ND-20-0198, ITAAC Closure Notification on Completion of ITAAC 2.2.03.09a.1 (Index Number 201)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.09a.1 (Index Number 201)

ML20132A159
Person / Time
Site:	Vogtle
Issue date:	05/11/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0198
Download: ML20132A159 (6)

Text

Michael J. Vox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tel Docket Nos.: 52-025 MAY I 1 2020 ND-20-0198 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.09a.1 [Index Number 2011 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 Vogtie Electric Generating Plant(VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) item 2.2.03.09a.i [Index Number 201], for verifying the In-containment Refueling Water Storage Tank (IRWST) drain line flow resistance values. 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 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 10 CFR 52.99.

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

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.09a.i [Index Number 201]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-20-0198 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. 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 Reoulatorv 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

U.S. Nuclear Regulatory Commission ND-20-0198 Page 3 of 3 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 Westinahouse 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., CDS 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-20-0198 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-0198 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.09a.l [Index Number 201]

U.S. Nuclear Regulatory Commission ND-20-0198 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 9.a) The PXS provides a function to cool the outside of the reactor vessel during a severe accident.

I nspections/Tests/Analvses i) A flow test and analysis for each IRWST drain line to the containment will be conducted. The test is initiated by opening isolation valves in each line. Test fixtures may be used to simulate squib valves.

Acceptance Criteria i) The calculated flow resistance for each IRWST drain line between the IRWST and the containment is ^ 4.44 x 10 ft/gpm^.

ITAAC Determination Basis Multiple ITAAC were performed to verify that the Passive Core Cooling System (PXS) provides a function to cool the outside of the reactor vessel during a severe accident. This ITAAC performed a flow test and analysis on each In-containment Refueling Water Storage Tank (IRWST) drain line to the containment to demonstrate that the calculated flow resistance meets acceptance criteria.

Performance tests were conducted in accordance with the Unit 3 preoperational test procedure 3-PXS-ITPP-507(Reference 1 and 2) which demonstrated that the flow resistance in each IRWST drain line to the containment was s 4.44 x 10 ft/gpm^.

The test installed a temporary valve in the IRWST screen drain lines, installed a jumper between the A and B containment sump injection lines, installed flow test fixtures for the squib valves in the containment recirculation sump lines, filled the IRWST with demineralized water to act as a temporary water supply, and initiated flow from the A screen in the IRWST into the containment recirculation sump A to recirculation injection line B to the reactor vessel. All valves in the flow path were opened during the test and sufficient flow was provided to open the check valves. The flow rate between the IRWST and containment sump A, differential pressure, and IRWST level were monitored and recorded. The process was then repeated with IRWST screen B to containment sump B to reactor vessel injection line A. The constant value for each flow resistance was calculated based on IRWST level, differential pressure and discharge flow, adjusted for measurement uncertainty, and compared to the acceptance criteria.

The flow resistance for each Unit 3 IRWST drain line between the IRWST and the containment was calculated to be 3.57 x 10 ft/gpm2 (drain line A) and 2.49 x 10 ft/gpm^ (drain line B)

(References 4 and 5). The Unit 3 test results were documented in Reference 3 and confirmed that the calculated flow resistance between each IRWST drain line to the containment sump meets the ITAAC acceptance criteria.

References 1 through 5 are available for NRG inspection as well as the ITAAC 2.2.03.09a.i Completion Package (Reference 6).

U.S. Nuclear Regulatory Commission ND-20-0198 Enclosure Page 3 of 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 were no relevant ITAAC findings associated with this ITAAC.

iTAAC Compietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.09a.i 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 NRC Inspection)

1. 3-PXS-ITPP-507, Rev. 3,"IRWST Flow Tests"

2. Work Order 1071722,"(ITAAC) Perform Preop Test 3-PXS-ITPP-507"

3. SV3-PXS-ITR-800201, Rev. 0, ITAAC Technical Report,"Unit 3 Recorded Results of PXS IRWST Drain Line Flow Resistance: ITAAC 2.2.03.09a.i"

4. SV3-PXS-T1R-003, Rev. 0,"Vogtle Unit 3 3-PXS-ITPP-507 Section 4.3.1 and 4.3.3 IRWST to Containment Recirc Sump Flow Resistance Test Engineering Report"

5. SV3-PXS-T2C-003, Rev. 0,"Vogtle Unit 3 3-PXS-ITPP-507 Section 4.3.1 and 4.3.3 IRWST to Containment Recirc Sump Flow Resistance Test Calculation"

6. 2.2.03.09a.i-U3-CP-Rev0, ITAAC Completion Package

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