ND-19-1140, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.07.ii (Index Number 108)

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Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.07.ii (Index Number 108)
ML19266A636
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 09/23/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-19-1140
Download: ML19266A636 (12)
v • d • e


Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel SEP 2 3 2019 Docket Nos.: 52-025 52-026 ND-19-1140 10CFR 52.99(c)(3)

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 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.01.07.11 [Index Number 1081 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of September 18, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.07.ii

[Index Number 108] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

Southern Nuclear Operating Company(SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.2.01.07.11 [Index Number 108] ND-18-0663

[ML19249C320], dated September 6, 2019. This resubmittal supersedes ND-18-0663 in its entirety.

This notification is informed by the guidance described in 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.

All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding tfiat all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

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

Respectfully submitted.

Michael J. Yox Regulatory Affairs Directc/r Vogtle 3 & 4

Michael J.Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro. GA 30830 706-848-6459 tel Enclosure; Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.07.11 [Index Number 108]

MJY/CWM/sfr

U.S. Nuclear Regulatory Commission ND-19-1140 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

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

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

Mr. G. Chick Mr. M. J. Vox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 go:

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

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-19-1140 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinghouse 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. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hosier, 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 Service 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-19-1140 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-19-1140 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.07.ii [Index Number 108]

U.S. Nuclear Regulatory Commission ND-19-1140 Enclosure Page 2 of 8 ITAAC Statement Desion Commitment

7. The CMS provides the safety-related function of containment isolation for containment boundary integrity and provides a barrier against the release of fission products to the atmosphere.

Insoections/Tests/Analvses ii) Testing will be performed to demonstrate that remotely operated containment isolation valves close within the required response times.

Acceptance Criteria ii) The containment purge isolation valves(VFS-PLV-003, -V004, -V009, and -V010) close within 10 seconds, containment vacuum relief isolation valves(VFS-PL-V800A and -V800B) close within 30 seconds, SGS valves SGS-PL-V040A/B and SGS-PL-V057A/B are covered in subsection 2.2.4, Table 2.2.4-4 (item 11 .b.ii) and all other containment isolation valves close within 60 seconds upon receipt of an actuation signal.

ITAAC Completion Description Multiple ITAAC are performed to verify by tests that the Containment System (CNS) provides the safety-related function of containment isolation for containment boundary integrity and provides a barrier against the release of fission products to the atmosphere. Testing will be performed to demonstrate that remotely operated containment isolation valves close within the required response times. The containment purge isolation valves (VFS-PLV003, -V004, -V009, and -V010) close within 10 seconds, containment vacuum relief isolation valves (VFS-PL-V800A and -V800B) close within 30 seconds, SGS valves SGS-PL-V040A/B and SGS-PL-V057A/B are covered in the Combined License(COL) Appendix C subsection 2.2.4, Table 2.2.4-4(item 11.b.ii) included in consolidated ITAAC Index 250 and all other containment isolation valves close within 60 seconds upon receipt of an actuation signal. The VEGP Unit 3 and 4 Updated Final Safety Analysis Report(UFSAR)Table 6.2.3-1 identifies all remotely operated containment isolation valves.

Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 1 and 2). These component test packages utilize B-GEN-ITPCI-039(Reference 3) to direct the performance of test procedures 3/4-CAS-OTS 001 (References 4 and 5), 3/4-CCS-OTS-10-001 (References 6 and 7), 3/4-GEN-OTS-10-001 (References 8 and 9), 3/4-GEN-OTS-10-002(References 10 and 11), 3/4-GEN-OTS-10-003 (References 12 and 13), 3/4-GEN-OTS-10-004(References 14 and 15), 3/4-RNS-OTS-17-004 (References 16 and 17), 3/4-SGS-OTS-10-003(References 18 and 19), 3/4-SGS-OTS-10-004 (References 20 and 21), and 3/4-VWS-OTS-10-001 (References 22 and 23) to verify Containment isolation valve closure times.

References 4 through 23 establish initial conditions with each Containment isolation valve in the open position. An actuation signal is generated by Protection and Safety Monitoring System

U.S. Nuclear Regulatory Commission ND-19-1140 Enclosure Page 3 of 8 (PMS) using the PMS Maintenance and Test Panel(MTP)to close each Containment isolation valve. Each Containment isolation valve closure is timed from the time the closed demand signal is generated until the valve is fully closed. The Containment isolation valve is verified locally closed by a person located at the valve.

The completed Unit 3 and Unit 4 component test results (References 1 and 2) confirm the containment purge isolation valves(VFS-PLV003,-V004, -V009, and -V010) close within 10 seconds, containment vacuum relief isolation valves(VFS-PL-V800A and -V800B) close within 30 seconds, SGS valves SGS-PL-V040A/B and SGS-PL-V057A/B are covered in COL Appendix C subsection 2.2.4, Table 2.2.4-4 (item ll.b.ii) and all other containment isolation valves close within 60 seconds upon receipt of an actuation signal as shown in Attachment A.

Attachment A was generated to document the remotely operated containment isolation valves and the information contained in Attachment A was obtained from the VEGP Unit 3 and 4 Updated Final Safety Analysis Report(UFSAR)Table 6.2.3-1 and COL Appendix C.

References 1 and 2 are available for NRC inspection as part of ITAAC 2.2.01.07.ii Unit 3 and 4 Completion Packages(Reference 24 and 25).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company(SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References(available for NRC inspection)

1. SNCXXXXXX
2. SNCYYYYYY
3. B-GEN-ITPCI-039,"PMS CIM Component Test Procedure"
4. 3-CAS-0TS-10-001,"Compressed Air System Valve Stroke Test"
5. 4-CAS-0TS-10-001,"Compressed Air System Valve Stroke Tesf
6. 3-CCS-0TS-10-001,"Component Cooling Water System Valve Stroke Test"
7. 4-CCS-0TS-10-001,"Component Cooling Water System Valve Stroke Test"
8. 3-GEN-0TS-10-001,"Division A Quarterly Valve Stroke Tesf
9. 4-GEN-0TS-10-001,"Division A Quarterly Valve Stroke Test"
10. 3-GEN-0TS-10-002,"Division B Quarterly Valve Stroke Tesf
11. 4-GEN-QTS-10-002,"Division B Quarterly Valve Stroke Test" 12.3-GEN-QTS-10-003,"Division C Quarterly Valve Stroke Tesf 13.4-GEN-QTS-10-003,"Division C Quarterly Valve Stroke Tesf
14. 3-GEN-QTS-10-004,"Division D Quarterly Valve Stroke Test" 15.4-GEN-QTS-10-004,"Division D Quarterly Valve Stroke Tesf 16.3-RNS-QTS-17-004,"Normal Residual Heat Removal System Valve Stroke Tesf
17. 4-RNS-QTS-17-004,"Normal Residual Heat Removal System Valve Stroke Tesf
18. 3-SGS-QTS-10-003,"Steam Generating System Valve Stroke Test Train A Modes 3-6" 19.4-SGS-QTS-10-003,"Steam Generating System Valve Stroke Test Train A Modes 3-6" 20.3-SGS-QTS-10-004,"Steam Generating System Valve Stroke Test Train B Modes 3-6"
21. 4-SGS-QTS-10-004,"Steam Generating System Valve Stroke Test Train B Modes 3-6" 22.3-VWS-QTS-10-001,"Central Chilled Water System Valve Stroke Test"

U.S. Nuclear Regulatory Commission ND-19-1140 Enclosure Page 4 of 8 23.4-VWS-OTS-10-001,"Central Chilled Water System Valve Stroke Tesf 24.2.2.01.07.ii-U3-CP-Rev 0, ITAAC Completion Package 25.2.2.01.07.ii-U4-CP-Rev 0, ITAAC Completion Package

26. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-1140 Enclosure Page 5 of 8 Attachment A Required Actual Valve Equipment Name^^' Valve Closure Test Tag No.<^' Closure Time Time Procedure (seconds)

(seconds)

Instrument Air Supply Outside Containment CAS-PL-V014 < 60 CAS-OTS-10-001 Isolation Valve Component Cooling Water System (CCS)

Containment Isolation Motor-operated Valve CCS-PL-V200 S 60 CCS-OTS-10-001 (MOV)- Inlet Line s Outside Reactor OC Containment(ORC)

CCS Containment Isolation MOV - Outlet CCS-PL-V207 o S 60 DC CCS-OTS-10-001 Line IRC VI CCS Containment Isolation MOV - Outlet CCS-PL-V208 < 60 CCS-OTS-10-001 Line ORC CVS Letdown Containment Isolation CVS-PL-V045 < 60 GEN-OTS-10-001 Valve CVS Letdown Containment Isolation CVS-PL-V047 i 60 GEN-OTS-10-004 Valve CVS Makeup Line Containment Isolation CVS-PL-V090 GEN-OTS-10-004 Motor-operated Valve CVS Makeup Line Containment Isolation CVS-PL-V091 5 60 (S 30) GEN-OTS-10-001 Motor-operated Valve CVS Zinc Injection Containment Isolation CVS-PL-V092 ^ 60 GEN-OTS-10-004 Valve ORC CVS Zinc Injection Containment Isolation CVS-PL-V094 ^ 60 (1) GEN-OTS-10-001 Valve IRC CVS Hydrogen Injection Containment Isolation CVS-PL-V219 £ 60 GEN-OTS-10-004 Valve ORC Containment Air Sample Containment Isolation Valve Inside Reactor PSS-PL-V008 < 60 GEN-OTS-10-002 Containment(IRC)

Liquid Sample Line Containment Isolation PSS-PL-V010A < 60 GEN-OTS-10-002 Valve IRC Liquid Sample Line Containment Isolation PSS-PL-V010B < 60 GEN-OTS-10-004 Valve IRC

U.S. Nuclear Regulatory Commission ND-19-1140 Enclosure Page 6 of 8 Attachment A (con't)

Required Actual Valve Equipment Name^^' Valve Closure Test Tag No.<^> Closure Time Time Procedure (seconds)

(seconds)

Liquid Sample Line Containment Isolation Valve Outside Reactor PSS-PL-V011A < 60 GEN-OTS-10-003 Containment(ORC)

Liquid Sample Line Containment Isolation PSS-PL-V011B < 60 0) GEN-OTS-10-001 Valve ORC Sample Return Line Containment Isolation PSS-PL-V023 S 60 GEN-OTS-10-001 Valve ORC Sample Return Containment Isolation PSS-PL-V024 S 60 GEN-OTS-10-002 Valve IRC Air Sample Line Containment Isolation PSS-PL-V046 S 60 GEN-OTS-10-001 Valve ORC Nitrogen Supply Containment Isolation PXS-PL-V042 < 60 GEN-OTS-10-004 Valve RCS Outer Hot Leg Suction Motor-operated RNS-PL-V002A S 60 RNS-OTS-17-004 Isolation Valve RCS Outer Hot Leg Suction Motor-operated RNS-PL-V002B ^ 60 RNS-OTS-17-004 Isolation Valve RNS Discharge Motor-operated Containment RNS-PL-V011 < 60 GEN-OTS-10-001 Isolation Valve RNS Suction Header Motor-operated RNS-PL-V022 < 60 GEN-OTS-10-001 Containment Isolation Valve RNS Suction from IRWST Motor-operated RNS-PL-V023 5 60 GEN-OTS-10-002 Isolation Valve RNS Return from Chemical and Volume Control System (CVS) RNS-PL-V061 5 60 GEN-OTS-10-002 Containment Isolation Valve SFS Suction Line Containment Isolation SFS-PL-V034 5 60 GEN-OTS-10-002 MOV - IRC SFS Suction Line Containment Isolation SFS-PL-V035 S 60 GEN-OTS-10-001 MOV - ORC

U.S. Nuclear Regulatory Commission ND-19-1140 Enclosure Page 7 of 8 Attachment A (con't)

Required Actual Valve Valve Closure Test Equipment Name^^^ Tag Closure Time Time Procedure (seconds)

(seconds)

SFS Discharge Line Containment Isolation SFS-PL-V038 S 60 GEN-OTS-10-001 MOV - ORC Power-operated Relief Valve Block Motor-operated Valve Steam SGS-PL-V027A < 60 (< 44)<2) GEN-OTS-10-002 Generator 01 Power-operated Relief Valve Block Motor-operated Valve Steam SGS-PL-V027B < 60 (< 44)<2) GEN-OTS-10-004 Generator 02 Steam Line Condensate SGS-PL-V036A < 60 GEN-OTS-10-004 Drain Isolation Valve Steam Line Condensate SGS-PL-V036B S 60 GEN-OTS-10-004 Drain Isolation Valve Main Steam Line SGS-PL-V040A <5<1> SGS-OTS-10-003 Isolation Valve Main Steam Line SGS-PL-V040B <5(1) SGS-OTS-10-004 Isolation Valve Main Feedwater Isolation Valve SGS-PL-V057A <5(1) SGS-OTS-10-003 Main Feedwater Isolation Valve SGS-PL-V057B <5(1) SGS-OTS-10-004 Startup Feedwater Isolation Motor-operated SGS-PL-V067A < 60(1) GEN-OTS-10-002 Valve Startup Feedwater Isolation Motor-operated SGS-PL-V067B ^ 60(1) GEN-OTS-10-004 Valve Steam Generator Slowdown Isolation SGS-PL-V074A S 60 (1) GEN-OTS-10-004 Valve Steam Generator Slowdown Isolation SGS-PL-V074B S 60(1) GEN-OTS-10-002 Valve Main Steam Isolation GEN-OTS SGS-PL-V240A ^ 60(1)

Valve Bypass Isolation 002/-004 Main Steam Isolation GEN-OTS SGS-PL-V240B < 60(1)

Valve Bypass Isolation 002/-004 Containment Purge Inlet Containment Isolation VFS-PL-V003 <10(1) GEN-OTS-10-001 Valve - ORC Containment Purge Inlet Containment Isolation VFS-PL-V004 < 10(1) GEN-OTS-10-004 Valve - IRC

U.S. Nuclear Regulatory Commission ND-19-1140 Enclosure Page 8 of 8 Attachment A (con't)

Required Actual Valve Valve Closure Test Equipment Name^^^ Tag No.<2) Closure Time Time Procedure (seconds)

(seconds)

Containment Purge Discharge Containment VFS-PL-V009 GEN-OTS-10-004 Isolation Valve - IRC Containment Purge Discharge Containment VFS-PL-V010 GEN-OTS-10-001 Isolation Valve - ORC Vacuum Relief Containment Isolation VFS-PL-V800A < 30 GEN-OTS-10-001 AMOV-ORC Vacuum Relief Containment Isolation VFS-PL-V800B < 30(1) GEN-OTS-10-003 B MOV - ORC Fan Coolers Supply Containment Isolation VWS-PL-V058 S 60 VWS-OTS-10-001 Valve - ORC Fan Coolers Return Containment Isolation VWS-PL-V082 < 60 VWS-OTS-10-001 Valve - IRC Fan Coolers Return Containment Isolation VWS-PL-V086 ^ 60 VWS-OTS-10-001 Valve - ORC Sump Discharge Containment Isolation WLS-PL-V055 < 60 GEN-OTS-10-001 Valve - IRC Sump Discharge Containment Isolation WLS-PL-V057 S 60 GEN-OTS-10-004 Valve - ORC Reactor Coolant Drain Tank(RCDT) Gas WLS-PL-V067 < 60 GEN-OTS-10-001 Outlet Containment Isolation Valve - IRC RCDT Gas Outlet Containment Isolation WLS-PL-V068 <60<^) GEN-OTS-10-004 Valve - ORC From U3/U4 COL Appendix C.

From VEGP Unit 3 and 4 Updated Final Safety Analysis Report(UFSAR)Table 6.2.3-1.

Required Valve Closure time will be the minimum value listed.

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