ND-20-0902, ITAAC Closure Notification on Completion of ITAAC 2.2.01.07.ii (Index Number 108)

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ITAAC Closure Notification on Completion of ITAAC 2.2.01.07.ii (Index Number 108)
ML21252A736
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 09/09/2021
From: Yox M
Southern Nuclear Company
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.2.01.07.ii, ND-20-0902
Download: ML21252A736 (11)
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Text

Michael J. Yox 7325 River Road SOUtnGrn NUClGSr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel SEP 0 9 2021 Docket No.:

52-025 ND-20-0902 10 CFR 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 ITAAC Closure Notification on Completion of ITAAC 2.2.01.Oy.ii [index Number 1081 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 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.07.ii [Index Number 108], for verifying that remotely operated containment isolation valves close within the required response times. The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52", which is 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 Kelli Roberts at 706-848-6991.

Respectfully submitted, Michael J. Yoi^

Regulatory Affairs Dicfector Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.01.07.

[Index Number 108]

MJY/TJC/sfr

U.S. Nuclear Regulatory Commission ND-20-0902 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M. Fisher Mr. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil M

M M

M Ms. N. C. Coovert M

M M

M M

M M

M M

M M

M M

M C. P. Patel G. J. Khourl C. J. Even B. J. Kemker C. Welch J. Gaslevic O. Lopez-Santiago G. Armstrong M. Webb T. Fredette C. Santos B. Davis J. Vasquez J. Eargle E. Davidson T. Fanelll Ms. K. McCurry J. Parent B. Griman

U.S. Nuclear Regulatory Commission ND-20-0902 Page 3 of 3 Qqlethcrpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani Mr. D. 0. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-20-0902 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-20-0902 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.01.07.11 [Index Number 108]

U.S. Nuclear Regulatory Commission ND-20-0902 Enclosure Page 2 of 8 ITAAC Statement Design 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.

I nspections/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-PL-V003, -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 Determination Basis Multiple ITAAC were 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 was performed to demonstrate that remotely operated containment isolation valves close within the required response times. The containment purge isolation valves (VFS-PL-V003, -V004, -V009, and -V010) close within 10 seconds, containment vacuum relief isolation valves (VFS-PL-V800A and -V800B) close within 30 seconds, steam generator system valves SGS-PL-V040A/B and SGS-PL-V057A/B are covered in the Combined License (COL) Appendix C (Reference 1) 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&4 Updated Final Safety Analysis Report (UFSAR)

(Reference 2) Table 6.2.3-1 identifies all remotely operated containment isolation valves.

Testing was performed in accordance with Unit 3 component test packages listed in References 3 through 13 to verify Containment isolation valve closure times.

Work orders listed in References 3 through 13 establish initial conditions with each Containment isolation valve in the open position. An actuation signal was 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 signal is generated until the valve is fully closed. The Containment isolation valve is verified locally closed by a person located at the valve.

U.S. Nuclear Regulatory Commission ND-20-0902 Enclosure Page 3 of 8 The completed Unit 3 component test results (References 3 through 13) confirm the containment purge isolation valves (VFS-PL-V003, -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 1 l.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&4 Updated Final Safety Analysis Report (UFSAR) Table 6.2.3-1 and COL Appendix C.

References 3 through 13 are available for NRC inspection as part of ITAAC 2.2.01.07.ii Unit 3 Completion Package (Reference 14).

ITAAC Finding Review 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. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.01.07.11 (Reference 14) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.07.11 was performed for VEGP Unit 3 and that the prescribed acceptance criteria were 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.

U.S. Nuclear Regulatory Commission ND-20-0902 Enclosure Page 4 of 8 References (available for NRG inspection)

1. Combined License Vogtle Electric Generating Plant Unit 3 Appendix C Amendment 186
2. VEGP 3&4 UFSAR Rev. 10 Table 6.2.3-1
3. SV3-CNS-ITR-800108, Rev. 0, "Unit 3 Compilation of CAS Containment Isolation Valve Testing: ITAAC 2.2.01.07.ii NRC Index Number 108"
4. SV3-CNS-ITR-801108, Rev. 0, "Unit 3 Compilation of CCS Containment Isolation Valve Testing: ITAAC 2.2.01.07.11 NRC Index Number 108"
5. SV3-CNS-ITR-802108, Rev. 1, "Unit 3 Compilation of CVS Containment Isolation Valve Testing: ITAAC 2.2.01.07.ii NRC Index Number 108"
6. SV3-CNS-ITR-803108, Rev. 0, "Unit 3 Compilation of PSS Containment Isolation Valve Testing: ITAAC 2.2.01.07.ii NRC Index Number 108"
7. SV3-CNS-ITR-804108, Rev. 0, "Unit 3 Compilation of PXS Containment Isolation Valve Testing: ITAAC 2.2.01.07.11 NRC Index Number 108"
8. SV3-CNS-ITR-805108, Rev. 0, "Unit 3 Compilation of RNS Containment Isolation Valve Testing: ITAAC 2.2.01.07.ii NRC Index Number 108"
9. SV3-CNS-ITR-806108, Rev. 0, "Unit 3 Compilation of SFS Containment Isolation Valve Testing: ITAAC 2.2.01.07.11 NRC Index Number 108"
10. SV3-CNS-ITR-807108, Rev. 0, "Unit 3 Compilation of SGS Containment Isolation Valve Testing: ITAAC 2.2.01.07.ii NRC Index Number 108"
11. SV3-CNS-ITR-808108, Rev. 0, "Unit 3 Compilation of VFS Containment Isolation Valve Testing: ITAAC 2.2.01.07.11 NRC Index Number 108"
12. SV3-CNS-ITR-809108, Rev. 0, "Unit 3 Compilation of VWS Containment Isolation Valve Testing: ITAAC 2.2.01.07.11 NRC Index Number 108"
13. SV3-CNS-ITR-810108, Rev. 0, "Unit 3 Compilation of WLS Containment Isolation Valve Testing: ITAAC 2.2.01.07.11 NRC Index Number 108"
14. 2.2.01.07.ii-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-20-0902 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

< 60 1

CAS-OTS-10-001 B-GEN-ITPCI-039-F003 Component Cooling Water System (CCS)

Containment Isolation Motor-operated Valve (MOV) -

Inlet Line Outside Reactor Containment (ORC)

CCS-PL-V200

< 60 32 B-GEN-ITPCI-039-F004 CCS Containment Isolation MOV -

Outlet Line IRC CCS-PL-V207 o

DC IV 31 B-GEN-ITPCI-039-F005 CCS Containment Isolation MOV -

Outlet Line ORC CCS-PL-V208

< 60 32 B-GEN-ITPCI-039-F006 CVS Letdown Containment Isolation Valve CVS-PL-V045

< 60 23 B-GEN-ITPCI-039-F010 CVS Letdown Containment Isolation Valve CVS-PL-V047

< 60 13 B-GEN-ITPCI-039-F011 CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V090

< 60 (< 30) <2) 14 B-GEN-ITPCI-039-F013 CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V091

^ 60 30) 13 B-GEN-ITPCI-039-F014 CVS Zinc Injection Containment Isolation Valve ORC CVS-PL-V092 o

DC IV 4

GEN-OTS-10-004 B-GEN-ITPCI-039-F015 CVS Zinc Injection Containment Isolation Valve IRC CVS-PL-V094

< 60 6

GEN-OTS-10-001 B-GEN-ITPCI-039-F016 CVS Hydrogen Injection Containment Isolation Valve ORC CVS-PL-V219

< 60 8

GEN-OTS-10-004 B-GEN-ITPCI-039-F019 Containment Air Sample Containment Isolation Valve Inside Reactor Containment (IRC)

PSS-PL-V008

< 60

< 1 B-GEN-ITPCI-039-F061 Liquid Sample Line Containment Isolation Valve IRC PSS-PL-V010A S 60 1

B-GEN-ITPCI-039-F062 Liquid Sample Line Containment Isolation Valve IRC PSS-PL-V010B S 60

< 1 B-GEN-ITPCI-039-F063

U.S. Nuclear Regulatory Commission ND-20-0902 Enclosure Page 6 of 8 Attachment A (cent.)

Equipment Name^^'

Tag 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 (1) 7 B-GEN-ITPCI-039-F064 Liquid Sample Line Containment Isolation Valve ORC PSS-PL-V011B

< 60 (1) 6 B-GEN-ITPCI-039-F065 Sample Return Line Containment Isolation Valve ORC PSS-PL-V023

< 60 3

B-GEN-ITPCI-039-F066 Sample Return Containment Isolation Valve IRC PSS-PL-V024

< 60

< 1 B-GEN-ITPCI-039-F067 Air Sample Line Containment Isolation Valve ORC PSS-PL-V046

< 60 5

B-GEN-ITPCI-039-F068 Nitrogen Supply Containment Isolation Valve PXS-PL-V042

< 60 4

GEN-OTS-10-004 B-GEN-ITPCI-039-F077 RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A

< 60 <1) 29 B-GEN-ITPCI-039-F171 RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B

< 60 (1) 30 B-GEN-ITPCI-039-F172 RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011

< 60 29 B-GEN-ITPCI-039-F173 RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022

< 60 (1) 24 B-GEN-ITPCI-039-F174 RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023

< 60 (1) 29 B-GEN-ITPCI-039-F175 RNS Return from Chemical and Volume Control System (CVS)

Containment Isolation Valve RNS-PL-V061

< 60 4

GEN-OTS-10-002 B-GEN-ITPCI-039-F176 SFS Suction Line Containment Isolation MOV-IRC SFS-PL-V034

< 60 17 B-GEN-ITPCI-039-F179 SFS Suction Line Containment Isolation MOV -

ORC SFS-PL-V035

< 60 17 B-GEN-ITPCI-039-F180

U.S. Nuclear Regulatory Commission ND-20-0902 Enclosure Page 7 of 8 Attachment A (cent.)

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 14 B-GEN-ITPCI-039-F181 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A

<44(1) 20 B-GEN-ITPCI-039-F182 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B

<44(1) 22 B-GEN-ITPCI-039-F183 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A

< 60 C) 4 B-GEN-ITPCI-039-F184 Steam Line Condensate Drain Isolation Valve SGS-PL-V036B o

DC VI 5

B-GEN-ITPCI-039-F185 Main Steam Line Isolation Valve SGS-PL-V040A 4.231 B-GEN-ITPCI-039-F186-189 Main Steam Line Isolation Valve SGS-PL-V040B 4.604 B-GEN-ITPCI-039-F190-193 Main Feedwater Isolation Valve SGS-PL-V057A 4.357 B-GEN-ITPCI-039-F194-197 Main Feedwater Isolation Valve SGS-PL-V057B

<5(1) 4.35 B-GEN-ITPCI-039-F198-201 Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A

< 60 (1) 28 B-GEN-iTPCI-039-F202 Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067B

< 60 (1) 28 B-GEN-ITPCI-039-F203 Steam Generator Slowdown Isolation Valve SGS-PL-V074A

< 60 (1) 8 B-GEN-ITPCI-039-F204 Steam Generator Slowdown Isolation Valve SGS-PL-V074B

< 60 (1) 7 B-GEN-ITPCI-039-F205 Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A

< 60 C) 7 B-GEN-ITPCI-039-F212-213

U.S. Nuclear Regulatory Commission ND-20-0902 Enclosure Page 8 of 8 Attachment A (cont.)

Equipment Name(^>

Tag No.<2)

Required Valve Closure Time (seconds)

Actual Valve Closure Time (seconds)

Test Procedure Main Steam Isolation Valve Bypass Isolation SGS-PL-V240B

< 60 6

B-GEN-ITPCI-039-F214-215 Containment Purge Inlet Containment Isolation Valve -

ORC VFS-PL-V003 2

B-GEN-ITPCI-039-F234 Containment Purge Inlet Containment Isolation Valve -

IRC VFS-PL-V004 2

B-GEN-ITPCI-039-F235 Containment Purge Discharge Containment Isolation Valve -

IRC VFS-PL-V009

<10(1) 3 B-GEN-ITPCI-039-F236 Containment Purge Discharge Containment Isolation Valve -

ORC VFS-PL-V010

< 10(1) 2 B-GEN-ITPCI-039-F237 Vacuum Relief Containment Isolation AMOV-ORC VFS-PL-V800A O

CO IV 18 B-GEN-ITPCI-039-F238 Vacuum Relief Containment Isolation B MOV -

ORC VFS-PL-V800B

< 30 (1) 19 B-GEN-ITPCI-039-F239 Fan Coolers Supply Containment Isolation Valve -

ORC VWS-PL-V058

< 60 (1) 2 B-GEN-ITPCI-039-F240 Fan Coolers Return Containment Isolation Valve -

IRC VWS-PL-V082

< 60 (1) 2 B-GEN-ITPCI-039-F241 Fan Coolers Return Containment Isolation Valve -

ORC VWS-PL-V086

< 60 (1) 2 B-GEN-ITPCI-039-F242 Sump Discharge Containment Isolation Valve -

IRC WLS-PL-V055 5 60 (1) 2 B-GEN-ITPCI-039-F243 Sump Discharge Containment Isolation Valve -

ORC WLS-PL-V057

< 60 (1) 2 B-GEN-ITPCI-039-F244 Reactor Coolant Drain Tank (RCDT) Gas Outlet Containment Isolation Valve -

IRC WLS-PL-V067 o

DC IV 7

B-GEN-ITPCI-039-F245 RCDT Gas Outlet Containment Isolation Valve -

ORC WLS-PL-V068

< 60 (1) 10 B-GEN-ITPCI-039-F246 From U3 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 tfie minimum value listed.

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