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

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Southern Nuclear SEP 0 6 2019 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket Nos.:

52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-18-0663 10CFR 52.99(c)(3)

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 Equipment Name*^>

Tag No.'2)

Required Valve Closure Time (seconds)

Actual Valve Closure Time (seconds)

Test Procedure Instrument Air Supply Outside Containment Isolation Valve CAS-PL-V014 2

60<2)

CAS-OTS-10-001 Component Cooling Water System (CCS)

Containment Isolation Motor-operated Valve (MOV) -

Inlet Line Outside Reactor Containment (ORC)

CCS-PL-V200 5

60<2)

CCS-OTS-10-001 CCS Containment Isolation MOV -

Outlet Line IRC CCS-PL-V207

< 60 (2)

CCS-OTS-10-001 CCS Containment Isolation MOV -

Outlet Line ORC CCS-PL-V208

< 60 (2)

CCS-OTS-10-001 CVS Letdown Containment Isolation Valve CVS-PL-V045

< 60 <2)

GEN-OTS-10-001 CVS Letdown Containment Isolation Valve CVS-PL-V047 s 60 (2>

GEN-OTS-10-004 CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V090 S 60 <2)

GEN-OTS-10-004 CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V091

< 60 (2)

GEN-OTS-10-001 CVS Zinc Injection Containment Isolation Valve ORC CVS-PL-V092

< 60 <2)

GEN-OTS-10-004 CVS Zinc Injection Containment Isolation Valve IRC CVS-PL-V094

^ 60 <2)

GEN-OTS-10-001 CVS Hydrogen Injection Containment Isolation Valve ORC CVS-PL-V219

^ 60 <2)

GEN-OTS-10-004 Containment Air Sample Containment Isolation Valve Inside Reactor Containment (IRC)

PSS-PL-V008

< 60 (2)

GEN-OTS-10-002 Liquid Sample Line Containment Isolation Valve IRC PSS-PL-V010A

< 60 <2)

GEN-OTS-10-002 Liquid Sample Line Containment Isolation Valve IRC PSS-PL-V010B

^ 60 <2>

GEN-OTS-10-004

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

Equipment Name^^'

Tag No.'^'

Required Valve Closure Time (seconds)

Actual Valve Closure Time (seconds)

Test Procedure Liquid Sample Line Containment Isolation Valve Outside Reactor Containment (ORC)

PSS-PL-V011A

< 60 GEN-OTS-10-003 Liquid Sample Line Containment Isolation Valve ORC PSS-PL-V011B

< 60 (2)

GEN-OTS-10-001 Sample Return Line Containment Isolation Valve ORC PSS-PL-V023

< 60 (2)

GEN-OTS-10-001 Sample Return Containment Isolation Valve IRC PSS-PL-V024

< 60 <2)

GEN-OTS-10-002 Air Sample Line Containment Isolation Valve ORC PSS-PL-V046

< 60 <2' GEN-OTS-10-001 Nitrogen Supply Containment Isolation Valve PXS-PL-V042 S 60 <2>

GEN-OTS-10-004 RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A

< 60 (2)

RNS-OTS-17-004 RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B

< 60 <2)

RNS-OTS-17-004 RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011

^ 60 <2)

GEN-OTS-10-001 RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022

< 60 (2)

GEN-OTS-10-001 RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023

< 60 <2)

GEN-OTS-10-002 RNS Return from Chemical and Volume Control System (CVS)

Containment Isolation Valve RNS-PL-V061

^60<2)

GEN-OTS-10-002 SFS Suction Line Containment Isolation MOV-IRC SFS-PL-V034

< 60 <2)

GEN-OTS-10-002 SFS Suction Line Containment Isolation MOV-ORC SFS-PL-V035

< 60 <2)

GEN-OTS-10-001

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

Equipment Name<^>

Tag No.<2)

Required Valve Closure Time (seconds)

Actual Valve Closure Time (seconds)

Test Procedure SFS Discharge Line Containment Isolation MOV-ORC SFS-PL-V038

< 60 <2)

GEN-OTS-10-001 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A see (2)

GEN-OTS-10-002 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B

< 60 <2)

GEN-OTS-10-004 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A

< 60 <2>

GEN-OTS-10-004 Steam Line Condensate Drain Isolation Valve SGS-PL-V036B

< 60 <2)

GEN-OTS-10-004 Main Steam Line Isolation Valve SGS-PL-V040A

<5(^>>

SGS-OTS-10-003 Main Steam Line Isolation Valve SGS-PL-V040B

<5(^>

SGS-OTS-10-004 Main Feedwater Isolation Valve SGS-PL-V057A

< 5 SGS-OTS-10-003 Main Feedwater Isolation Valve SGS-PL-V057B

<5<^>

SGS-OTS-10-004 Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A

< 60 (2)

GEN-OTS-10-002 Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067B

< 60 <2)

GEN-OTS-10-004 Steam Generator Slowdown Isolation Valve SGS-PL-V074A

< 60 <2)

GEN-OTS-10-004 Steam Generator Slowdown Isolation Valve SGS-PL-V074B

< 60 <2>

GEN-OTS-10-002 Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A

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

< 60 <2)

GEN-OTS 002/-004 Containment Purge Inlet Containment Isolation Valve -

ORC VFS-PL-V003

<10<^>

GEN-OTS-10-001 Containment Purge Inlet Containment Isolation Valve -

IRC VFS-PL-V004

< 10 GEN-OTS-10-004

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

Equipment Name*^*

Tag No.<^'

Required Vaive Closure Time (seconds)

Actual Vaive Closure Time (seconds)

Test Procedure Containment Purge Discharge Containment Isolation Valve -

IRC VFS-PL-V009 GEN-OTS-10-004 Containment Purge Discharge Containment Isolation Valve -

ORC VFS-PL-V010

< 10 GEN-OTS-10-001 Vacuum Relief Containment Isolation A MOV-ORC VFS-PL-V800A

< 30 GEN-OTS-10-001 Vacuum Relief Containment Isolation B MOV-ORC VFS-PL-V800B s 30 GEN-OTS-10-003 Fan Coolers Supply Containment Isolation Valve-ORC VWS-PL-V058

< 60 <2)

VWS-OTS-10-001 Fan Coolers Return Containment Isolation Valve -

IRC VWS-PL-V082

< 60 <2)

VWS-OTS-10-001 Fan Coolers Return Containment Isolation Valve -

ORC VWS-PL-V086

^ 60 <2)

VWS-OTS-10-001 Sump Discharge Containment Isolation Valve -

IRC WLS-PL-V055 5 60 <2)

GEN-OTS-10-001 Sump Discharge Containment Isolation Valve -

ORC WLS-PL-V057

< 60 GEN-OTS-10-004 Reactor Coolant Drain Tank (RCDT) Gas Outlet Containment Isolation Valve -

IRC WLS-PL-V067

< 60 GEN-OTS-10-001 RCDT Gas Outlet Containment Isolation Valve -

ORC WLS-PL-V068

< 60 <2)

GEN-OTS-10-004 (1) From U3/U4 COL Appendix C.

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