ND-18-0816, Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.11a.i (Index Number 114)

Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.01.11a.i (Index Number 114)

ML18171A053
Person / Time
Site:	Vogtle
Issue date:	06/18/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.01.11a.i, ND-18-0816
Download: ML18171A053 (8)

Text

Michael J. Yox 7825 River Road

^ Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel 410-474-8587 cell JUL 1 8 2018 myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0816 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 2.2.01.Ila.i findex Number 1141 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 11, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.01.1 la.i [Index Number 114] 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 f^otifications 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.

J\rAawda Michael J. Yox Vv£ll

^

^ W Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.11 a.i [Index Number 114]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-18-0816 Page 2 of 3 To:

Southern Nuclear Operating Companv/ Georgia Power Company M D. A. Bost (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 M A. 8. Parton M W. A. Sparkman M C. E. Morrow Ms. K. M. Stacy M M. K. Washington M . 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 Qqiethoroe Power Corporation Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0816 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric ComDanv. 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. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0816 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0816 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.01.11a.i [Index Number 114]

U.S. Nuclear Regulatory Commission ND-18-0816 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 11.a) The motor-operated and check valves identified in Table 2.2.1-1 perform an active safety-related function to change position as indicated in the table.

Insoections. Tests. Analvses i) Tests or type tests of motor-operated valves will be performed to demonstrate the capability of each valve to operate under design conditions.

ii) Inspection will be performed for the existence of a report verifying that the as-built motor-operated valves are bounded by the tests or type tests.

Acceotance Criteria i) Atest report exists and concludes that each motor-operated valve changes position as indicated in Table 2.2.1-1 under design conditions.

ii) A report exists and concludes that the as-built motor-operated valves are bounded bythe tests or type tests.

ITAAC Completion Description Multiple Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are performed to demonstrate that the Containment System (CMS) motor-operated valves identified in the Combined License (COL) Appendix C, Table 2.2.1-1 perform an active safety-related function to change position as indicated in the table.

\) A test report exists and concludes that each motor-operated valve changes oosition as indicated in Table 2.2.1-1 under design conditions.

This portion of the subject ITAAC requires tests ortype tests of motor-operated valves to be performed to demonstrate the capability ofthe valve to operate under itsdesign conditions.

The motor-operated valves identified in COL Appendix C, Table2.2.1-1 are qualified in accordance with the provisions of American Society of Mechanical Engineers (ASME)

QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants" (Reference 1).

Functional qualification is performed underthe design conditions identified in the design specification for the valves (Reference 2) to demonstrate that each motor-operated valve is qualified to perform its designated function when used in its intended service. In accordance with ASME QME-1-2007, qualification is substantiated by demonstrating the relationship between the service requirements and the type testing and analysis that was conducted as part of this qualification program.

Type testing is performed, including natural frequency determination, side load static deflection testing, final static seat and stem leakage testing, steam testing, and water testing, for the

U.S. Nuclear Regulatory Commission ND-18-0816 Enclosure Page 3 of 5 ranges of the pressure, temperature and flow for each valve and the maximum seat-sealing differential pressure. In accordance with ASME QME-1-2007, the functional qualification process for these motor-operated valve assemblies also included valve and actuator internal inspections and measurement, orientation requirements, seat and stem leakage limitations, diagnostic data collection and analysis methods, static and dynamic flow diagnostic testing, and pressure locking and thermal binding evaluations. The qualification also followed the provisions of ASME QME-1-2007 for the extrapolation of functional qualification to another valve assembly, and demonstration of functional capability of production valve assemblies.

The results of the qualification are documented in the Equipment Qualification (EQ) Reports (Reference 3) which are identified in Attachment A for each applicable valve. These reports summarize the test methodology and ASME QME-1-2007 functional qualification that demonstrate that each motor-operated valve changes position as indicated in VEGP Unit 3 and Unit 4 COL Appendix 0 Table 2.2.1-1 under design conditions.

ii) A report exists and concludes that the as-built motor-operated valves are bounded bv the tests or tvpe tests.

This portion of the subject ITAAC requires that an inspection is performed for the existence of a report verifying that the as-built motor-operated valves are bounded by tests or type tests.

The motor-operated valves in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.2.1-1 are verified by type tests in accordance with ITAAC 2.2.01.1 la.i to demonstrate the capability of the valves to operate under their design conditions. The EQ Reports in Attachment A identify the equipment mounting employed for the testing and the specific conditions tested.

In accordance with the EQ Walkdown ITAAC Guideline (Reference 4), an inspection is conducted of the CNS to confirm the satisfactory installation of the motor-operated valves. The inspection includes verification of equipment make/model/serial number, verification of equipment mounting and location, and verification that the mechanical and electrical connections are bounded by the tested conditions.

The documentation of installed configuration of the motor-operated valves includes photographs and/or sketches of equipment mounting and connections. The verification of installed component configuration is documented in the As-Built EQ Reconciliation Report(s) (EQRR)

(Reference 5).

Attachment A identifies the EQRR which verify that the installed configuration of the motor-operated valves identified in VEGP Unit 3 and Unit 4 COL Appendix 0 Table 2.2.1-1 are bounded by the tests or type tests.

Together, these EQ Reports and EQRR (References 3 and 5), provide evidence that the ITAAC Acceptance Criteria requirements are met:

• A test report exists and concludes that each motor-operated valve changes position as indicated in Table 2.2.1-1 under design conditions; and

• A report exists and concludes that the as-built motor-operated valves are bounded by the tests or type tests.

U.S. Nuclear Regulatory Commission ND-18-0816 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.01.11a.i Completion Packages (References 6 and 7, respectively).

List of ITAAC Findings 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 finding review, which includes now-consolidated ITAAC Index 115, found the following relevant ITAAC finding associated with this ITAAC:

• Unresolved Item (URI)05200025/2017002-02 (closed)

References favallable for NRG inspection)

1. American Society of Mechanical Engineers (ASME) QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants"

2. APP-PV11-Z0-001 Revision X, "Design Specification for Butterfly Valves, ASME Boiler and Pressure Vessel Code Section III, Class 2 and 3"

3. Equipment Qualification (EQ) Reports as identified in Attachment A

4. ND-XX-XX-001, EQ Walkdown ITAAC Guideline

5. As-Built Equipment Qualification Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4

6. 2.2.01.11a.i-U3-CP- RevO, ITAAC Completion Package

7. 2.2.01.11a.i-U4-CP- RevO, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-18-0816 Enclosure Page 5 of 5 Attachment A System: Containment System (CNS)

Active EQ Reports As-Built EQRR Equipment Name ^ Tag No. * (Reference 5)*

Function * (Reference 3)

Component Cooling Water System (CCS) Containment Isolation Motor-operated CCS-PL- Transfer APP-PV11-VBR-005/ 2.2.01.11a.i-U3-Valve (MOV) - Inlet Line V200 Closed APP-PV11-VBR-006 EORR-PCDXXX Outside Reactor Containment (ORC)

CCS Containment Isolation CCS-PL- Transfer APP-PV11-VBR-005/ 2.2.01.11a.i-U3-MOV - Outlet Line IRC V207 Closed APP-PV11-VBR-006 EORR-PCDXXX CCS Containment Isolation CCS-PL- Transfer APP-PV11-VBR-005/ 2.2.01.11a.i-U3-MOV - Outlet Line ORC V208 Closed APP-PV11-VBR-006 EORR-PCDXXX SFS Discharge Line Transfer APP-PV11-VBR-005/ 2.2.01.11a.i-U3-Containment Isolation MOV SFS-PL-V038 Closed APP-PV11-VBR-006 EORR-PCDXXX

-ORC SFS Suction Line Transfer APP-PV11-VBR-005/ 2.2.01.11a.i-U3-Containment Isolation MOV SFS-PL-V034 Closed APP-PV11-VBR-006 EORR-PCDXXX

-IRC SFS Suction Line Transfer APP-PV11-VBR-005/ 2.2.01.11a.i-U3-Containment Isolation MOV SFS-PL-V035 Closed APP-PV11-VBR-006 EORR-PCDXXX

-ORC Transfer Vacuum Relief Containment VFS-PL- Closed / APP-PV11-VBR-005/ 2.2.01.11 a.i-U3-Isolation A MOV - ORC V800A Transfer APP-PV11-VBR-006 EORR-PCDXXX Open Transfer Vacuum Relief Containment VFS-PL- Closed / APP-PV11-VBR-005/ 2.2.01.11a.i-U3-Isolation B MOV - ORC V800B Transfer APP-PV11-VBR-006 EORR-PCDXXX Open Notes:

Excerpt from COL Appendix C Table 2.2.1-1

• The Unit 4 As-Built EQRR are numbered "2.2.01.11a.i-U4-EQRR-PCDXXX"