ND-21-0990, ITAAC Closure Notification on Completion of ITAAC Item 2.5.05.04 (Index Number 572)

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ITAAC Closure Notification on Completion of ITAAC Item 2.5.05.04 (Index Number 572)
ML21362A419
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 12/27/2021
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0990
Download: ML21362A419 (7)
v • d • e


Text

Southern Nuclear DEC 2 7 2021 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 Docket No.:

52-025 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 ND-21-0990 10 CFR 52.99(c)(1)

Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC Item 2.5.05.04 [Index Number 5721 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, Testa, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.05.04 [Index Number 572].

This ITAAC confirms Incore Instrumentation System Safety-related displays of the parameters identified in the Combined License (COL) Appendix C Table 2.5.5-1 can be retrieved in the main control room. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) request 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.

aATV Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

MJY/TJC/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.5.05.04 [Index Number 572]

U.S. Nuclear Regulatory Commission ND-21-0990 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKlnney Mr. H. NIeh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J.B. Williams 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. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Requlatorv Commission Ms. M. Bailey M

M 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

. M. King G. Bowman C. P. Patel G. J. Khouri 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 T. Fanelli Ms. K. McCurry J. Parent B. Griman V. Hall

U.S. Nuclear Regulatory Commission ND-21-0990 Page 3 of 3 Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Orlani 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-21-0990 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-21-0990 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.5.05.04 [Index Number 572]

U.S. Nuclear Regulatory Commission ND-21-0990 Enclosure Page 2 of 4 ITAAC Statement Design Commitment

4. Safety-related displays of the parameters identified in Table 2.5.5-1 can be retrieved In the MCR.

Inspections. Tests. Analyses Inspection will be performed for retrievability of the safety-related displays in the MCR.

Acceptance Criteria Safety-related displays identified in Table 2.5.5-1 can be retrieved in the MCR.

ITAAC Determination Basis An inspection was performed to verify the safety-related displays of the parameters identified in the Combined License (COL) Appendix C Table 2.5.5-1 (Attachment A) could be retrieved in the main control room (MCR).

The inspection was performed in accordance with the Unit 3 preoperational test procedure and ITP Work Order listed in Reference 1 for Incore Instrumentation System component indication verifications. The test procedures injected a test signal for core exit temperature (CET) and visually confirmed that when each of the safety-related displays for core exit temperature was summoned at the MCR Protection and Safety Monitoring System (PMS) Visual Display Units (VDUs), the summoned core exit temperature appeared on the PMS VDU.

The Unit 3 test results (Reference 1) confirmed that the VEGP Unit 3 plant parameter safety-related displays listed in Attachment A can be retrieved in the MCR.

Reference 1 is available for NRC inspection as part of Unit 3 ITAAC 2.5.05.04 Completion Package (Reference 2).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of 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 2.5.05.04 (Reference 2) and is available for NRC review.

ITAAC Compietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.5.05.04 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-21-0990 Enclosure Page 3 of 4 References favailabie for NRG inspection)

1. SV3-IIS-ITR-800572, Revision 0, "Unit 3 Incore Instrumentation System: ITAAC 2.5.05.04, Item 4, NRG Index Number: 572"
2. 2.5.05.04-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-21-0990 Enclosure Page 4 of 4 Attachment A MIS Safety-Related Displays in the MGR Table 2.5.5-1

  • Equlpment Name
  • Safety-Related Display Incore Thimble Assemblies (at least three assemblies in each core quadrant)

Core Exit Temperature'^'

(1) Only applies to the safety-related assemblies. There are at least two safety-related assemblies in each core quadrant.

  • Excerpt from COL Table 2.5.5-1
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