ND-18-0293, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.12A.iv (Index Number 56)

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Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.12A.iv (Index Number 56)
ML18065A056
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/02/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.1.02.12A.iv, ND-18-0293
Download: ML18065A056 (9)
v • d • e


Text

Michael J. Yox 7825 River Road Regulatory Affairs Director WaynesiDoro, GA 30830 Southern Nuclear Vogtle 3 & 4 706-848-6459 tei MAR 0 2 2018 410-474-8587 ceii myox @southernco.com Docket Nos.: 52-025 52-026 ND-18-0293 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 2.1.02.12a.iv [Index Number 561 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of February 27, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.12a.iv

[Index Number 56] 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

U.S. Nuclear Regulatory Commission ND-18-0293 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.iv [Index Number 56]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0293 Page 3 of 4 To:

Southern Nuclear Operating Company/ 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. Yox Mr. D. L. Fulton Mr. J. D. Williams Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. 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 Oalethoroe Power Corporation Mr. R. B. Brinkman MuniclDal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0293 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. OrlanI (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. Deangells 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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-0293 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0293 Enclosure Vogtle Electric Generating Riant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.iv [Index Number 56]

U.S. Nuclear Regulatory Commission ND-18-0293 Enclosure Page 2 of 5 ITAAC Statement Design Commitment 12.a) The automatic depressurization valves identified in Table 2.1.2-1 perform an active safety-related function to change position as indicated in the table.

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

v) Inspection will be performedfor the existence of a report verifying that the as-built squib valves are bounded by the tests or type tests.

Acceptance Criteria iv) Atest report exists and concludes that each squib valvechanges position as indicated in Table 2.1.2-1 under design conditions.

v) 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 Reactor Coolant System (RCS) automaticdepressurization (squib) valves identified in the Combined License (COL) Appendix C, Table 2.1.2-1 perform an active safety-related function to change position as indicated in the table.

ivi A test report exists and concludes that each souib valve chances position as indicated in Table 2.1.2-1 under design conditions.

This acceptance criteria requires tests or type tests ofsquibvalves to be performed to demonstrate the capability of the valve to operate under its design conditions.

The functional qualification program for the API 000 squib valves is developed based on American Society of Mechanical Engineers (ASME) QME-1-2007, "Qualification ofActive 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 underthe 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 partof this qualification program.

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

U.S. Nuclear Regulatory Commission ND-18-0293 Enclosure Page 3 of 5 flow for each 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 Unit4 COL Appendix C Table 2.1.2-1 under design conditions.

v1 A report exists and concludes that the as-built souib valves are bounded bv the tests or type tests.

This acceptance criteria requires that an inspection is performedfor 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 2.1.2-1 are verified by the type tests in accordance with ITAAC 2.1.02.12a.iv (above) to demonstrate the capability ofthe 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 Inspection ITAAC Guideline (Reference 4), an inspection is conducted of the RCS 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 EQ As-Built Reconciliation Report(s) (EQRR) (Reference 5).

AttachmentA identifies the EQRR which verify that the installed configuration of the squib valves identified in VEGP Unit 3 and Unit 4 COLAppendix 0 Table 2.1.2-1 are bounded by the tests or type tests.

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

  • Atest report exists and concludes that each squib valve changes position as indicated in Table 2.1.2-1 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 2.1.02.12a.iv Completion Packages (References 6 and 7, respectively).

U.S. Nuclear Regulatory Commission ND-18-0293 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 57, 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)

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. 2.1.02.12a.iv-U3-CP-RevX, "Completion Package for Unit 3 ITAAC 2.1.02.12a.iv [Index Number 56]"
7. 2.1.02.12a.iv-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.1.02.12a.iv [Index Number 56]"
8. NEI 08-01, "Industry Guideline for the IT/WC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0293 Enclosure Page 5 of 5 Attachment A System; Reactor Coolant System (RCS)

Active Equipment Name

  • Tag No.
  • Function EQ Reports (Reference 3) As-Built EQRR (Reference 5)*

+

Fourth-stage ADS Transfer APP-PV70-VBR-005 / 2.1.02.12a.iv-U3-EQRR-RCS-PL-V004A Squib Valve Open APP-PV70-VBR-004 PCDXXX Fourth-stage ADS Transfer APP-PV70-VBR-005 / 2.1.02.12a.iv-U3-EQRR-RCS-PL-V004B Squib Valve Open APP-PV70-VBR-004 PCDXXX Fourth-stage ADS Transfer APP-PV70-VBR-005/ 2.1.02.12a.iv-U3-EQRR-RCS-PL-V004C Squib Valve Open APP-PV70-VBR-004 PCDXXX Fourth-stage ADS Transfer APP-PV70-VBR-005 / 2.1.02.12a.iv-U3-EQRR-RCS-PL-V004D Squib Valve Open APP-PV70-VBR-004 PCDXXX Notes:

+Excerpt from COL Appendix C Table 2.1.2-1

  • The Unit 4 As-Built EQRR are numbered "2.1.02.12a.iv-U4-EQRR-PCDXXX"
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