ND-18-1508, Unit 4 - ITAAC Closure Notification on Completion of ITAAC 2.2.01.04a.ii (Index Number 96)

Unit 4 - ITAAC Closure Notification on Completion of ITAAC 2.2.01.04a.ii (Index Number 96)

ML18362A186
Person / Time
Site:	Vogtle
Issue date:	12/20/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.01.04a.ii, ND-18-1508
Download: ML18362A186 (7)

Text

A Southern Nuclear Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel DEC 2 0 2018 410-474-8587 cell myox@southernco.com Docket No.: 52-025 52-026 ND-18-1508 10 CFR 52 .99(c)(1)

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 ITAAC Closure Notification on Completion of ITAAC 2.2.01.04a.ii [Index Number 96)

Ladies and Gentlemen :

In accordance with 10 CFR 52.99(c)(1 ), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01 .04a.ii [Index Number

96) for verifying the CNS Containment and Pressure-Retaining Penetration Materials Fracture Toughness. The closure process for this ITAAC is based on 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 .

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52 .99.

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

Respectfully submitted ,

~ ~J.\' /JJ I Michae( ~ !J Regulatory Affairs Direct , r Vogtle 3 & 4

. I

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 2.2.01 .04a.ii [Index Number 96)

MJY/GCW/sfr

U.S. Nuclear Regulatory Commission ND-18-1508 Page 2 of 3 To:

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

Mr. D. L. McKinney (w/o enclosures)

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

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

Mr. J. 8. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. S. Parton Ms. A. L. Pugh Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

Mr. F. D. Brown Ms. J. M. Heisserer Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. 8. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. I. Cozens Mr. J. Gaslevic Mr. V. Hall Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-1508 Page 3 of 3 Westinghouse Electric Company, LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan Mr. J. L. Coward Other Mr. J.E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W.R. Jacobs, Jr., Ph.D., GOS Associates, Inc.

Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-18-1508 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-1508 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 2.2.01.04a.ii [Index Number 96]

U.S. Nuclear Regulatory Commission ND-18-1508 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 4.a) The components identified in Table 2.2.1-1 as ASME Code Section Ill retain their pressure boundary integrity at their design pressure.

Inspections/Tests/Analyses ii) Impact testing will be performed on the containment and pressure-retaining penetration materials in accordance with the ASME Code Section Ill, Subsection NE, to confirm the fracture toughness of the materials.

Acceptance Criteria ii) A report exists and concludes that the containment and pressure-retaining penetration materials conform with fracture toughness requirements of the ASME Code Section Ill.

ITAAC Determination Basis Multiple ITMC are performed to demonstrate that the components identified in the Combined License (COL) Appendix C, Table 2.2.1-1 as ASME Code Section Ill retain their pressure boundary integrity at their design pressure. This ITMC requires impact testing be performed on the containment and pressure-retaining penetration materials to confirm the fracture toughness of the materials.

The Vogtle Electric Generating Plant (VEGP) containment vessels for Unit 3 and Unit 4 are designed and fabricated in accordance with the American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel (B&PV) Code Section Ill, Subsection NE, 2001 edition, 2002 addenda and require impact testing to confirm the fracture toughness of the materials (Reference 1). Materials in this regard include pressure-retaining attachments and reinforcements as well as the containment vessel (CV) pressure boundary itself and any pressure-retaining penetrations in that boundary (Reference 2). The scope of this ITMC requires impact testing be performed on the CV pressure boundary material and the pressure-retaining penetration materials to conclude the material fracture toughness requirements conform to the ASME Code Section Ill.

VEGP 3&4 Updated Final Safety Analysis Report (UFSAR) Table 3.2-3 (Reference 3) establishes the ASME Ill classification of the CV as Class MC. Class MC components fall under the jurisdiction of the ASME Code Section Ill, Subsection NE. Other equipment classified as ASME Ill Class MC and forming the pressure retaining boundary of containment are also listed in Reference 3 and are considered ASME Code "Parts" of the CV. These parts of the CV will be listed under the N-Stamp of the vessel on ASME Form N-1. The following table provides a listing of each ASME Code Section Ill, Subsection NE component, material or part that requires fracture toughness testing (Charpy impact testing) per this ITMC. All impact testing coupons conform to the requirements of ASME SA-370 for Charpy V-notch tests.

U.S. Nuclear Regulatory Commission ND-18-1508 Enclosure Page 3 of 4 Contanment Vessel and Pressure-Retaining Penetration Material Impact Testing Requirements and Results ASME Impact Test Impact Test Component/Part Design Code Requirement Results (Penetration #) Specification Subsection (ft-lbs) (ft-lbs)

Containment NE-2200, Varies APP-MV50-Z0-001 >50 Vessel Plates -2300 40 to 50 Penetration NE-2200, APP-MV50-Z0-001 15 >15 Sleeves -2300 Electrical NE-2200, Penetration APP-EY01-Z0-001 15 >15

-2300 Assemblies NE-2200, Varies Guard Pipes APP-MV50-Z0-001 >50

-2300 30to 50 Bellows Expansion NE-2200, Varies APP-ML 1O-Z0-004 >50 Joints -2300 30 to 50 NE-2200, Personnel Hatches APP-MV50-Z0-003 40 >40

-2300 Equipment/

NE-2200, Varies Maintenance APP-MV50-Z0-002 >50

-2300 40 to 50 Hatches Fuel Transfer Tube NE-2200, APP-FT01-Z0-001 40 >40 Insert -2300 Fracture Toughness Testing (Charpy testing) has also been performed for welding material used for CV construction in accordance with ASME Code Section Ill. The welding material meets the requirements for impact testing according to ASME Code Section Ill, and the results were documented in Reference 4 and were retained as quality records. The fracture toughness acceptance criteria for this material is the same as the base material. The fracture toughness tests results of welding material in all cases were greater than 50 ft-lbs.

The results of the impact testing summarized above were documented in the Vogtle Containment Vessel Units 3 & 4 Fracture Toughness Test Results contained in Reference 4.

These reports exist and conclude that the containment and pressure-retaining penetration materials conform with fracture toughness requirements of the ASME Code Section Ill.

Reference 4 is available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.01.04a.ii Completion Packages (References 5 and 6, respectively).

U.S. Nuclear Regulatory Commission ND-18-1508 Enclosure Page 4 of 4 ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings associated with these ITAAC. The ITAAC completion review is documented in the ITAAC Completion Packages for ITAAC 2.2.01.04a.ii for Unit 3 and Unit 4 (References 5 and 6 respectively) and are available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.04a.ii was performed for VEGP Unit 3 and Unit 4 and that the prescribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References (available for NRC inspection)

1. ASME Boiler and Pressure Vessel Code, Section Ill, "Rules for Construction of Nuclear Facility Components", 2001 Edition, 2002 Addenda

2. APP-MV50-Z0-001, Rev. 13, "AP1000 Containment Vessel Design Specification"

3. VEGP 3&4 Updated Final Safety Analysis Report,

a. Table 3.2-3, AP1000 Classification of Mechanical and Fluid Systems, Components, Equipment

b. Table 5.2-201, ASME Code, Case N-655-1, "Use of SA-738, Grade B, for Metal Containment Vessels, Class MC"

4. 165766-CBI-LT-SONC-000064 dated 12/1/2018, "CV ITAAC 2.2.01.04a.ii Preliminary Turnover"

5. 2.2.01.04a.ii-U3-CP-Rev 0, "Completion Package for the Unit 3 ITAAC 2.2.01.04a.ii [Index number 96]"

6. 2.2.01.04a.ii-U4-CP-Rev 0, "Completion Package for the Unit 4 ITAAC 2.2.01.04a.ii [Index number 96]"