ND-22-0256, ITAAC Closure Notification on Completion of ITAAC 3.1.00.03 (Index Number 735)

ITAAC Closure Notification on Completion of ITAAC 3.1.00.03 (Index Number 735)

ML22096A314
Person / Time
Site:	Vogtle
Issue date:	04/06/2022
From:	Coleman J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-22-0256
Download: ML22096A314 (7)

Text

Jamie M. Coleman 7 8 25 Rive r R oa d

. Southern Nuclear Regula tory Affa irs Direc to r W a y n es b oro, GA 30 830 Vo gtle 3 & 4 706-848-692 6 tel APR O 6 2022

Docket No.: 52 -025 ND-22-0256 1 O 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 3.1.00.03 (Index Number 735]

Ladies and Gentlemen:

In accordance with 1 O CFR 52.99(c)(1 ), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the complet ion of Vogtle Electric Generating Plant (VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.1.00.03 (Index Number 735].

This ITAAC confirms that selected plant parameters listed in COL Appendix C, Table 2.5.4-1, can be retrieved in the Technical Support Cente r. The closure process for this IT AAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "Industry Guideline for the ITAAC Closure Process Under 1 O 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 1 O CFR 52.99.

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

Respectfully submitted,

~ut~

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enc losure : Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 3. 1.00.03 (Index Number 735]

JMC / RLB / sfr U.S. Nuclear Regula tory Comm ission ND-22 - 0256 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. Mo rrow Mr. K. J. Drudy Mr. J. M. F isher 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

cc:

Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Ve il Mr. C. P. Patel Mr. G. J. Khou ri Mr. C. J. Even Mr. 8. J. Kemker Ms. N. C. Coovert Mr. C. Welch M r. J. Gaslev ic Mr. 0. Lopez-Sant iago Mr. G. Armstrong Mr. M. Webb Mr. T. F redette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. T. Fanelli Ms. K. Mccu rry Mr. J. Parent Mr. B. Griman Mr. V. Hall U.S. Nuclear Regulatory Commiss ion ND-22-0256 Page 3 of 3

Oglethorpe Powe r Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

Municipal Electric Authority o f 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-22-0256 Enclosure Page 1 of 4

Southern Nuclear Operating Company ND-22-0256 Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 3.1.00.03 [Index Number 735]

U.S. Nuclear Regulatory Commission ND-22-0256 Enclosure Page 2 of 4

ITAAC Statement

Design Commitment

3. The plant parameters listed in Table 2.5.4-1, minimum inventory table, in subsection 2.5.4, DDS, with a "Yes" in the "Display" column, can be retrieved in the TSC.

Inspections / Tests/ Analyses

An inspection will be performed for retrievability of the plant parameters in the TSC.

Acceptance Criteria

The plant parameters listed in Table 2.5.4-1, minimum inventory table, in subsection 2.5.4,

DDS, with a "Yes" in the "Display" column, can be retrieved in the TSC.

ITAAC Determination Basis

An inspection was performed to verify the retrievability of the VEGP Unit 3 plant parameters in the Technical Support Center (TSC). The inspection for retrievability confirmed that the plant parameters listed in COL Appendix C Table 2.5.4-1, Minimum Inventory of Controls, Displays, and Alerts at the RSW, with a "Yes" in the " Display" column (Attachment A) can be retrieved in the TSC.

The inspection was performed as described in ITAAC Technical Report SV3-ERO-ITR-800735 (Reference 1 ), and visually confirmed that when each of the plant parameters identified in Attachment A was summoned at a workstation connected to the TSC Local Area Network (Enterprise Data System) the summoned plant parameter appeared on a display monitor at that TSC workstation.

The inspection results are documented in Reference 1 and confirmed that the VEGP Unit 3 plant parameters listed in Attachment A can be retrieved in the TSC.

Reference 1 is available for NRG Inspection as part of the Unit 3 ITAAC 3. 1.00.03 Completion Package (Reference 2).

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 were no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.1.00.03 (Reference 2) and is available for NRG review.

ITAAC Completion Statement

Based on the above information, SNC hereby notifies the NRG that ITAAC 3. 1.00.03 was performed for VEGP Unit 3 and that the prescribed acceptance criteria was 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-22-0256 Enclosure Page 3 of 4

References (available for NRC inspection)

1. SV3-ERO-ITR-800735, Unit 3 ITAAC 735 Displays: ITAAC 3.1.00.03, Rev 0

2. 3.1.00.03-U3-CP-Rev0, ITAAC Completion Package U.S. Nuclear Regulatory Commission ND-22-0256 Enclosure Page 4 of 4

Attachment A

Minimum Inventory of Controls, Displays, and Alerts at the RSW*

Description. Display

• Neutron Flux Yes Startup Rate Yes Reactor Coolant System (RCS) Pressure Yes Wide-ranae Hot Lea Temperature Yes Wide-ranae Cold Lea 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 Yes RCS Pressure Containment Water Level Yes Containment Pressure Yes Pressurizer Water Level Yes Pressurizer Water Level Trend Yes Pressurizer Reference Lea Temperature Yes Reactor Vessel-Hot Leq Water Level Yes Pressurizer Pressure Yes Core Exit Temperature Yes RCS Subcoolina Yes RCS Cold Overpressure Limit Yes In-containment Refuelinq Water Storaqe Tank (IRWST) Water Level Yes Pass ive Residual Heat Removal (PRHR) Flow Yes PRHR HX Outlet Temperature Yes PRHR HX Inlet Isolation and Control Valve Status Yes Passive Containment Cooling System (PCS) Storage Tank Water Yes Level PCS Cooling Flow Yes IRWST to Normal Residual Heat Removal System (RNS) Suction Yes Valve Status Remotely Operated Containment Isolation Valve Status Yes Containment Area Hiah-ranae Radiation Level Yes Containment Pressure (Extended Ranqe) Yes Core Makeup Tank (CMT) Level Yes

• Excerpt from COL Table 2.5.4-1