ND-18-0531, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.i.04 (Index Number 180)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.i.04 (Index Number 180)

ML18120A264
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-18-0531
Download: ML18120A264 (6)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tei 410-474-8587 ceil myox@southernco.com APR L 7 jiuid Docket Nos.: 52-025 52-026 ND-18-0531 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.i.04 [Index Number 1801 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, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.1.04 [Index Number 180] 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 Companywill, 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 Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.1.04 [Index Number 180]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-18-0531 Page 2 of 3 To:

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

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

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

M D. L. McKinney M M. J. Yox M D. L. Fulton M J. B. Klecha M G. Chick M 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 Reouiatorv 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 Oaiethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0531 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. Orlani (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., 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-18-0531 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0531 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.l.04 [index Number 180]

U.S. Nuclear Regulatory Commission ND-18-0531 Enclosure Page 2 of 3 ITAAC Statement Design Commitment S.c) The PXS provides RCS makeup, boratlon, and safety injection during design basis events.

inspectlons/Tests/Anaivses

1) A low-pressure injection test and analysis for each CMT, each accumulator, each IRWST injection line, and each containment recircuiation line wiii be conducted. Each test is initiated by opening isolation vaive(s) in the line being tested. Test fixtures may be used to simulate squib valves.

4. Containment Recircuiation: A temporary water supply wiii be connected to the recircuiation lines. Ail valves in these lines wiii be open during the test. Sufficient flow wiii be provided to open the check valves.

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

4. Containment Recircuiation: The calculated flow resistance for each containment recircuiation line between the containment and the reactor vessel is:

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

ITAAC Completion Description Multiple ITAAC are performed to verify that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boratlon, and safety injection during design basis events. The subject ITAAC requires a low-pressure injection test and analysis on each containment recircuiation line between the containment and the reactor vessel to demonstrate that the calculated flow resistance meets acceptance criteria.

Performance tests are conducted in accordance with Unit 3 and Unit 4 preoperational test procedures (Reference 1 and 2, respectively) to demonstrate that the flow resistance in each containment recircuiation line between the containment and the reactor vessel for line A is

^ 1.33 X10' ft/gpm^ and for line B is ^ 1.21 x 10' ft/gpm^.

This is accomplished by installing a compression plug in the In-containment Refueling Water Storage Tank (IRWST) screen B drain line, installing flow test fixtures forthe squib valves in the containment recircuiation sump lines, filling the IRWST with demineralized water to act as a temporary water supply, and initiating flow from the A screen inthe IRWST into the containment recircuiation sump to recircuiation injection line B to the reactor vessel. All valves in these lines are opened during the test and sufficient flow is 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 are monitored and recorded. The process is then repeated with IRWST screen B to the 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 to the acceptance criteria.

U.S. Nuclear Regulatory Commission ND-18-0531 Enclosure Page 3 of 3 The flow resistance for Unit 3 is calculated to be XXX ft/gpm^ for the containment recirculation line A flow path and YYY ft/gpm^ for the containment recirculation line B flow path. The flow resistance for Unit 4 is calculated to be XXX ft/gpm^ for the containment recirculation line A flow path and YYY ft/gpm^ for the containment recirculation line B flow path. The completed Unit 3 and Unit 4 preoperational tests confirm that the calculated flow resistance for each containment recirculation line between the containment and the reactor vessel is ^ 1.33 x 10 ft/gpm^ for Line A and 2 1.21 x 10 ft/gpm^ for line B.

References 1 and 2 are available for NRC inspection as part of the ITAAC 2.2.03.08c.i.04 Completion Packages (References 3 and 4).

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 are no relevant ITAAC findings associated with this ITAAC.

References favailable 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. 2.2.03.08c.i.04-U3-CP-Rev X, ITAAC Completion Package

4. 2.2.03.08c.i.04-U4-CP-Rev X, ITAAC Completion Package

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