ML20126G499

Unit 4, Notice of Revised Uncompleted ITAAC Item 2.2.03.08b.01 (Index Number 175)

ML20126G499
Person / Time
Site:	Vogtle
Issue date:	05/05/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.2.03.08b.01
Download: ML20126G499 (7)

Text

^Southern Nuclear Michael J, Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel MAY 0 5 2020 Docket Nos.: 52-025 52-026 ND-20-0490 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washiington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Revised Uncompleted ITAAC Item 2.2.03.08b.01 [Index Number 1751 Ladies and Gentlemen:

Southern Nuclear Operating Company(SNC) hereby provides the NRC with a revised Notice of Uncompleted ITAAC for Item 2.2.03.08b.01 [Index Number 175]. This revised notice is being submitted to incorporate the recently approved Amendment 177 (Vogtle Electric Generating Plant(VEGP) Unit 3) and Amendment 176(VEGP Unit 4)for License Amendment Request (LAR)19-017.

The Notice of Uncompleted ITAAC for ITAAC 175 was previously submitted on October 31, 2019 (ND-19-1244, reference ML19305A232) while LAR-19-017 was pending before the NRC (reference ML19249C739). In the October 31, 2019 notice, SNC specifically stated its intent to resubmitthe Notice of Uncompleted ITAAC for ITAAC 175 upon NRC approval of Amendments 177/176.

Amendments 177/176 modify ITAAC 175 by replacing the passive residual heat removal (PRHR) heat exchanger natural circulation test with the PRHR heat exchanger forced flow test.

The NRC published notice of Amendments 177/176 in the Federal Register on February 11, 2020, providing an opportunity for comments and hearing requests (85 FR 7796). No comments or hearing requests were submitted. Amendments 177/176 were subsequently approved by the NRC on March 20, 2020(85 FR 16146).

This submittal supersedes the October 31, 2019 Notice of Uncompleted ITAAC for ITAAC 175 (ND-19-1244) in its entirety and incorporates the changes implemented by Amendments 177/176.

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director i'ogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-20-0490 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08b.01 [Index Number 175]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-20-0490 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKlnney (w/o enclosures)

Mr. M. D. Meier (w/o enclosures)

Mr. D. H. Jones (w/o enclosures)

Mr. G. Chick Mr. M. Page Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow 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 cc:

Nuclear Regulatory Commission M . W. Jones(w/o enclosures)

M C. P. Patel M G. J. Khouri Ms. S. E. Temple M . N. D. Karlovich M . A. Lerch M . C. J. Even M 8. J. Kemker Ms. N. C. Coovert M . C. Welch M . J. Gaslevic M . V. Hall M . G. Armstrong Ms. T. Lamb M M. Webb M T. Fredette M C. Weber M S. Smith M C. Santos M s. M. Bailey M S. Rose M . B. Davis M . J. Vasquez M . J. Eargle Ms. K. Carrington

U.S. Nuclear Regulatory Commission ND-20-0490 Page 4 of 4 Mr. P. Heher Mr. M. King Mr. E. Davidson Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-20-0490 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-0490 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Pian for Uncompleted ITAAC 2.2.03.08b.01 [Index Number 175]

U.S. Nuclear Regulatory Commission ND-20-0490 Enclosure Page 2 of 3 ITAAC Statement Desian Commitment:

8.b) The PXS provides core decay heat removal during design basis events.

inspection. Tests. Anaivses:

1. A heat removal performance test and analysis of the PRHR HX will be performed to determine the heat transfer from the HX. For the test, the reactor coolant hot leg temperature will be initially at s 350°F with the reactor coolant pumps running. The IRWST water level for the test will be above the top of the HX. The test will continue until the hot leg temperature is

< 250°F.

Acceptance Criteria:

1. A report exists and concludes that the PRHR HX heat transfer rate with the design basis number of PRHR HX tubes plugged is:

s 8.46 X 10^ Btu/hr with 250°F HL Temp and an initial IRWST temperature of 80°F.

The heat transfer rate measured in the test should be adjusted to account for differences in the HL and IRWST temperatures and the number of tubes plugged.

ITAAC Completion Description Multiple ITAAC are performed to confirm the Passive Core Cooling System provides core decay heat removal during design basis events by testing and analysis of the Passive Residual Heat Removal(PRHR) Heat Exchanger(HX)to determine the heat transfer from the PRHR HX. The Reactor Coolant System (RCS) hot leg temperature will be initially s 350°F with the Reactor Coolant Pumps(RCPs) running. The In-containment Refueling Water Storage Tank(IRWST) water level for the test will be above the top of the PRHR HX and the test will continue until the hot leg (HL)temperature is ^ 250F.

The testing is performed in accordance with Unit 3 and Unit 4 Preoperational test procedures (References 1 and 2) during Hot Functional Testing with the RCS at s 350°F and the IRWST level verified to be above the PRHR HX. The RCPs are verified to be running and the test initiated by opening one of the PRHR HX outlet valves. RCS temperature is monitored and when temperature decreases to ^ 250°F, the PRHR HX outlet valve is closed. PRHR HX inlet temperature, RCS hot leg and cold leg temperatures, IRWST temperature and PRHR HX flow are trended during the test and this information is provided to engineering to perform the heat transfer rate calculations. The heat transfer rate determined by engineering is corrected to compensate for the design number of tubes plugged (5%)and compared to the acceptance criteria.

The completed test results report(References 1 and 2) documents the heat transfer rate for Unit 3 is A.AA X 10^ Btu/hr with 250°F hot leg temperature and an initial IRWST temperature of 80°F.

The heat transfer rate for Unit 4 is B.BB x 10^ Btu/hr with 250°F hot leg temperature and an initial IRWST temperature of 80°F.

U.S. Nuclear Regulatory Commission ND-20-0490 Enclosure Page 3 of 3 The heat transfer rate measured in the test is adjusted to account for differences in the HL and IRWST temperatures and the number of tubes plugged.

This demonstrates that a report exists and concludes that the PRHR HX heat transfer rate with the design basis number of PRHR HX tubes plugged is:

s 8.46 X 10^ Btu/hr with 250°F hot leg temperature and an initial IRWST temperature of 80°F.

References 1 and 2 are available for NRG inspection as part of ITAAC 2.2.03.08b.01 Unit 3 and 4 Completion Packages(Reference 3 and 4).

List of ITAAC Findings 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 are no relevant ITAAC findings associated with this ITAAC.

References(available for NRC inspection)

1. 3-PXS-ITPP-504,"Passive Core Cooling System Hot Functional Test"

2. 4-PXS-ITPP-504,"Passive Core Cooling System Hot Functional Test"

3. 2.2.03.08b.01-U3-CP-Rev0, ITAAC Completion Package

4. 2.2.03.08b.01-U4-CP-Rev0, ITAAC Completion Package

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