ML20118C437

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08b.02 (Index Number 176)

ML20118C437
Person / Time
Site:	Vogtle
Issue date:	04/27/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.2.03.08b.02
Download: ML20118C437 (6)

Text

^Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel April 27, 2020 Docket Nos.: 52-026 ND-19-0817 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 4 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08b.02 (Index Number 1761 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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08b.02 [Index Number 176]. This ITAAC verifies that the elevation of the centerline of the Passive Residual Heat Removal Heat Exchanger(PRHR HX) upper channel head is greater than the Hot Leg (HL) centerline by at least 26.3 ft. 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 Tom Petrak at 706-848-1575.

Respectfully submitted.

7A<

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.2.03.08b.02 [Index Number 176]

MJY/WLP/sfr

U.S. Nuclear Regulatory Commission ND-19-0817 Page 2 of 3 To:

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

Mr. D. L. McKinney (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. 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 Reouiatorv Commission Mr. W. Jones(w/o enclosures)

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

U.S. Nuclear Regulatory Commission ND-19-0817 Page 3 of 3 Mr. M. King Mr. E. Davidson Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Companv. 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. Hosier, 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 Sen/ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-0817 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-0817 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.2.03.08b.02[Index Number 176]

U.S. Nuclear Regulatory Commission ND-19-0817 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.b) The PXS provides core decay heat removal during design basis events.

I nspections/Tests/Analvses

2. Inspection of the elevation of the PRHR HX will be conducted.

Acceptance Criteria

2. The elevation of the centerline of the PRHR HX's upper channel head is greater than the HL centerline by at least 26.3 ft.

ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Passive Core Cooling System (PXS) provides core decay heat removal during design basis events. The subject ITAAC requires that an inspection be conducted of the Passive Residual Heat Removal Heat Exchanger(PRHR HX) to confirm that the centerline elevation of the PRHR HX's upper channel head is greater than the Hot Leg (HL) centerline by at least 26.3 ft.

The inspection of the centerline elevation of the PRHR HX's upper channel head and the centerline elevation of the HL was performed,following installation of the PRHR HX and the main reactor coolant loop piping, using survey equipment in accordance with the site survey and measurement procedures (Reference 1). The elevation difference was determined by measuring the centerline elevation of the HL and the centerline elevation of the PRHR HX's upper channel head in relation to a common reference point and comparing the results.

The inspection results documented in Reference 2, verify that the centerline elevation of the PRHR HX's upper channel head is greater than the Hot Leg (HL) centerline by at least 26.3 ft, which meets the ITAAC acceptance criteria. The Reference 2 inspection results are available for NRG inspection as part of the ITAAC Completion Package (Reference 3).

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.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08b.02 was performed for VEGP Unit 4 and that the prescribed acceptance criteria are 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-19-0817 Enclosure Page 3 of 3 References favailable for NRG inspection)

1. 26139-000-4MP-T81C-N3201, Rev 5,"Construction Survey"

2. SV4-PXS-FSK-800176, Rev 0,"Unit 4 As-Built Elevation Comparison of PRHR Heat Exchanger Upper Channel Head Centerilne to RCS Hot Leg Centeriine"

3. 2.2.03.08b.02-U4-CP-Rev0,"Completion Package for the Unit 4 ITAAC 2.2.03.08b.02 [index Number 176]"