ND-18-0563, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.13a (Index Number 063)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.13a (Index Number 063)

ML18117A269
Person / Time
Site:	Vogtle
Issue date:	04/23/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0563
Download: ML18117A269 (5)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tel 410-474-8587 celi myox@southernco.Gom APR 2 3 2018 Docket Nos.: 52-025 52-026 ND-18-0563 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 2.1.02.13a [Index Number 0631 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 18, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.13a [Index Number 063]

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 Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.13a [Index Number 063]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0563 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. Vox Mr. D. L. Fulton Mr. J. 8. 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 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 Oalethorpe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0563 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. 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 PublicService 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-18-0563 Enclosure Page 1 of 2 Southern Nuclear Operating Company ND-18-0563 Enclosure Vogtle Electric Generating Plant (VEGP) Unit3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.13a [Index Number 063]

U.S. Nuclear Regulatory Commission ND-18-0563 Enclosure Page 2 of 2 ITAAC Statement Design Commitment 13.a) Controls exist in the MCR to trip the RCPs.

Insoections. Tests. Analyses Testing will be performed on the RCPs using controls in the MCR.

Acceptance Criteria Controls in the MCR operate to trip the RCPs.

ITAAC Completion Description Testing is performed in accordance with the Unit 3 and Unit 4 component test package work orders (References 1 and 2, respectively) for Reactor Coolant Pump (RCP) trip testing to demonstrate controls in the Main Control Room (MCR) operate to trip the RCPs (RCS-MP-01A, RCS-MP-01B, RCS-MP-02A, RCS-MP-02B). Soft controls from the Plant Control System (PLS) are used to generate a RCP trip signal to the four RCP breakers controlled from PLS. The breaker for RCP 1A is ECS-ES-31, the breaker for RCP 1B is ECS-ES-41, the breaker for RCP 2A is ECS-ES-51, and the breaker for RCP 2B is ECS-ES-61. Local inspection verifies the PLS trip signal causes the listed RCP breakers to open.

The Unit 3 and Unit 4 component test results (References 1 and 2, respectively) confirm that controls in the MCR operate to trip the RCPs.

References 1 and 2 are available for NRC inspection as part of the Unit 3 and Unit4 ITAAC 2.1.02.13a Completion Packages (References 3 and 4, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a reviewof all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review found no relevant ITAAC findings associated with this ITAAC.

References (available for NRC Inspection)

1. SNC922049 Revision 0, "Reactor Coolant Pump Trip Test - ITAAC:SV3-2.1.02.13a"

2. SNCXXXXXX Revision 0, "Reactor Coolant Pump Trip Test - ITAAC:SV4-2.1.02.13a"

3. 2.1.02.13a-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.1.02.13a [Index Number 63]"

4. 2.1.02.13a-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.1.02.13a [Index Number 63]"

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