ND-20-0194, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.l.04 (Index Number 180)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.l.04 (Index Number 180)

ML20150A477
Person / Time
Site:	Vogtle
Issue date:	05/29/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.2.03.08c.l.04, ND-20-0194
Download: ML20150A477 (6)

Text

Michael J. Vox

^Southern NucIear Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket Nos.: 52-025 MAY 2 9 2020 ND-20-0194 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 2.2.03.08c.l.04 [Index Number 1801 Ladles 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 2.2.03.08c.l.04

[Index Number 180], for verifying the Containment Reclrculatlon 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/

N Mlcfiael J. Vox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.1.04 [Index Number 180]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-20-0194 Page 3 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 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

U.S. Nuclear Regulatory Commission ND-20-0194 Page 3 of 3 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 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. 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-20-0194 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-20-0194 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.l.04[Index Number 180]

U.S. Nuclear Regulatory Commission ND-20-0194 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

Inspections/Tests/Analvses i) A low-pressure injection test and analysis for each CMT, each accumulator, each IRWST injection line, and each containment recirculation line will be conducted. Each test is initiated by opening isolation valve(s) in the line being tested. Test fixtures may be used to simulate squib valves.

4. Containment Recirculation:

A temporary water supply will be connected to the recirculation lines. All valves in these lines will be open during the test. Sufficient flow will be provided to open the check valves.

Acceptance Criteria i) The injection line flow resistance from each source is as follows:

4. Containment Recirculation:

The calculated flow resistance for each containment recirculation line between the containment and the reactor vessel is:

Line A: < 1.33 x 10"^ ft/gpm^ and Line B: < 1.21 x lO'Sft/gpm^.

ITAAC Determination Basis Multiple ITAAC were performed to verify that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. This ITAAC performed a low pressure injection test and analysis on each containment recirculation line between the containment and the reactor vessel 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(References 1 and 2) which demonstrated that the flow resistance in each containment recirculation line between the containment and the reactor vessel for line A was s 1.33 X 10 ft/gpm^ and for line B was < 1.21 x 10 ft/gpm^.

The test installed a temporary valve in the In-containment Refueling Water Storage Tank (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 to recirculation injection line B to the reactor vessel. Flow was throttled from the A IRWST screen to simulate the maximum flood level pressure available to the B recirculation flow path. All valves in the

U.S. Nuclear Regulatory Commission ND-20-0194 Enclosure Page 3 of 3 recirculation line flow path were opened during the test and sufficient flow was provided to open the check valves. The flow rate between the containment sump B and the reactor vessel injection line, differential pressure, and IRWST level were monitored and recorded. The process was then repeated with IRWST screen B to the containment sump 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 Unit 3 was calculated to be 1.24 x 10 ft/gpm^ for the line A containment recirculation flow path and 1.12 x lO ^ft/gpm^ for the line B containment recirculation flow path (References 4 and 5). The Unit 3 test results were documented in Reference 3 and confirm that the calculated flow resistance between each containment sump to reactor vessel via the containment recirculation line flow path meets the ITAAC acceptance criteria.

References 1 through 5 are available for NRC inspection as well as the ITAAC 2.2.03.08c.i.04 Completion Package (Reference 6).

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 Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.i.04 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 favaiiabie 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-800180, Rev 0, ITAAC Technical Report,"Unit 3 Recorded Results of PXS Containment Recirculation Line Flow Resistance: ITAAC 2.2.03.08c.i.04"

4. SV3-PXS-T1R-002, Rev. 0,"Vogtle Unit 3 3-PXS-ITPP-507 Section 4.3.2 and Section 4.3.4 Containment Recirculation Sump to DVI Nozzle Flow Resistance Test Engineering Report"

5. SV3-PXS-T2C-002, Rev. 0,"Vogtle Unit 3 3-PXS-ITPP-507 Section 4.3.2 and Section 4.3.4 Containment Recirculation Sump to DVI Nozzle Flow Resistance Test Calculation"

6. 2.2.03.08c.i.04-U3-CP-Rev0, ITAAC Completion Package

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