ND-18-0847, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.09.06 (Index Number 647)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.6.09.06 (Index Number 647)

ML18178A557
Person / Time
Site:	Vogtle
Issue date:	06/26/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.6.09.06, ND-18-0847
Download: ML18178A557 (6)

Text

^ Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel JUN 2 6 2018 410-474-8587 cell myox @southernco.com Docket Nos.: 52-025 52-026 ND-18-0847 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 2.6.09.06 [Index Number 6471 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 12, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.6.09.06 [Index Number 647]

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 & Unit 4 Completion Plan for Uncompleted ITAAC 2.6.09.06 [Index Number 647]

MJY/RAS/amw

U.S. Nuclear Regulatory Commission ND-18-0847 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (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 Reoulatorv 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 Qqiethorpe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0847 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse 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. 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-18-0847 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-18-0847 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 & Unit 4 Completion Plan for Uncompleted ITAAC 2.6.09.06 [Index Number 647]

U.S. Nuclear Regulatory Commission ND-18-0847 Enclosure Page 2 of 3 ITAAC Statement Design Commitment

6. The vehicle barrier system is installed and located at the necessary stand-off distance to protect against the DBT vehicle bombs.

Inspections. Tests. Analvses Inspections and analysis will be performed for the vehicle barrier system.

Acceptance Criteria The vehicle barriersystem will protect against the DBT vehicle bombs based upon the stand-off distance of the system.

ITAAC Completion Description Inspections and analysis of the vehicle barrier system (VBS, as defined by NUREG-2203) are performed to ensure the system is installed and located at the necessary stand-off distanceto protect against the Design Basis Threat (DBT) vehicle bombs. The inspections and analysis confirm the VBS will protect against the DBT vehicle bombs based upon the stand-off distance of the VBS and satisfythe applicable VBS stand-off distance requirements of the Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Physical Security Plan associated with 10 CFR 73.55(e)(10). The VEGP Unit 3 [Unit 4] PlantSecurity System ITAACs only cover the Unit 3

[Unit 4] plant security system design commitment scope.

The design, construction and installation ofthe VBS is based upon analyses of the minimum safe stand-off distance (MSSD) required to provide adequate protection of the personnel, equipment, and systems necessary to prevent significant core damage and spent fuel pool sabotageagainst the effects of the DBT of radiological sabotage land vehicle bomb assault.

The Unit 3 [Unit 4] MSSD is established by standard plantanalysis (Reference 1), as supplemented by the site specific MSSD analysis (Reference 2 [3]).

Procedure XXX, Unit 3 [Unit 4] Vehicle Barrier System Stand-off Distance Inspection Procedure (Reference 4 [5]), performs an inspection to confirm the VBS is installed at stopping distances equal to orgreater than the MSSDs established by analyses (References 1 and 2 [1 and 3]).

The inspection also confirms that the as-built VBS installation is consistent with the VBS design and installation analyses assumptions.

The VBS DBT inspection and analysis results are documented in References 1 through 5 and confirm the vehicle barrier system will protectagainst the DBT vehicle bombs based upon the stand-off distance of the VBS.

References 1 through 5 are available for NRC inspection as partofthe Unit 3 [Unit 4] ITAAC 2.6.09.06 Completion Package (Reference 6 [7]).

U.S. Nuclear Regulatory Commission ND-18-0847 Enclosure Page 3 of 3 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 favaiiable for NRC inspection)

1. APP-XV01 -ZOC-001, "AP1000 Vehicle Barrier System Standoff Distances for a Range of Blast Scenarios" (Safeguards Information)

2. DOEJ-V34-LAR-18-008-SEC001, "Minimum Safe Standoff Distance (MSSD) Evaluation of the Transitional Vehicle Barrier System Between Plant Vogtle Units 3 & 4 With Respect to Equipment Required for Safe Shutdown, Equipment Required for Security Response, and Security Force Response Personnel" (Safeguards Information)

3. Document XXX, Unit 4 MSSD Site Specific Information (Safeguards Information)

4. Procedure XXX, Unit 3 Vehicle Barrier System Stand-off Distance Inspection Procedure (Safeguards Information)

5. Procedure XXX, Unit 4 Vehicle Barrier System Stand-off Distance Inspection Procedure (Safeguards Information)

6. 2.6.09.06-U3-CP-Rev0, ITAAC Completion Package

7. 2.6.09.06-U4-CP-Rev0, ITAAC Completion Package

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