ND-18-0518, Vogtie, Unit 3 and 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.i.03 (Index Number 179)

Vogtie, Unit 3 and 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.i.03 (Index Number 179)

ML18120A301
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-18-0518
Download: ML18120A301 (6)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com APR 2 7 2018 Docket Nos.: 52-025 52-026 ND-18-0518 10CFR 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.03 findex Number 1791 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.i.03 [Index Number 179] 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 Diredtor Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.i.03 [Index Number 179]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-18-0518 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. S. 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 Reaulatorv 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 Ooiethorpe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0518 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., 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-18-0518 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0518 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.l.03 [Index Number 179]

U.S. Nuclear Regulatory Commission ND-18-0518 Enclosure Page 2 of 3 ITAAC Statement Design Commitment 8.0) 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.

3. IRWST Injection:

The IRWST will be partially filled with water. 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:

3. IRWST Injection:

The calculated flow resistance for each IRWST injection line between the IRWST and the r©3ctor V0SS6I is*

Line A: s 5.35 x 10" ft/gpm^ and ^ 9.09 x 10" ft/gpm^ and Line B: s 6.15 x 10 ft/gpm^ and ^ 1.05 x 10 ft/gpm^.

ITAAC Completion Description Multiple ITAAC are performed to verify that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. The subject ITAAC requires a low-pressure injection test and analysis on each In-containment Refueling Water Storage Tank (IRWST) injection line to 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 determine that the flow path from each IRWST injection line to the reactor vessel has a flow resistance s 5.35x 10" ft/gpm^ and s 9.09 x 10' ft/gpm^for line A and a flow resistance ^ 6.15 x 10" ft/gpm^ and ^ 1.05 x 10"ft/gpm^for line B.

This is accomplished by installing flow test fixtures for the squib valves in the IRWST injection lines, isolating the containment sump recirculation lines, filling the IRWST with demineralized water to act as a temporary water supply, and initiating flow between the IRWST and direct vessel injection line A. All valves in these lines are opened during the test and sufficientflow is provided to open the check valves. The flow rate be^een the IRWST and the injection line Ato the reactor vessel, differential pressure, and IRWST level are measured. This test is repeated for the direct vessel injection line B. The constant value for flow resistance is calculated based on measured tank level, differential pressure, and discharge flow, adjusted for measurement uncertainty, and compared to the acceptance criteria.

U.S. Nuclear Regulatory Commission ND-18-0518 Enclosure Page 3 of 3 The flow resistance for Unit 3 is calculated to be XXX ft/gpm^ for the IRWST injection line A flow path and YYY ft/gpm^ for the IRWST injection line Bflow path. The flow resistance for Unit 4 is calculated to be XXX ft/gpm^ for the IRWST injection line Aflow path and YYY ft/gpm^ for the IRWST injection line Bflow path. The completed Unit 3 and Unit 4 preoperational tests confirm that the calculated flow resistance for each IRWST injection line between the IRWST and the reactor vessel is s 5.35 x 10" ft/gpm^ and ^ 9.09x 10" ft/gpm^for line Aand > 6.15 x 10 ft/gpm^ and < 1.05 x lO'^ft/gpm^for line B.

References 1 and 2 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.03.08c.i.03 Completion Packages (References 3 and 4, respectively).

List of ITAAC Findings In accordance with plantprocedures 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 NRG 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.03-U3-CP-Rev X, ITAAC Completion Package

4. 2.2.03.08c.i.03-U4-CP-Rev X, ITAAC Completion Package

5. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10CFR Part52"