ND-20-0281, ITAAC Closure Notification on Completion of ITAAC 2.1.02.08d.iv (Index Number 35)

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ITAAC Closure Notification on Completion of ITAAC 2.1.02.08d.iv (Index Number 35)
ML20090C009
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 03/27/2020
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0281
Download: ML20090C009 (6)


Text

_ I .I I Michael J. Vox 7825 River Road bouthern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel MAR 2 7 2020 Docket Nos.;52-026 ND-20-0281 10CFR 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 2.1.02.08d.iv (Index Number 351 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 2.1.02.08d.iv [Index Number 35]for verification of the effective flow area through the Reactor Coolant System (RCS)Stage 1, 2, and 3 Automatic Depressurization System (ADS) valves. 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, I

Michael J.

Regulatory Affairs Difector Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.1.02.08d.iv [Index Number 35]

MJY/WLP/sfr

U.S. Nuclear Regulatory Commission ND-20-0281 Page 2 of 3 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. J. L. Hughes 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 B. 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 M P. Heher M M. King M E. Davidson

U.S. Nuclear Regulatory Commission ND-20-0281 Page 3 of 3 Oalethorpe 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 Westinahouse Electric Company. LLC Dr. L. OrlanI (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. Hesler, Bechtel Power Corporation Ms. L. Mails, Tetra Tech NUS, Inc.

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

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

U.S. Nuclear Regulatory Commission ND-20-0281 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-0281 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 4 Completion of ITAAC 2.1.02.08d.iv [Index Number 35]

U.S. Nuclear Regulatory Commission ND-20-0281 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.d) The RCS provides automatic depressurization during design basis events.

Insoections. Tests. Analvses:

iv) Type tests and analysis will be performed to determine the effective flow area through each stage 1,2,3 ADS valve.

Acceptance Criteria:

iv) A report exists and concludes that the effective flow area through each stage 1 ADS valve ^

4.6 in^ and each stage 2,3 ADS valve is s 16 in^.

ITAAC Determination Basis Multiple Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are performed to demonstrate that the Reactor Coolant System (RCS) provides automatic depressurization during design basis events. This ITAAC requires type tests and analysis to determine the effective flow area through each Stage 1 Automatic Depressurization System (ADS) valve is s 4.6 in^ and the effective flow area through each Stage 2 ,3 ADS valve is s 16 in^.

Type tests and analyses were performed to determine the effective flow area through each Stage 1,2,3 ADS valve. The effective flow area for each type of valve was calculated based on the valve flow coefficient derived in accordance with ANSI/ISA-75.02.01-2008 (Reference 1) from applicable test condition data and the flow test results with the valve in the fully open position.

The ADS valve analysis report(Reference 2) demonstrates that the effective flow area for the Stage 1 ADS valve is 5.66 in^ and the Stage 2 and 3 ADS valve is 18.5 in^ and meets the ITAAC acceptance criteria.

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 that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review document number is included in the Vogtle Unit 4 ITAAC Completion Package for ITAAC 2.1.02.08d.iv (Reference 3) and available for NRC inspection.

U.S. Nuclear Regulatory Commission ND-20-0281 Enclosure Page 3 of 3 ITAAC Completion Statement Based on the above information, SMC hereby notifies the NRG that ITAAC 2.1.02.08d.iv 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.

References(available for NRG inspection)

1. ANSI/ISA-75.02.01-2008, "Control Valve Capacity Test Procedure"
2. SV4-PV01-VDR-000005, Rev. 0,"ADS 1,2,3 Globe Valve Choked Flow Area Test Results and Analysis Report"
3. 2.1.02.08d.iv-U4-CP-Rev0, ITAAC Completion Package