ND-21-1063, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.01.03e (Index Number 515)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.01.03e (Index Number 515)

ML21344A193
Person / Time
Site:	Vogtle
Issue date:	12/10/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-1063
Download: ML21344A193 (8)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel myox@southsrnco.com DEC 1 0 2021 Docket No.: 52-026 ND-21-1063 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 Notice of Uncompleted ITAAC 225-clavs Prior to Initial Fuel Load Item 2.5.01.03e [Index Number 5151 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of December 10, 2021, Vogtle Electric Generating Plant(VEGP) Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.01.03e [Index Number 515]

has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

Southern Nuclear Operating Company(SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.5.01.03e [Index Number 515] ND-19-0302

[ML19106A221], dated April 16, 2019. This resubmittal addresses changes made to ITAAC by Amendment 186 to the Vogtle Electric Generating Plant(VEGP) Unit 4 Combined License (COL) and supersedes ND-19-0302 for Unit 4.

This notification is informed by the guidance described in 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

U.S. Nuclear Regulatory Commission ND-21-1063 Page 2 of 4 Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC 2.5.01.03e [Index Number 515]

MJY/TJC/sfr

U.S. Nuclear Regulatory Commission ND-21-1063 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney 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. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Reoulatorv Commission Ms. M. Bailey M . M. King M G. Bowman Ms. A. Veil M . C. P. Patel M G. J. Khouri M . C. J. Even M B. J. Kemker Ms. N. C. Coovert M C. Welch M J. Gaslevic M O. Lopez-Santiago M G. Armstrong M M. Webb M T. Fredette M C. Santos M B. Davis M J. Vasquez M J. Eargle M T. Fanelli Ms. K. McCurry M . J. Parent M . B. Griman M . V. Hall

U.S. Nuclear Regulatory Commission ND-21-1063 Page 4 of 4 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. OrianI Mr. D. C. 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., GDS Associates, inc.

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

U.S. Nuclear Regulatory Commission ND-21-1063 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-21-1063 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion Plan for Uncompleted ITAAC 2.5.01.03e [Index Number 515]

U.S. Nuclear Regulatory Commission ND-21-1063 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 3.e) The sensors identified on Table 2.5.1-3 are used for DAS input and are separate from those being used by the RMS and plant control system.

Inspections. Tests. Analyses Inspection of the as-built system will be performed except for the core exit temperature sensor installation.

Acceptance Criteria The sensors identified on Table 2.5.1-3 are used by DAS and are separate from those being used by the RMS and plant control system.

ITAAC Completion Description Inspection of the as-built Diverse Actuation System (DAS) is performed to demonstrate that the sensors identified in Combined License (COL) Appendix C Table 2.5.1-3(Attachment A), except for the core exit temperature sensor installation, are used for DAS input and are separate from those being used by the Protection and Safety Monitoring System (RMS)and plant control system (RLS). Inspection of the core exit temperature sensors is performed to demonstrate that the sensors are used for DAS input and are separate from those being used by the RMS and RLS.

The DAS System Specification Document(Reference 1) requires that the sensors identified in Attachment A be used for DAS input and are separate and independent from the sensor inputs in the RMS and plant control system. Construction drawing SV4-DAS-J0-001,(Reference 2),

illustrates the DAS sensor flow and indication architecture. An inspection of construction drawings and completed construction records is performed in accordance with SV4-DAS-ITR-800515(Reference 3), to confirm that the sensors identified in Attachment A are installed, except for the core exit temperature sensor installation, per the DAS sensor input requirements of Reference 1 and are separate from those being used by the RMS and plant control system.

The inspection of the DAS Core Exit Temperature sensors is performed using a combination of methods in accordance with Reference 3. This includes inspections of plant drawings and quality release and certificate of conformance records to ensure the Core Exit Temperature sensors designated for DAS are separate from those being used by the RMS and RLS.

The inspection results are documented in Reference 3 and confirm that the sensors identified in Attachment A are used by DAS and are separate from those being used by the RMS and plant control system.

References 1 through 3 are available for NRC inspection as part of the Unit 4 ITAAC 2.5.01.03e Completion Rackage (Reference 4).

U.S. Nuclear Regulatory Commission ND-21-1063 Enclosure Page 3 of 4 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with the ITAAC.

References favaiiabie for NRG inspection)

1. SV4-DAS-J4-001,"AP1000 Diverse Actuation System System Design Specification",

Revision 3

2. SV4-DAS-J0-001,"AP 1000 Diverse Actuation System (DAS)Sensor Flow and indication Architecture", Revision 1

3. SV4-DAS-ITR-800515,"Unit 4 Inspection Results of Diverse Actuation System (DAS)

Sensor Hardware Diversity: ITAAC 2.5.01.03e NRC Index Number: 515", Revision 0

4. 2.5.01.03e-U4-CP-Rev0,"ITAAC Completion Package"

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

Revision 5 - Corrected

U.S. Nuclear Regulatory Commission ND-21-1063 Enclosure Page 4 of 4 Attachment A

'Excerpt from COL Table 2.5.1-3

• Equipment Name *Tag Number Reactor Coolant System (RCS) Hot Leg Temperature RCS-300A RCS Hot Leg Temperature RCS-300B Steam Generator 1 Wide-range Level SGS-044 Steam Generator 1 Wide-range Level SGS-045 Steam Generator 2 Wide-range Level SGS-046 Steam Generator 2 Wide-range Level SGS-047 Pressurlzer Water Level RCS-305A Pressurizer Water Level RCS-305B Containment Temperature VCS-053A Containment Temperature VCS-053B Core Exit Temperature IIS-009 Core Exit Temperature IIS-013 Core Exit Temperature IIS-030 Core Exit Temperature IIS-034 Rod Control Motor Generator Voltage PLS-001 Rod Control Motor Generator Voltage PLS-002