML17363A285 (11)

Text

Michael J. Vox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@souttiernco.com DEC 2 9 2017 Docket Nos.: 52-025 52-026 ND-17-2126 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 ITAAC Closure Notification on Completion of ITAAC 3.7.00.01 tindex Number 8411 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)

Unit 3 and Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.7.00.01

[Index Number 841] which confirms the design of Structures, Systems and Components (SSC) within the scope of the reliability assurance program is consistent with risk insights and key assumptions. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 3.7.00.01 [Index Number 841]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-17-2126 Page 2 of 3 To:

Southern Nuclear Operating Company / Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Vox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. R. L. Beiike Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Oalethorpe Power Corporation Mr. K. T. Haynes Mr. R. B. Brinkman Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-17-2126 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. 8. DiTommaso Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Sen/ice Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-17-2126 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-17-2126 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 3.7.00.01 [Index Number 841]

U.S. Nuclear Regulatory Commission ND-17-2126 Enclosure Page 2 of 8 ITAAC Statement Design Commitment

1. The D-RAP ensures that the design of SSCs within the scope of the reliability assurance program (Table 3.7-1) is consistent with the risk insights and key assumptions (e.g., SSC design, reliability, and availability).

Inspections. Tests. Analyses An analysis will confirm that the design of RAP SSCs identified in Table 3.7-1 has been completed in accordance with applicable D-RAP activities.

Acceptance Criteria An analysis report documents that safety-related SSCs identified in Table 3.7-1 have been designed in accordance with a 10 CFR 50 Appendix B quality program.

An analysis report documents that non-safety-related SSCs identified in Table 3.7-1 have been designed in accordance with a program that satisfies quality assurance requirements for SSCs important to investment protection.

ITAAC Determination Basis Risk-significant SSCs identified for the Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 design are listed in the VEGP Unit 3 and Unit 4 Combined License (COL) Appendix C Table 3.7-1. Table 3.7-1 is provided in the attachment.

The Westinghouse Quality Management System (QMS) defines the 10 CFR 50 Appendix B quality program that was used for the design of the safety-related SSCs. The NRC approved Revision 7 to the Westinghouse QMS by letter dated December 29, 2014 (ML14336A487).

Westinghouse procedure APP-GW-GAM-200, "API000 Quality Assurance Requirements for RTNSS Systems, Structures, and Components" (Reference 1), defines the quality program that was used for the design of non-safety-related SSCs.

Engineering Report APP-GW-GRR-011, "API000 Design Reliability Assurance Program inspections, Test, Analyses, and Acceptance Criteria Report" (Reference 2), documents the analysis report that verified the components listed in VEGP Unit 3 and Unit 4 COL Appendix C Table 3.7-1 have been designed in accordance with a program that satisfies applicable quality assurance redluirements. Safety-related SSCs Identified in VEGP Unit 3 and Unit 4 COL Appendix C Table 3.7-1 have been designed in accordance with a 10 CFR 50 Appendix B program and i:he non-safety-related SSCs identified in VEGP Unit 3 and Unit 4 COL Appendix C Table 3.7-1 have been designed in accordance with a program that satisfies quality assurance requirements for SSCs important to investment protection.

ITAAC Finding Review In accordance! with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and

U.S. Nuclear Regulatory Commission ND-17-2126 Enclosure Page 3 of 8 associated corrective actions. This review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC finding review is documented in the VEGP Unit 3 and Unit 4 ITAAC Completion Package for ITAAC 3.7.00.01 [Index Number 841] (Reference 3) and is available for NRC inspection.

ITAAC Completion Statement Based upon the above information, SNC hereby notifies the NRC that ITAAC 3.7.00.01 [Index Number 841] was performed for VEGP Unit 3 and Unit 4 and the prescribed acceptance criteria are met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

I References (available for NRC inspection)

I

1. APP-GW-(i3AM-200, "API 000 Quality Assurance Requirements for RTNSS Systems, Structures! and Components," Revision 2

2. APP-GW-GRR-011, "API000 Design Reliability Assurance Program Inspections, Test, Analyses, and Acceptance Criteria Report," Revision 1

3. ITAAC 3.7.00.01-U0-CP Completion Package for Unit 3 and Unit 4 [Index Number 841],

Design Reliability Assurance Program

U.S. Nuclear!Regulatory Commission ND-17-2126 Enclosure Page 4 of 8 Attachment A COL Appendix 0, Table 3.7-1 Table 3.7-1 RIsk-Slgnlflcant Components Equipment Name Tag No.

Component Cooling Water System (COS)

Component Cooling Water Pumps CCS-MP-01A/B Containment System (CNS)

Containment Vessel CNS-MV-01 Hydrogen Igniters VLS-EH-1 through -66 Chemical and Volume Control System (CVS)

Makeup Pumps CVS-MP-01A/B Makeup Pumps Suction and Discharge Check CVS-PL-V113 Valves CVS-PL-V160A/B Letdown Discharge Isolation Valves CVS-PL-V045 CVS-PL-V047 Diverse Actuation System (DAS)

DAS Processor Cabinets and Control Panel DAS-JD-001 (used to provide automatic and manual DAS-JD-002 actuation) DAS-JD-003 OCS-JC-20 Auxiliary Building UPS Distribution Panels EDS2-EA-12, EDS3-EA-14A (provide power to DAS)

Control Cabinets for the Rod Drive MG Sets PLS-JD-RDM001 (generator field control relays) PLS-JD-RDM002 Containment Isolation Valves Controlled by DAS CVS-PL-V045, -047 VFS-PL-V003, -V004, -V009, -V010 WLS-PL-V055, -V057 Main ac Powerj System (ECS)

Reactor Coolant Pump Switchgear ECS-ES-31,-32, -41,-42,

-51,-52, -61,-62 Ancillary Diesel Generators ECS-MS-01, -02 6900 Vac Buses ECS-ES-1,-2

U.S. Nuclear Regulatory Commission ND-17-2126 Enclosure Page 5 of 8 Attachment A COL Appendix 0, Table 3.7-1 Table 3.7-1 RIsk-Slgnlflcant Components Equipment Name Tag No.

Main and Startup Feedwater System (FWS)

Startup Feedwater Pumps FWS-MP-03A/B General l&G j IRWST Wide Range Level Sensors PXS-046, -047, -048 IRWST Lower Narrow Range Level Sensors PXS-066, -067, -068, -069 RCS Hot Leg Level Sensors RGS-160A/B Pressurizer Pressure Sensors RGS-191A/B/G/D Pressurizer Level Sensors RGS-195A/B/G/D Steam Generator Narrow-Range Level Sensors SGS-001, -002, -003, -004,

-005, -006, -007, -008 Steam Generator Wide-Range Level Sensors SGS-011,-012, -013, -014,

-015, -016, -017,-018 Main Steam Line Pressure Sensors SGS-030, -031, -032, -033,

-034, -035, -036, -037 Main Feedwater Low-Range Flow Sensors FWS-050A/G/E, -051A/G/E Startup Feedwater Flow Sensors SGS-055A/B/G/D/E, -056A/B/G/D/E GMT Level Sensors PXS-011A/B/G/D, -012A/B/G/D,

-013A/B/G/D, -014A/B/G/D Glass 1E dc Pdwer and Uninterruptible Power System (IDS) 250 Vdc 24-Hour Batteries IDSA-DB-1A/B, IDSB-DB-1A/B, IDSG-DB-1A/B, IDSD-DB-1A/B 250 Vdc 24-Hour Buses IDSA-DS-1, IDSB-DS-1 IDSG-DS-1, IDSD-DS-1 250 Vdc 24-Hour Battery Chargers IDSA-DG-1, IDSB-DG-1, IDSG-DG-1, IDSD-DG-1

U.S. Nuclear Regulatory Commission ND-17-2126 Enclosure Page 6 of 8 Attachment A COL Appendix 0, Table 3.7-1 Table 3.7-1 RIsk-Slgnlflcant Components Equipment Name Tag No.

250 Vdc and 120 Vac Distribution Panels IDSA-DD-1, IDSA-EA-1/-2, IDSB-DD-1, IDSB-EA-1/-2/-3, IDSC-DD-1, IDSC-EA-1/-2/-3, IDSD-DD-1, IDSD-EA-1/-2 Fused Transfer Switch Boxes IDSA-DF-1, IDSB-DF-1/-2, IDSC-DF-1/-2, IDSD-DF-1 250 Vdc Motor Control Centers IDSA-DK-1, IDSB-DK-1, IDSC-DK-1, IDSD-DK-1 250 Vdc 24-Hour Inverters IDSA-DU-1, IDSB-DU-1, IDSC-DU-1, IDSD-DU-1 Passive Contaihment Cooling System (PCS)

Recirculation Pumps PCS-MP-01A/B PCCWST Drain Isolation Valves PCS-PL-V001A/B/C Plant Control System (PLS)

PLS Actuation Software (used to provide control Refer to Table 3.7-2 functions)

PLS Actuation Hardware (used to provide control Refer to Table 3.7-2 functions)

Protection and Monitoring System (PMS)

PMS Actuation Software (used to provide Refer to Tables 2.5.2-2 and 2.5.2-3 automatic control functions)

PMS Actuation Hardware (used to provide Refer to Tables 2.5.2-2 and 2.5.2-3 automatic control functions)

MCR 1E Displays and System Level Controls OCS-JC-010, -Oil Reactor Trip Switchgear PMS-JD-RTSA01/02, B01/02, C01/02, D01/02 Passive Core dooling System (PXS)

PXS-MY-Y21, -Y22, -Y23, -Y24, -Y25, IRWST Hood Vent Covers

-Y26, -Y27, -Y28, -Y29, -Y30, -Y31, -Y32,

-Y33, -Y41, -Y47, -Y48 IRWST Steam Generator Wall Vent Covers PXS-MY-Y61, -Y62, -Y63, -Y64

U.S. Nuclear Regulatory Commission ND-17-2126 Enclosure Page 7 of 8 Attachment A COL Appendix 0, Table 3.7-1 Table 3.7-1 RIsk-Slgnlflcant Components Equipment Name Tag No.

IRWST Overflow Weir Covers PXS-MY-Y71, -Y72, -Y73, -Y74, -Y75, -Y76 IRWST Screens PXS-MY-Y01A/B/C Containment Recirculation Screens PXS-MY-Y02A/B CMT Discharge isolation Valves PXS-PL-V014A/B, -V015A/B CMT Discharge Check Valves PXS-PL-V016A/B, -V017A/B Accumulator Discharge Check Valves PXS-PL-V028A/B, -V029A/B PRHR HX Control Valves PXS-PL-V108A/B Containment Recircuiation Squib Valves PXS-PL-V118A/B, -V120A/B IRWST Injection Check Valves PXS-PL-V122/VB, -V124A/B IRWST Injection Squib Valves PXS-PL-V123A/B, -V125A/B IRWST Gutter Bypass Isolation Valves PXS-PL-V130A/B ReactorCoolar]it System (RCS)

ADS Stage 1/2/3 Valves (MOVs) RCS-PL-V001A/B, -V011A/B RCS-PL-V002A/B, -V012A/B RCS-PL-V003A/B, -V013A/B ADS Stage 4 Valves (Squibs) RCS-PL-V004A/B/C/D Pressurizer Safety Valves RCS-PL-V005A/B Reactor Vessel Insulation Water Inlet and Steam RXS-MN-01 Vent Devices Reactor Cavity Doorway Damper -

Fuel Assemblies 157 assemblies with tag numbers beginning with RXS-FA Normal Residual Heat Removal System (RNS)

Residual Heat Removal Pumps RNS-MP-01A/B RNS Motor-Operated Valves RNS-PL-V011, -V022, -V023, -V055 RNS Stop Check Valves RNS-PL-V015A/B RNS Check Valves RNS-PL-V017A/B RNS Check Valves RNS-PL-V007A/B, -V013, -V056

U.S. Nuclear Regulatory Commission ND-17-2126 Enclosure Page 8 of 8 Attachment A COL Appendix C, Table 3.7-1 Table 3.7-1 RIsk-Slgnlflcant Components Equipment Name Tag No.

Spent Fuel Cooling System (SFS)

Spent Fuel Cooling Pumps SFS-MP-01A/B Steam Generator System (SGS)

Main Steam Safety Valves SGS-PL-V030A/B, -V031A/B, -V032A/B,

-V033A/B, -V034A/B, -V035A/B Main Steam Line Isolation Valves SGS-PL-V040A/B Main Feedwater Isolation Valves SGS-PL-V057A/B Service Water ^ystem (SWS)

Service Water Cooling Tower Fans SWS-MA-01A/B Service Water Pumps SWS-MP-01A/B Nuclear Island Nonradioactive Ventilation System (VBS)

MCR Ancillary Fans VBS-MA-10A/B l&C Room B/C Ancillary Fans VBS-MA-11, -12 Containment Air Filtration System (VFS)

Containment Purge Isolation Valves VFS-PL-V003 VFS-PL-V004 VFS-PL-V009 VFS-PL-V010 Chilled Water System (VWS)

Air Cooled Chiller Pumps VWS-MP-02, -03 Air Cooled Chillers VWS-MS-02, -03 Liquid Radwaste System (WLS)

Sump Containment Isolation Valves WLS-PL-V055 WLS-PL-V057 Onsite Standby Power System (ZOS)

Engine Room Exhaust Fans VZS-MY-V01A/B, -V02A/B Onsite Diesel Generators ZOS-MS-05A/B Note: Dash (-) indicates not applicable.