ND-18-0663, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.07.11 (Index Number 108)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.07.11 (Index Number 108)

ML19249C320
Person / Time
Site:	Vogtle
Issue date:	09/06/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0663
Download: ML19249C320 (11)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel SEP 0 6 2019 Docket Nos.: 52-025 52-026 ND-18-0663 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 August 28, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.07.11

[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.

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 that 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 Director Vogtle 3 & 4

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-18-0663 Page 2 of 3 To:

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

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

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

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

Mr. G. Chick Mr. M. J. Yox 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. 8. 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-18-0663 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani (w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward 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 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-18-0663 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-18-0663 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.07.11 [Index Number 108]

U.S. Nuclear Regulatory Commission ND-18-0663 Enclosure Page 2 of 8 ITAAC Statement Design Commitment

7. The 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.

Inspections/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 11b.ii) and all other containment isolation valves close within 60 seconds upon receipt of an actuation signal.

ITAAC Completion DescriDtion 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 li.b.ii) 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 (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

U.S. Nuclear Regulatory Commission ND-18-0663 Enclosure Page 3 of 8 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 Test"

6. 3-CCS-0TS-10-001,"Component Cooling Water System Valve Stroke Test"

7. 4-CCS-OTS-10-001,"Component Cooling Water System Valve Stroke Test"

8. 3-GEN-0TS-10-001,"Division A Quarterly Valve Stroke Test"

9. 4-GEN-0TS-10-001,"Division A Quarterly Valve Stroke Test"

10. 3-GEN-0TS-10-002,"Division B Quarterly Valve Stroke Test" 11.4-GEN-0TS-10-002, "Division B Quarterly Valve Stroke Test"

12. 3-GEN-0TS-10-003, "Division C Quarterly Valve Stroke Test" 13.4-GEN-0TS-10-003, "Division C Quarterly Valve Stroke Test"

14. 3-GEN-0TS-10-004,"Division D Quarterly Valve Stroke Test" 15.4-GEN-0TS-10-004,"Division D Quarterly Valve Stroke Test"

16. 3-RNS-0TS-17-004,"Normal Residual Heat Removal System Valve Stroke Test" 17.4-RNS-OTS-17-004,"Normal Residual Heat Removal System Valve Stroke Test"

18. 3-SGS-OTS-10-003,"Steam Generating System Valve Stroke Test Train A Modes 3-6" 19.4-SGS-0TS-10-003,"Steam Generating System Valve Stroke Test Train A Modes 3-6"

20. 3-SGS-0TS-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-0TS-10-001, "Central Chilled Water System Valve Stroke Test" 23.4-VWS-OTS-10-001, "Central Chilled Water System Valve Stroke Test"

U.S. Nuclear Regulatory Commission ND-18-0663 Enclosure Page 4 of 8

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"

27. VEGP Unit 3 & 4 UFSAR

U.S. Nuclear Regulatory Commission ND-18-0663 Enclosure Page 5 of 8 Attachment A Required Actual Valve Valve Closure Test Equipment Name*^> Tag No.'2) Closure Time Time Procedure (seconds)

(seconds)

Instrument Air Supply Outside Containment CAS-PL-V014 260<2) CAS-OTS-10-001 Isolation Valve Component Cooling Water System (CCS)

Containment Isolation Motor-operated Valve CCS-PL-V200 5 60<2) CCS-OTS-10-001 (MOV)- Inlet Line Outside Reactor Containment(ORC)

CCS Containment Isolation MOV - Outlet CCS-PL-V207 < 60 (2) CCS-OTS-10-001 Line IRC CCS Containment Isolation MOV - Outlet CCS-PL-V208 < 60 (2) CCS-OTS-10-001 Line ORC CVS Letdown Containment Isolation CVS-PL-V045 < 60 <2) GEN-OTS-10-001 Valve CVS Letdown Containment Isolation CVS-PL-V047 s 60 (2> GEN-OTS-10-004 Valve CVS Makeup Line Containment Isolation CVS-PL-V090 S 60 <2) GEN-OTS-10-004 Motor-operated Valve CVS Makeup Line Containment Isolation CVS-PL-V091 < 60 (2) GEN-OTS-10-001 Motor-operated Valve CVS Zinc Injection Containment Isolation CVS-PL-V092 < 60 <2) GEN-OTS-10-004 Valve ORC CVS Zinc Injection Containment Isolation CVS-PL-V094 ^ 60 <2) GEN-OTS-10-001 Valve IRC CVS Hydrogen Injection Containment Isolation CVS-PL-V219 ^ 60 <2) GEN-OTS-10-004 Valve ORC Containment Air Sample Containment Isolation PSS-PL-V008 < 60 (2) GEN-OTS-10-002 Valve Inside Reactor Containment(IRC)

Liquid Sample Line Containment Isolation PSS-PL-V010A < 60 <2) GEN-OTS-10-002 Valve IRC Liquid Sample Line Containment Isolation PSS-PL-V010B ^ 60 <2> GEN-OTS-10-004 Valve IRC

U.S. Nuclear Regulatory Commission ND-18-0663 Enclosure Page 6 of 8 Attachment A (con't)

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

(seconds)

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

Liquid Sample Line Containment Isolation PSS-PL-V011B < 60 (2) GEN-OTS-10-001 Valve ORC Sample Return Line Containment Isolation PSS-PL-V023 < 60 (2) GEN-OTS-10-001 Valve ORC Sample Return Containment Isolation PSS-PL-V024 < 60 <2) GEN-OTS-10-002 Valve IRC Air Sample Line Containment Isolation PSS-PL-V046 < 60 <2' GEN-OTS-10-001 Valve ORC Nitrogen Supply Containment Isolation PXS-PL-V042 S 60 <2> GEN-OTS-10-004 Valve RCS Outer Hot Leg Suction Motor-operated RNS-PL-V002A < 60 (2) RNS-OTS-17-004 Isolation Valve RCS Outer Hot Leg Suction Motor-operated RNS-PL-V002B < 60 <2) RNS-OTS-17-004 Isolation Valve RNS Discharge Motor-operated Containment RNS-PL-V011 ^ 60 <2) GEN-OTS-10-001 Isolation Valve RNS Suction Header Motor-operated RNS-PL-V022 < 60 (2) GEN-OTS-10-001 Containment Isolation Valve RNS Suction from IRWST Motor-operated RNS-PL-V023 < 60 <2) GEN-OTS-10-002 Isolation Valve RNS Return from Chemical and Volume Control System (CVS) RNS-PL-V061 ^60<2) GEN-OTS-10-002 Containment Isolation Valve SFS Suction Line Containment Isolation SFS-PL-V034 < 60 <2) GEN-OTS-10-002 MOV-IRC SFS Suction Line Containment Isolation SFS-PL-V035 < 60 <2) GEN-OTS-10-001 MOV-ORC

U.S. Nuclear Regulatory Commission ND-18-0663 Enclosure Page 7 of 8 Attachment A (con't)

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

(seconds)

SFS Discharge Line Containment Isolation SFS-PL-V038 < 60 <2) GEN-OTS-10-001 MOV-ORC Power-operated Relief Valve Block Motor-SGS-PL-V027A see (2) GEN-OTS-10-002 operated Valve Steam Generator 01 Power-operated Relief Valve Block Motor-SGS-PL-V027B < 60 <2) GEN-OTS-10-004 operated Valve Steam Generator 02 Steam Line Condensate SGS-PL-V036A < 60 <2> GEN-OTS-10-004 Drain Isolation Valve Steam Line Condensate SGS-PL-V036B < 60 <2) GEN-OTS-10-004 Drain Isolation Valve Main Steam Line SGS-PL-V040A <5(^>> SGS-OTS-10-003 Isolation Valve Main Steam Line SGS-PL-V040B <5(^> SGS-OTS-10-004 Isolation Valve Main Feedwater SGS-PL-V057A <5 SGS-OTS-10-003 Isolation Valve Main Feedwater SGS-PL-V057B <5<^> SGS-OTS-10-004 Isolation Valve Startup Feedwater Isolation Motor-operated SGS-PL-V067A < 60 (2) GEN-OTS-10-002 Valve Startup Feedwater Isolation Motor-operated SGS-PL-V067B < 60 <2) GEN-OTS-10-004 Valve Steam Generator Slowdown Isolation SGS-PL-V074A < 60 <2) GEN-OTS-10-004 Valve Steam Generator Slowdown Isolation SGS-PL-V074B < 60 <2> GEN-OTS-10-002 Valve Main Steam Isolation GEN-OTS SGS-PL-V240A < 60 Valve Bypass Isolation 002/-004 Main Steam Isolation GEN-OTS SGS-PL-V240B < 60 <2)

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

U.S. Nuclear Regulatory Commission ND-18-0663 Enclosure Page 8 of 8 Attachment A (con't)

Required Actual Vaive Vaive Closure Test Equipment Name*^* Tag No.<^' 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 < 10 GEN-OTS-10-001 Isolation Valve - ORC Vacuum Relief Containment Isolation A VFS-PL-V800A < 30 GEN-OTS-10-001 MOV-ORC Vacuum Relief Containment Isolation B VFS-PL-V800B s 30 GEN-OTS-10-003 MOV-ORC Fan Coolers Supply Containment Isolation VWS-PL-V058 < 60 <2) VWS-OTS-10-001 Valve-ORC Fan Coolers Return Containment Isolation VWS-PL-V082 < 60 <2) VWS-OTS-10-001 Valve - IRC Fan Coolers Return Containment Isolation VWS-PL-V086 ^ 60 <2) VWS-OTS-10-001 Valve - ORC Sump Discharge Containment Isolation WLS-PL-V055 5 60 <2) GEN-OTS-10-001 Valve - IRC Sump Discharge Containment Isolation WLS-PL-V057 < 60 GEN-OTS-10-004 Valve - ORC Reactor Coolant Drain Tank(RCDT)Gas Outlet WLS-PL-V067 < 60 GEN-OTS-10-001 Containment Isolation Valve - IRC RCDT Gas Outlet Containment Isolation WLS-PL-V068 < 60 <2) GEN-OTS-10-004 Valve - ORC (1) From U3/U4 COL Appendix C.

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