ND-20-0699, ITAAC Closure Notification on Completion of ITAAC 2.1.02.08e (Index Number 40)

ITAAC Closure Notification on Completion of ITAAC 2.1.02.08e (Index Number 40)

ML20188A332
Person / Time
Site:	Vogtle
Issue date:	07/06/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0699
Download: ML20188A332 (6)

Text

^Southern Nuclear Michael J. Vox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel JUL 0 6 2020 Docket Nos.: 52-025 ND-2G-G699 1GCFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 2G555-GGG1 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.1.G2.G8e [Index Number 4G1 Ladies and Gentlemen:

In accordance with 1G 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.G2.G8e [Index Number 4G]. This ITAAC verified that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.G Ibm/sec at 25GG psia in the RCS. The closure process for this ITAAC is based on the guidance described in NEI-G8-G1, "Industry Guideline for the ITAAC Closure Process under 1G CFR Part 52"(Reference 1), which is 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 1G CFR 52.99.

If there are any questions, please contact Tom Petrak at 7G6-848-1575.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of 2.1.G2.G8e [Index Number 4G]

MJY/TST/sfr

U.S. Nuclear Regulatory Commission ND-20-0699 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. Vox 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 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 M M. Webb M T. Fredette 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 M P. Heher M M. King M E. Davidson

U.S. Nuclear Regulatory Commission ND-20-0699 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 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. 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., CDS Associates, Inc.

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

U.S. Nuclear Regulatory Commission ND-20-0699 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-0699 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.1.02.08e [Index Number 40]

U.S. Nuclear Regulatory Commission ND-20-0699 Enclosure Page 2 of 3 ITAAC Statement Design Commitment:

8.e) The RCS provides emergency letdown during design basis events.

Inspections. Tests. Analvses:

Inspections of the reactor vessel head vent valves and inlet and outlet piping will be conducted.

Acceptance Criteria:

A report exists and conciudes that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.0 Ibm/sec at 2500 psia in the RCS.

ITAAC Determination Basis The Reactor Cooiant System (RCS) provides emergency ietdown during design basis events. This ITAAC performs inspections of the reactor vessel head vent(RVHV) valves and inlet and outlet piping to verify that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.0 Ibm/sec at 2500 psia in the RCS.

The flow capacity of the RVHV pipe routing is restricted (choked) up to the orifice downstream of the RVHV valves RCS-PL-V150C and D. The flow resistance of the RVHV valves and inlet and outlet piping was caicuiated with Darcy's formula using line routing information (i.e., pipe length, pipe diameter, number and type of pipe fittings, entrance/exit losses and valves)(Reference 3).

Following installation, inspections of construction records were performed to verify the iine routing information of the RVHV inlet and outlet piping including valves up to the downstream orifice is consistent with the information in the fiow capacity design calculation. The inspection results documented in Reference 2 verify that there is negligible difference between the as-designed and as-buiit RVHV piping configuration. The calculated RVHV flow capacity of 12.34 ibm/sec at 2500 psia in the RCS remains valid for the as-built system configuration.

The inspection results documented in Reference 2 verify that the capacity of the reactor vessel head vent is sufficient to pass not less than 9.0 Ibm/sec at 2500 psia in the RCS, which meets the ITAAC acceptance criteria. The design calculation and inspection results (References 3 and 2 respectively) are available for NRC inspection as part of the ITAAC Completion Package (Reference 4).

ITAAC Finding Review In accordance with plant procedures for IT/\AC completion. Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining to the subject IT/\AC 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 2.1.02.08e was performed for VEGP Unit 3 and that the prescribed acceptance criteria are met.

U.S. Nuclear Regulatory Commission ND-20-0699 Enclosure Page 3 of 3 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 favailable for NRG inspection)

1. NEI-08-01 Rev. 5 corrected 6-30-2014, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52

2. SV3-RCS-ITR-800040, Rev 0,"Unit 3 Inspections and Associated Analysis of the RCS Reactor Vessel Head Vent Line: ITAAC 2.1.02.08e, NRC Index Number: 40"

3. APP-RCS-M3C-067, Rev 4, "Orifice Functional Requirements for RCS Reactor Vessel Head Vent Flow Orifices (APP-RCS-PY-R01A/B)"

4. 2.1.02.08e-U3-CP-Rev0, ITAAC Completion Package