ND-21-0632, ITAAC Closure Notification on Completion of 2.1.02.09a (Index Number 41)

ITAAC Closure Notification on Completion of 2.1.02.09a (Index Number 41)

ML21237A509
Person / Time
Site:	Vogtle
Issue date:	08/25/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0632
Download: ML21237A509 (6)

Text

Michael J. Yox 7825 River Road Sk. Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel AU6 2 5 2021 Docket No.: 52-025 ND-21-0632 10 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 2.1.02.09a [Index Number 411 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 2.1.02.09a [Index Number 41]

for verifying Reactor Coolant System post-fuel load flow rate is greater than or equal to 301,670 gpm. 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 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.

Michael J. Yox Regulatory Affairs Dire'ctor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.1.02.09a [Index Number 41]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-21-0632 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKlnney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino 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. 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 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-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. E. Davidson Mr. T. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman

U.S. Nuclear Regulatory Commission ND-21-0632 Page 3 of 3 Qqlethorpe 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 Westinqhouse 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 NU8, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GD8 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-21-0632 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-21-0632 Enclosure Vogtle Electric Generating Piant(VEGP) Unit 3 Completion of ITAAC 2.1.02.09a [Index Number 41]

U.S. Nuclear Regulatory Commission ND-21-0632 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 9.a) The RCS provides circulation of coolant to remove heat from the core.

inspections/Tests/Anaivses Testing and analysis to measure RCS flow with four reactor coolant pumps operating at no-load RCS pressure and temperature conditions will be performed. Analyses will be performed to convert the measured pre-fuel load flow to post-fuel load flow with 10-percent steam generator tube plugging.

Acceptance Criteria The calculated post-fuel load RCS flow rate is ^ 301,670 gpm.

ITAAC Determination Basis Testing was performed in accordance with Unit 3 preoperational test procedure 3-RCS-ITPP-506 (Reference 1) using Work Order 1071744(Reference 2)to confirm that at no-load Reactor Coolant System (RCS) pressure and temperature conditions, the calculated post-fuel load RCS flow rate is s 301,670 gpm with 10-percent steam generator tube plugging.

The testing measured RCS parameters using installed and temporary instrumentation and was trended and recorded using plant computer trends and a high-speed data acquisition system.

When the RCS was at approximately 557°F and 2240 psig with all 4 Reactor Coolant Pumps (RCPs) at 100% speed for a minimum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to ensure thermal stability, the trend data was taken for approximately 10 minutes. This data was analyzed to determine the post-fuel load flow rate with 10-percent steam generator tube plugging. This analysis (Reference 4) was documented and attached to References 1 and 3.

The results of the testing and analysis demonstrate that the Unit 3 RCS flow rate is 312,566 gpm (Reference 4) which confirms the calculated post-fuel load RCS flow rate is s 301,670 gpm.

References 1 through 4 are available for NRC inspection as well as Unit 3 ITAAC 2.1.02.09a Completion Package (Reference 5).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company(SNC) 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 this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.1.02.09a (Reference 5)and is available for NRC review.

U.S. Nuclear Regulatory Commission ND-21-0632 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRG that ITAAC 2.1.02.09a 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.

References(available for NRG inspection)

1. 3-RCS-ITPP-506 Rev. 3.0,"Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional"

2. Work Order 1071744, Rev. 0,"Perform Pre-Op Test 3-RCS-ITPP-506"

3. SV3-RCS-ITR-800041, Rev 0,"Unit 3 Recorded Results of RCS Flow Measurement Test:

ITAAC 2.1.02.09a"

4. SV3-RCS-T2R-5061, Rev. 0,"Vogtle Unit 3 Hot Functional Testing - Reactor Coolant System Flow Summary Report"

5. 2.1.02.09a-U3-CP-Rev0, ITAAC Completion Package