ND-18-0534, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.09a.i (Index Number 201)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.09a.i (Index Number 201)

ML18120A282
Person / Time
Site:	Vogtle
Issue date:	04/27/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0534
Download: ML18120A282 (6)

Text

Michael J. Vox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynestjoro, GA 30830 706-848-6459 tel 410-474-8587 cell APR 2 7 2018 myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0534 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.09a.i (Index Number 2011 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 12, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.09a.i [Index Number 201] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

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

Respectfully submitted.

Michael J. Yox^;

Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.09a.i [Index Number 201]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-18-0534 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKinney Mr. M. J. Yox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oolethorpe Power Corooration Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0534 Page 3 of 3 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 Ms. L. G. Iller Mr. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis 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 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-18-0534 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0534 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.09a.i [Index Number 201]

U.S. Nuclear Regulatory Commission ND-18-0534 Enclosure Page 2 of 3 ITAAC Statement Desion Commitment 9.a) The PXS provides a function to cool the outside of the reactor vessel during a severe accident.

Insoections/Tests/Analvses i) Aflow 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 resistancefor each IRWST drain line between the IRWST and the containment is ^ 4.44 x 10 ft/gpm^.

ITAAC Completion Description Multiple ITAAC are 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. The subject ITAAC requires a flow test andanalysis on each In-containment Refueling Water Storage Tank (IRWST) drain line tothe containment to demonstrate thatthe calculated flow resistance meets acceptance criteria.

Performance tests are conducted in accordance with Unit 3 and Unit 4 preoperational test procedures (Reference 1and 2, respectively) to demonstrate that the flow resistance in each IRWST drain line to the containment is < 4.44 x 10 ft/gpm^.

This is accomplished by installing a compression plug in the IRWST screen Bdrain line, installing flow test fixtures for the squib valves in the containment recirculation sump lines, filling the IRWST with demineralized water to act as a temporarywater supply, and initiating flow from the A screen in the IRWST into the containment recirculation sump to recirculation injection line B to the reactor vessel. All valves in these lines are opened during the test and sufficient fiow is provided to open the check valves. The flow rate between the IRWST andthe containment sump A, differential pressure, and IRWST level are monitored and recorded. The process is then repeated with IRWST screen Btothe containment sump to reactor vessel injection line A.

The constant value for each flow resistance is calculated, based on tank level, differential pressure and discharge flow, adjusted for measurement uncertainty, and compared tothe acceptance criteria.

The flow resistance for each Unit 3 IRWST drain line between the IRWST and the containment is calculated to be XXX ft/gpm^ (drain line A) and YYY ft/gpm^ (drain line B). The flow resistance for each Unit 4 IRWSTdrain line between the IRWSTand the containment is calculated to be XXX ft/gpm^ (drain line A) and YYY ft/gpm^ (drain line B). The completed Unit 3 and Unit 4 preoperational tests confirm that the calculated flow resistance for each IRWST drain line between the IRWST and the containment is ^ 4.44 x 10" ft/gpm^.

U.S. Nuclear Regulatory Commission ND-18-0534 Enclosure Page 3 of 3 References 1 and 2 are available for NRG inspection as part of tfie Unit 3 and Unit 4ITAAC 2.2.03.09a.i Completion Packages (References 3 and 4).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern NuclearOperating Company (SNC) performed a review of allfindings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References favaiiabie for NRC inspection)

1. 3-PXS-ITPP-5XX, "Passive Core Cooling System Preoperational Test Procedure"

2. 4-PXS-ITPP-5XX, "Passive Core Cooling System Preoperational Test Procedure"

3. 2.2.03.09a.i-U3-CP-Rev X, ITAAC Completion Package

4. 2.2.03.09a.i-U4-CP-Rev X, ITAAC Completion Package

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