ND-22-0290, ITAAC Closure Notification on Completion of ITAAC 2.5.02.06c.i (Index Number 532)

ITAAC Closure Notification on Completion of ITAAC 2.5.02.06c.i (Index Number 532)

ML22129A021
Person / Time
Site:	Vogtle
Issue date:	05/07/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.5.02.06c.i, ND-22-0290
Download: ML22129A021 (7)

Text

A Southern Nuclear May 7, 2022 Docket No.:

52-025 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-22-0290 10 CFR 52.99(c)(1)

ITAAC Closure Notification on Completion of ITAAC 2.5.02.06c.i [Index Number 5321 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 2.5.02.06c.i [Index Number 5321. This ITAAC confirms that the Protection and Safety Monitoring System (PMS) provides manual initiation of reactor trip. The closure process for this IT AAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "Industry Guideline for the IT AAC Closure Process under 10 CFR Part 52," which was 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, r ~

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

JMC /DCH/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.5.02.06c.i [Index Number 5321

U.S. Nuclear Regulatory Commission ND-22-0290 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. 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-22-0290 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-22-0290 Page 1 of 4 Southern Nuclear Operating Company ND-22-0290 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.5.02.06c.i [Index Number 532]

U.S. Nuclear Regulatory Commission ND-22-0290 Page 2 of 4 IT AAC Statement Design Commitment 6.c) The PMS provides manual initiation of reactor trip and selected engineered safety features as identified in Table 2.5.2-4.

Inspections/Tests/ Analyses An operational test of the as-built PMS will be performed using the PMS manual actuation controls.

Acceptance Criteria i) The reactor trip switchgear opens after manual reactor trip controls are actuated.

ITAAC Determination Basis Multiple IT AAC are performed to verify that the Protection and Safety Monitoring System (PMS) provide manual initiation of reactor trip and selected engineered safety features as identified in Combined License (COL) Appendix C, Table 2.5.2-4 (Attachment A). The subject ITAAC performed operational tests of the reactor trip function using the PMS manual actuation controls.

Operational testing was performed in accordance with Unit 3 preoperational test procedures listed in Reference 1 and confirmed that the reactor trip switchgear opened after manual reactor trip controls were actuated.

A preoperational test procedure verified the Reactor Trip Circuit Breakers (RTCBs) were closed.

The reactor trip was then manually actuated at the Primary Dedicated Safety Panel (PDSP) by placing hand switch 3-PMS-HS025, Reactor Trip, in the trip position. Each RTCB was verified to be open locally at the Reactor Trip Switchgear Cabinet, at the Maintenance and Test Panel, and on the Main Control Room displays. Testing was repeated for reactor trip hand switch 3-PMS-HS026. Another preoperational test procedure transferred control from the main control room to the remote shutdown workstation, ensured all RTCBs were closed, then placed the same reactor trip hand switch, 3-PMS-HS025, in the trip position. The RTCBs were then verified open, and the process was repeated for reactor trip hand switch 3-PMS-HS026.

Results of the preoperational testing are documented in Unit 3 preoperational test procedures in Reference 1 and confirm that the reactor trip switchgear opened after manual reactor trip controls were actuated.

Reference 1 is available for NRC inspection as part of Unit 3 ITAAC 2.5.02.06c.i Completion Package (Reference 2).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company performed a review of all IT AAC findings pertaining to the subject IT AAC and associated corrective actions. This review found there were no relevant ITAAC findings associated with the ITAAC. The review documents are included in in the ITAAC Completion Package for ITAAC 2.5.02.06c.i Unit 3 (Reference 2) and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-22-0290 Page 3 of 4 IT AAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.5.02.06c.i was performed for VEGP Unit 3 and that the prescribed acceptance criteria are 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.

References (available for NRC inspection)

1. SV3-PMS-ITR-800532, "Unit 3 PMS Provides Manual Initiation of Reactor Trip, ITAAC 2.5.02.06c.i, NRC Index Number: 532"

2. 2.5.02.06c.i-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0290 Page 4 of 4 Attachment A Table 2.5.2-4 PMS Manually Actuated Functions Reactor Trip Safeguards Actuation Containment Isolation Depressurization System Stages 1, 2, and 3 Actuation Depressurization System Stage 4 Actuation Feedwater Isolation Core Makeup Tank Injection Actuation Steam Line Isolation Passive Containment Cooling Actuation Passive Residual Heat Removal Heat Exchanger Alignment IRWST Injection Containment Recirculation Actuation Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization Steam Generator Relief Isolation Chemical and Volume Control System Isolation Normal Residual Heat Removal System Isolation Containment Vacuum Relief