ND-22-0201, ITAAC Closure Notification on Completion of ITAAC 2.5.02.08a.ii (Index Number 540)

ITAAC Closure Notification on Completion of ITAAC 2.5.02.08a.ii (Index Number 540)

ML22165A339
Person / Time
Site:	Vogtle
Issue date:	06/14/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.5.02.08a.ii, ND-22-0201
Download: ML22165A339 (9)

Text

A Southern Nuclear Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706 -848-6926 tel JUN 1 4 2022 Docket No.: 52-025 ND-22-0201 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 2.5.02.08a.ii [Index Number 5401 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 2.5.02 .08a.ii [Index Number 5401 , for verifying the Protection and Safety Monitoring System (PMS) provides visual alerts as specified. The closure process for this ITAAC is based on the guidance described in NEl-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 ,

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Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 ITAAC Completion of ITAAC 2.5.02.08a.ii [Index Number 5401 JMC/GES/sfr

U.S. Nuclear Regulatory Commission ND-22-0201 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. D. Pitts Mr. J.B. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M . Coleman Mr. C . T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J.C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01 .02.06 Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C . P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0 . Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C . Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-22-0201 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S.L. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

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

U.S. Nuclear Regulatory Commission ND-22-0201 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-22-0201 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.5.02.0Ba.ii [Index Number 540]

U.S. Nuclear Regulatory Commission ND-22-0201 Enclosure Page 2 of 6 ITAAC Statement Design Commitment 8.a) The PMS provides for the minimum inventory of displays, visual alerts, and fixed position controls, as identified in Table 2.5.2-5. The plant parameters listed with a "Yes" in the "Display" column and visual alerts listed with a "Yes" in the "Alert" column can be retrieved in the MCR.

The fixed position controls listed with a "Yes" in the "Control" column are provided in the MCR .

Inspections/Tests/ Analyses ii) An inspection and test will be performed to verify that the plant parameters are used to generate visual alerts that identify challenges to critical safety functions.

Acceptance Criteria ii) The plant parameters listed in Table 2.5.2-5 with a "Yes" in the "Alert" column are used to generate visual alerts that identify challenges to critical safety functions. The visual alerts actuate in accordance with their correct logic and values.

ITAAC Determination Basis Inspection and testing were performed to verify that the Protection and Safety Monitoring System (PMS) provides visual alerts as identified in Table 2.5.2-5 (Attachment A). The inspection and testing confirmed that the plant parameters listed with a "Yes" in the "Alert" column are used to generate visual alerts that identify challenges to critical safety functions and that these visual alerts actuate in accordance with their correct logic and values.

ITAAC 2.5.02.0Sa.ii was completed by:

• Factory Acceptance Testing - Channel Integration Test and System Integration Test for visual alerts that identify challenges to critical safety functions .

• Site software installation and regression test - Hardware and software integration verification and testing of post system delivery changes .

The Factory Acceptance Testing (FAT) followed the guidance of N El 08-01 (Reference 1)

Section 9.4 fo r the as-built tests to be performed at other than the final installed location. The FAT was performed in accordance with the Software Program Manual for Common Q Systems WCAP-16096 (Reference 2) , AP1000 Protection and Safety Monitoring System Test Plan (Reference 3) , AP1000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Procedure (Reference 4) , and applicable Codes and Standards described in Vogtle 3 and 4 UFSAR Chapter 7 (Reference 11 ).

During the FAT, the plant parameters were simulated and adjusted to create applicable alert conditions , PMS outputs were monitored, and it was confirmed that the visual alerts actuated in accordance with their correct logic and values. This testing was performed in accordance with FAT Test Procedure APP-PMS-T1 P-01 0 (Reference 4) . The results of the PMS testing are documented in the FAT test reports APP-PMS-T2R-01 0 (Reference 5) and SV3-PMS-T2R-150 (Reference 6). The FAT results confirm that the PMS inputs and outputs, logic and installed software functioned correctly to provide for the visual alerts, as identified in Attachment A.

U.S. Nuclear Regulatory Commission ND-22-0201 Enclosure Page 3 of 6 Additional hardware and software installation and associated inspections and testing were performed on-site to verify that the cabinets are intact and functional for applicable Field Change Notification (FCN) AP1000 Vogtle Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1 (Reference 7), implemented by Work Order 1123193 (Reference 8) and 8-GEN-ITPCl-001 (Reference 12), implemented by component testing identified in Reference 13.

References 10 and 12 include steps that confirm and document successful software load and further confirm the physical properties of the as-built PMS. Regression analyses (i.e ., change evaluation) GIC-AP1 000-HEDS-19-001 (Reference 9) was performed post-delivery and installation for hardware changes; software changes were addressed by SV3-PMS-T2R-050 and SV3-PMS-T2R-150 (References 10 and 6) to determine if additional testing was needed for the as-built system.

The completed Unit 3 FAT, FCNs, regression test results, and component testing (References 5-1 0 and 13) confirm that PMS plant parameters listed in Attachment A with a "Yes" in the "Alert" column are used to generate visual alerts that identify challenges to critical safety functions. These results also confirm that visual alerts actuate in accordance with their correct logic and values .

References 2 through 13 are available for NRC inspection as part of the ITAAC 2.5.02.08a.ii Unit 3 Completion Package (Reference 14).

IT AAC 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 were no relevant findings associated with this ITAAC. The review is documented in the ITAAC 2.5.02.08a.ii Completion Package (Reference 14) and is available for NRC review.

IT AAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.5.02.08a.ii 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-22-0201 Enclosure Page 4 of 6 References (available for NRC inspection)

1. NEI 08-01 , Rev 5 - Corrected, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

2. WCAP-16096 "Software Program Manual for Common Q Systems" Revision 4A

3. APP-PMS-T5-001 , Rev. 5, "AP1000 Protection and Safety Monitoring System Test Plan"

4. APP-PMS-T1 P-010, Rev. 5, "AP1000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Procedure"

5. APP-PMS-T2R-010, Rev 0 "AP1000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Report"

6. SV3-PMS-T2R-150-R0 "AP1000 Protection and Safety Monitoring System Integration Test Integrated System Validation Test Report"

7. SV3-GW-GCW-300, Rev 0, Field Change Notice "AP1000 Vogtle Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1 "

8. Work Order 1123193, "(ITAAC) Implement FCN SV3-GW-GCW-300"

9. GIC-AP1 000-HEDS-19-001, Rev. 0 "Regression Testing Analysis for Vogtle Unit 3 Protection and Safety Monitoring System (PMS) Baseline 8.2 to 8.4 Hardware Modifications Performed at Site"

10. SV3-PMS-T2R-050, Rev 0, "Vogtle AP1000 Protection and Safety Monitoring System Channel Integration Test Integrated System Validation Test Report" 11 . Vogtle Electric Generating Plant (VEGP) Units 3 and 4 Updated Final Safety Analysis Report (UFSAR) , Revision 11.0

12. B-GEN-ITPCl -001 , Rev 3, "PMS CABINETS"

13. SV3-PMS Cabinet Diagnostic Testing-001 , Rev 0, "Unit 3 PMS Cabinet Diagnostic Testing for Multiple ITAACs: ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No. 543] , ITAAC 2.5.04.02.i [NRC Index No. 557]"

14. ITAAC 2.5.02.08a.ii-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0201 Enclosure Page 5 of 6 Attachment A

• Excerpt from COL Appendix C Table 2.5.2-5

• Description *Alert(1l Neutron Flux Yes Neutron Flux Doubling Yes Startup Rate Yes Reactor Coolant System (RCS) Pressure Yes Wide-range Cold Leg Temperature Yes RCS Cooldown Rate Compared to the Limit Based on RCS Pressure Yes Wide-range Cold Leg Temperature Compared to the Limit Based on RCS Pressure Yes Change of RCS Temperature by more than 5°F in the last 1O minutes Yes Containment Water Level Yes Containment Pressure Yes Pressurizer Water Level Yes Reactor Vessel-Hot Leg Water Level Yes Core Exit Temperature Yes

1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the main control room, the visual alerts are embedded in the safety-related displays as visual signals.

U.S. Nuclear Regulatory Commission ND-22-0201 Enclosure Page 6 of 6 Attachment A (continued)

• Description *Alert( 1J RCS Subcooling Yes RCS Cold Overpressure Limit Yes I RWST Water Level Yes PRHR Flow Yes PRHR HX Outlet Temperature Yes PRHR HX Inlet Isolation and Control Valve Status Yes IRWST to Normal Residual Heat Removal System (RNS) Suction Valve Status Yes Containment Area High-range Radiation Level Yes

1. These parameters are used to generate visual alerts that identify challenges to the critical safety functions. For the main control room, the visual alerts are embedded in the safety-related displays as visual signals.