ND-20-0195, ITAAC Closure Notification on Completion of ITAAC 2.1.03.02a (Index Number 69)

ITAAC Closure Notification on Completion of ITAAC 2.1.03.02a (Index Number 69)

ML20115E455
Person / Time
Site:	Vogtle
Issue date:	04/24/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.1.03.02a, ND-20-0195
Download: ML20115E455 (9)

Text

Southern Nuclear Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel April 24, 2020 Docket Nos.;52-025 ND-20-0195 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 ITAAC Closure Notification on Completion of ITAAC 2.1.03.02a [Index Number 691 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 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.03.02a [Index Number 69], for verifying the Reactor System (RXS) accommodates the fuel and control assemblies. The closure process for this ITAAC is based on the guidance described in NEI 01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52", which is 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.

Michael J. Yox Regulatory Affairs Direbtor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of 2.1.03.02a [Index Number 69]

MJY/WLP/sfr

U.S. Nuclear Regulatory Commission ND-20-0195 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company M Peter P. Sena III (w/o enclosures)

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

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

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

M G. Chick M M. Page M P. Martino M M. J. Yox M A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R.L Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

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

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. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Mr. C. Santos Mrs. M. Bailey Mr. S. Rose Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Carrington Mr. P. Heher

U.S. Nuclear Regulatory Commission ND-20-0195 Page 3 of 3 Mr. M. King Mr. E. Davidson Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company. LLC Dr. L. Orlani (w/o enclosures)

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

Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-20-0195 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-20-0195 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 iTAAC Giosure Notification on Compietion of iTAAC 2.1.03.02a [Index Number 69]

U.S. Nuclear Regulatory Commission ND-20-0195 Enclosure Page 2 of 6 ITAAC Statement Design Commitment:

2.a) The reactor upper internals rod guide arrangement is as shown in Figure 2.1.3-1.

2.b) The control assemblies (rod cluster and gray rod) and drive rod arrangement is as shown in Figure 2.1.3-2.

Inspections. Tests. Analvses:

Inspection of the as-built system will be performed.

Inspection of the as-built system will be performed.

Acceptance Criteria:

The as-built RXS will accommodate the fuel assembly and control rod drive mechanism pattern shown in Figure 2.1.3-1.

The as-built RXS will accommodate the control assemblies (rod cluster and gray rod) and drive rod arrangement shown in Figure 2.1.3-2.

ITAAC Determination Basis This ITAAC requires inspections be performed of the as-built Reactor System (RXS)to verify the reactor upper internals rod guide pattern is as shown in the Combined License(COL) Appendix C Figure 2.1.3-1 (Attachment A)and the control assemblies (rod cluster and gray rod) and drive rod arrangement are as shown in COL Appendix C Figure 2.1.3-2 (Attachment B).

Inspections of the as-built RXS were performed to verify that the reactor upper internals rod guide pattern is as shown in Figure 2.1.3-1 (Attachment A)and that the control assemblies (rod cluster and gray rod) and drive rod arrangement are as shown in Figure 2.1.3-2(Attachment B).

Additionally, a review of inspection records verified that the as-built dimensions of the Reactor Vessel Internals are as shown in COL Appendix C Table 2.1.3-4(Attachment C).

Dimensional inspections were performed at the vendor's facility. Due to the nature of the manufacturing process of the reactor vessel head and internals, it was necessary to verify measurements were within the ITAAC acceptable ranges prior to shipment and final installation.

Completing these measurements at the vendor's facility meets the definition of "as-built inspections" per NEI 08-01, Section 9.5, "As-builf Inspections (Reference 1).

U.S. Nuclear Regulatory Commission ND-20-0195 Enclosure Page 3 of 6 The inspection results are documented in the Principle Closure Documents(References 2 and 3) supporting the ITAAC 2.1.03.02a Completion Package (Reference 4)and confirm that the Unit 3 as-built RXS will accommodate the fuel assembly and control rod drive mechanism pattern shown in Figure 2.1.3-1 and will accommodate the control assemblies (rod cluster and gray rod) and drive rod arrangement shown in Figure 2.1.3-2. References 2 and 3 are available for NRC inspection as part of the ITAAC 2.1.03.02a Completion Package (Reference 4).

ITAAC Finding Review 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.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.03.02a was performed for VEGP Unit 3 and that the prescribed acceptance criteria are 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. NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52

2. SV3-MI01-VQQ-002, Revision 9, API000 Reactor Vessel Internals(QR & C of C)

3. LTR-ARIDA-20-1, Revision 0, Use of Vogtle Unit 3 As-Built Reactor Vessel Internals Data to Support Dimensions J and K as Related to ITAAC Item 2.1.03.02a (Index Number 69)

4. 2.1.03.02a-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-20-0195 Enclosure Page 4 of 6 Attachment A: COL Appendix 0 Figure 2.1.3-1 The Reactor Upper Internals Rod Guide Arrangement(Attachment A) was Verified to accommodate the fuel assembly and control rod drive mechanism pattern per inspection of SV3-MI01-VQQ-002, page 2261, Section A-A (Reference 2).

ROD GUIDE LDCATIDNS FUEL ASSEMBLY PATTERN Figure 2.1.3-1 Reactor Upper Internals Rod Guide Arrangement

U.S. Nuclear Regulatory Commission ND-20-0195 Enclosure Page 5 of 6 Attachment B: COL Appendix 0 Figure 2.1.3-2 Labeled Items and configurations were verified per Inspection of Reference 2. Dimensions J and K were verified per Inspection of Reference 3(see Table 2.1.3-4, Attachment 0).

CRDM REACTOR PRESSURE VESSEL MATING SURFACE UPPER GUIDE STRUCTURE UPPER SUPPORT PLATE LOWER GUIDE STRUCTURE UPPER CORE PLATE LOWER CORE SUPPORT PLATE

U.S. Nuclear Regulatory Commission ND-20-0195 Enclosure Page 6 of 6 Figure 2.1.3-2 Rod Cluster Control and Drive Rod Arrangement Attachment 0 Table 2.1.3-4*

Key Dimensions and Acceptable Variations of the Reactor Vessel Internals (Figure 2.1.3-2)

Dimension Nominal Acceptable QR & 0 of 0 or Description* Value* Variation* Values - Min. to Elevation*

(inches) (inches) Max**(inches)

(inches)

Elevation from RV mating surface J 327.3 +0.50/-0.50 327.300 -327.305 to top of lower core support plate Separation distance between bottom of upper core plate and K 189.8 +0.20/-0.20 189.786-189.804 top of lower core support with RV head in place

- Excerpt from COL Appendix C Table 2.1.3-4 Min to Max dimensions taken from Westinghouse letter LTR-ARIDA-20-1 (Reference 3)