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MONTHYEARND-21-0973, Vogtie Electric Generating Plant, Unit 3, ITAAC Closure Notification on Completion of Item 2.3.06.05a.i (Index Number 361)2021-10-29029 October 2021 Vogtie Electric Generating Plant, Unit 3, ITAAC Closure Notification on Completion of Item 2.3.06.05a.i (Index Number 361) Project stage: Request ML21342A2922021-11-0202 November 2021, 9 December 2021 Update to Targeted Inspections, Tests, Analyses, and Acceptance Criteria for Vogtle Electric Generating Plant Unit 3 and 4 Project stage: Request ND-21-0982, ITAAC Closure Notification on Completion of Item 2.3.13.05.1 (Index Number 462)2021-11-0303 November 2021 ITAAC Closure Notification on Completion of Item 2.3.13.05.1 (Index Number 462) Project stage: Request ND-21-0992, ITAAC Closure Notification on Completion of Item 3.3.00.10.i (Index Number 815)2021-11-0404 November 2021 ITAAC Closure Notification on Completion of Item 3.3.00.10.i (Index Number 815) Project stage: Request ND-21-0377, ITAAC Closure Notification on 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Southern Nuclear Jamie M. Coleman Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel Docket No.: 52-025 ND-22-0262 10 CFR 52.99(c)(1)
APR 0 7 2022 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.5.02.09d [Index Number 5481 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 Vogtie Electric Generating Plant (VEGP)
Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.02.09d [Index Number 548] for verifying that the Protection and Safety Monitoring System (PMS) provides the interlock functions identified in Table 2.5.2-7. 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 A. Roberts at 706-848-6991.
Respectfully submitted.
Jamie M. Coleman Regulatory Affairs Director Vogtie 3 & 4 Vogtie Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.5.02.09d [Index Number 548]
Enclosure:
JMC/JTK/sfr
U.S. Nuclear Regulatory Commission ND-22-0262 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena II I Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino 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. Lelghty 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 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. O. Lopez-Santlago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman Mr. V. Hall
U.S. Nuclear Regulatory Commission ND-22-0262 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., CDS Associates, Inc.
Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Batch Bingham
U.S. Nuclear Regulatory Commission ND-22-0262 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-22-0262 Enclosure Vogtie Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.5.02.09d [Index Number 548]
U.S. Nuclear Regulatory Commission ND-22-0262 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 9.d) The PMS provides the interlock functions identified in Table 2.5.2-7.
Inspections/Tests/Anaivses An operational test of the as-built PMS will be performed using real or simulated test signals.
Acceptance Criteria Appropriate PMS output signals are generated as the interlock conditions are changed.
ITAAC Determination Basis Testing was performed to verify that the Protection and Safety Monitoring System (PMS) provides interlock functions identified in Combined License Appendix C Table 2.5.2-7 (Attachment A).
ITAAC 2.5.02.09d is completed as a combination of:
G Factory Acceptance Test -
Functional testing of interlocks G
Site software instaiiation and regression test - Hardware and software integration verification and testing of post system delivery changes The Factory Acceptance Testing (FAT) foliows the guidance of NEI 08-01 Section 9.4 (Reference 15) for the as-built tests to be performed at other than the final installed location.
The FAT was performed in accordance with PMS Software Program Manual WCAP-16096 (Reference 1), PMS Test Plan APP-PMS-T5-001 (Reference 2) and applicable Codes and Standards described in Vogtie 3 and 4 Updated Final Safety Analysis Report (UFSAR) Chapter 7
(Reference 3).
The FAT included testing of PMS inputs and outputs, logic, and functionality. During this test, the initial condition for the test scenarios was established and confirmed that the interlocks actuate as appropriate for the interlocks described in Vogtie 3 and 4 UFSAR Chapter 7, Section 7.6. During the test, the process parameters were simulated and adjusted to create applicable interlock conditions, PMS outputs were monitored, and it was confirmed that the interlocks work as designed, in accordance with PMS Channel Integration Test procedures APP-PMS-T1 P-008 and APP-PMS-T1 P-009 (References 4 and 5). The results of the testing are documented in the FAT test reports APP-PMS-T2R-008 and APP-PMS-T2R-009 (References 6 and 7).
U.S. Nuclear Regulatory Commission ND-22-0262 Enclosure Page 3 of 5 Additional hardware and software installation and associated inspections and testing performed on-site to verify that the cabinets are intact and functional in accordance with Unit 3 PMS Initial Software Installation documented in SV3-PMS Cabinet Software Loading-001 (Reference 10) performed by Work Order 1123193 (Reference 8), and Cabinet Diagnostics documented in SV3-PMS-ITR-800548 (Reference 14). References 8 through 11 include steps that confirm and document successful software load and further confirm the physical properties of the as-built PMS. A regression analysis (i.e., change evaluation) was performed for hardware changes and software changes (References 12 and 13) and determined that no additional testing is needed for the as-built system.
The completed Unit 3 FAT (References 4 through 7), Software Installation (Reference 8),
Regression test results (References 12 and 13) and Cabinet Diagnostics (Reference 14) confirm that appropriate PMS output signals are generated as the interlock conditions changed.
References 1 through 14 are available for NRC inspection as part of the ITAAC 2.5.02.09d Unit 3 Completion Package (Reference 16).
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 2.5.02.09d (Reference 16) and is available for NRC review.
ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.5.02.09d performed for VEGP Unit 3 and 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.
were are was
U.S. Nuclear Regulatory Commission ND-22-0262 Enclosure Page 4 of 5 References (available for NRC inspection)
- 1. WCAP-16096 Software Program Manual for Common Q Systems Revision 4A
- 2. APP-PMS-T5-001 AP1000 Protection and Safety Monitoring System Test Plan
- 3. Vogtie U3 and U4 UFSAR Rev 10.1 Chapter 7
- 4. APP-PMS-T1 P-008, Rev 3 API 000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Procedure
- 5. APP-PMS-T1 P-009, Rev 7 API 000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Procedure
- 6. APP-PMS-T2R-008, Rev 1, API000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Report
- 7. APP-PMS-T2R-009, Rev 0, API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Report
- 8. Work Order 1123193, (ITAAC) Implement FCN SV3-GW-GCW-300
- 9. SV3-GW-GCW-300, Rev 0, Field Change Notice API 000 Vogtie Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1
- 10. SV3-PMS Cabinet Software Loading-001, Rev 0 Unit 3 Software Loading for PMS Cabinets for Multiple ITAACs
- 11. B-GEN-ITPCI-001-011 Revs 1.1 & 1.2, PMS CABINETS - Cabinet Diagnostics
- 12. GIC-AP1000-HEDS-19-001, Rev. 0 Regression Testing Analysis for Vogtie Unit 3 Protection and Safety Monitoring System (PMS) Baseline 8.2 to 8.4 Flardware Modifications Performed at Site
- 13. SV3-PMS-T2R-050, Rev 0, Vogtie API 000 Protection and Safety Monitoring System Fuel Load Regression Test Report
- 14. SV3-PMS-ITR-800548 Rev 0, Unit 3 PMS Cabinet Diagnostic Testing: ITAAC 2.5.02.09d
- 15. NEI 08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52
- 16. ITAAC 2.5.02.09d-U3-CP-Rev0, ITAAC Completion Package
U.S. Nuclear Regulatory Commission ND-22-0262 Enclosure Page 5 of 5 Attachment A COL Appendix C Table 2.5.2-7 Table 2.5.2-7 PMS Interlocks RNS Suction Valves PRHR Heat Exchanger Inlet Isolation Valve CMT Cold Leg Balance Line Isolation Valves Containment Vacuum Relief Isolation Valves