ND-18-0454, Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.12a.i (Index Number 214)

Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.12a.i (Index Number 214)

ML18106A742
Person / Time
Site:	Vogtle
Issue date:	04/05/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0454
Download: ML18106A742 (8)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell myox@southernco.com APR 0 5 20ie Docket Nos.: 52-025 52-026 ND-18-0454 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 2.2.03.12a.i [Index Number 2141 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 1, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.12a.i [Index Number 214] has not been completed greater than 225-days priorto 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 priorto 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 priorto 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.

R^pectfully submit Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.12a.i [Index Number 214]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0454 Page 2 of 3 To:

Southern Nuclear Operating Companv/ 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. 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 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 Ooiethorpe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0454 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Eiectric 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., CDS 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-18-0454 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0454 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.12a.i [Index Number 214]

U.S. Nuclear Regulatory Commission ND-18-0454 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 12.a) The squib valves and check valves identified in Table 2.2.3-1 perform an active safety-related function to change position as indicated in the table.

Inspections. Tests. Analvses i) Tests or type tests of squib valves will be performed that demonstrate the capability of the valve to operate under its design condition.

ii) Inspection will be performed forthe existence of a reportverifying that the as-built squib valves are bounded by the tests or type tests.

Acceptance Criteria i) Atest report exists and concludes that each squib valve changes position as indicated in Table 2.2.3-1 under design conditions.

ii) A report exists and concludes that the as-built squib valves are bounded by the tests or type tests.

ITAAC Completion Description Multiple Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) are performed to demonstrate that the Passive Core Cooling System (PXS) squib valves and check valves identified in the Combined License (COL) Appendix C, Table 2.2.3-1 perform an active safety-related function to change position as indicated in the table.

\) A test report exists and concludes that each souib valve chances position as indicated in Table 2.2.3-1 under design conditions.

This portion of the subject ITAAC requires tests ortype tests of squib valves to be performed to demonstrate the capability of the valve to operate under its design conditions.

Thefunctional qualification program for the API 000 squib valves is developed based on American Society of Mechanical Engineers (ASME) QME-1-2007, "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants" (Reference 1). The qualification was based on the ASME QME-1-2007 requirements for power operated valve assemblies.

Functional qualification is performed under the design conditions identified in the design specification for the valves (Reference 2) to demonstrate thateach squib valve is qualified to perform its designated function when used in its intended service. In accordance with ASME QME-1-2007, qualification is substantiated bydemonstrating the relationship between the service requirements and the type testing and analysis that was conducted as partofthis qualification program.

Type testing is performed, including natural frequency determination, sealing capability testing, functional operation, and flow characteristics, for the rangesof the pressure, temperature and

U.S. Nuclear Regulatory Commission ND-18-0454 Enclosure Page 3 of 5 flow for eacfi valve. In accordance with ASME QME-1-2007, the functional qualification process for these valves also included valve internal inspections, actuator inspection and testing, orientation requirements, leakage limitations, diagnostic data collection and analysis methods, static and dynamic flow diagnostic testing, and thermal binding evaluations.

The results of the qualification are documented in the Equipment Qualification (EG) 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 squib valve changes position as indicated in VEGP Unit 3 and Unit 4 COL Appendix 0 Table 2.2.3-1 under design conditions.

\i) A report exists and concludes that the as-built souib valves are bounded bv the tests or tvoe tests.

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

The squib valves in VEGP Unit 3 and Unit 4 COL Appendix C Table 2.2.3-1 are verified by type tests in accordance with ITAAC 2.2.03.12a.i (above) to demonstrate the capability of the valves to operate under their design conditions. The EO Reports in Attachment A identify the equipment mounting employed forthe testing and the specific conditions tested.

In accordance with the EO Walkdown Inspection ITAAC Guideline (Reference 4), an inspection is conducted of the PXS to confirm the satisfactory installation of the squib 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 squib valves includes photographs and/or sketches of equipment mounting and connections. The verification of installed component configuration is documented in the EO As-Built Reconciliation Report(s) (EORR) (Reference 5).

Attachment A identifiesthe EORR which verify that the installed configuration of the squib valves identified in VEGP Unit 3 and Unit 4 COL Appendix 0 Table 2.2.3-1 are bounded by the tests or type tests.

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

• Atest report exists and concludes that each squib valve changes position as indicated in Table 2.2.3-1 under design conditions; and

• A report exists and concludes that the as-built squib valves are bounded bythe tests or type tests.

References 3 and 5 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.2.03.12a.i Completion Packages (References 6 and 7, respectively).

U.S. Nuclear Regulatory Commission ND-18-0454 Enclosure Page 4 of 5 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 included now-consolidated ITAAC Index 215, found the following relevant ITAAC findings associated with this ITAAC:

• Notice of Nonconformance 99900080/2013-201-01 (Closed)

• Notice of Nonconformance 99900080/2013-201 -02 (Closed)

• Notice of Nonconformance 99900080/2012-201-01 (Closed)

• Notice of Nonconformance 99900404/2012-201-01 (Closed)

• Notice of Nonconformance 99900404/2012-201 -02 (Closed)

• Notice of Nonconformance 99900404/2012-201 -03 (Closed)

References (available 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-PV70-Z0-001 Revision X, "Squib (Pyrotechnic Actuated) Valves, ASME Boiler and Pressure Vessel Code,Section III Class 1"

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. 2.2.03.12a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.2.03.12a.i [Index Number 214]"

7. 2.2.03.12a.i-U4-CP-Rev X, "Completion Package for Unit 4 IT/\AC 2.2.03.12a.i [Index Number 214]"

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

U.S. Nuclear Regulatory Commission ND-18-0454 Enclosure Page 5 of 5 Attachment A System: Passive Core Cooling System (PXS)

Active Equipment Name

• Tag No.

• EQ Reports (Reference 3) As-Buiit EQRR (Reference 5)*

Function +

Containment 2.2.03.12a.i-U3-EQRR-Transfer APP-PV70-VBR-002 /

Recirculation A Squib PXS-PL-V118A Open APP-PV70-VBR-003 PCDXXX Valve Containment APP-PV70-VBR-002 /

Transfer 2.2.03.12a.i-U3-EQRR-Recirculation B Squib PXS-PL-V118B APP-PV70-VBR-003 PCDXXX Open Valve Containment APP-PV70-VBR-002 /

Transfer 2.2.03.12a.i-U3-EQRR-Recirculation A Squib PXS-PL-V120A APP-PV70-VBR-003 Open PCDXXX Valve Containment APP-PV70-VBR-002 /

Transfer 2.2.03.12a.i-U3-EQRR-Recirculation B Squib PXS-PL-V120B APP-PV70-VBR-003 Open PCDXXX Valve IRWST Injection A Transfer APP-PV70-VBR-002 / 2.2.03.12a.i-U3-EQRR-PXS-PL-V123A Squib Valve Open APP-PV70-VBR-003 PCDXXX IRWST Injection B Transfer APP-PV70-VBR-002 / 2.2.03.12a.i-U3-EQRR-PXS-PL-V123B Squib Valve Open APP-PV70-VBR-003 PCDXXX IRWST Injection A Transfer APP-PV70-VBR-002 / 2.2.03.12a.i-U3-EQRR-PXS-PL-V125A Squib Valve Open APP-PV70-VBR-003 PCDXXX IRWST Injection B Transfer APP-PV70-VBR-002 / 2.2.03.12a.i-U3-EQRR-PXS-PL-V125B Squib Valve Open APP-PV70-VBR-003 PCDXXX Notes:

+Excerpt from COL Appendix C Table 2.2.3-1

• The Unit 4 As-Built EQRR are numbered "2.2.03.12a.i-U4-EQRR-PCDXXX"