ND-18-0845, Voglte, Units 3 and 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel and Load Item 2.1.02.12a.i (Index Number 53)

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Voglte, Units 3 and 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel and Load Item 2.1.02.12a.i (Index Number 53)
ML18177A135
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 06/25/2018
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.1.02.12a.i, ND-18-0845
Download: ML18177A135 (8)
v • d • e


Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 706-848-6459 tei Vogtie 3 & 4 410-474-8587 ceii JUN 2 5 20t8 myox @southernco.com Docket Nos.: 52-025 52-026 ND-18-0845 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.12a.l [Index Number 531 Ladles and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as ofJune 12, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.1.02.12a.l [Index Number 53]

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, oranalyses 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 Vogtie 3 &4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.l [Index Number 53]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-18-0845 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (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. 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 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0845 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse Electric 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. Hesler, 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-18-0845 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-0845 Enclosure Vogtle Electric Generating Riant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.12a.i [Index Number 53]

U.S. Nuclear Regulatory Commission ND-18-0845 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 i) Tests or type tests of motor-operated valves will be performed that demonstrate the capability of the valve to operate under its 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.

Acceptance Criteria i) Atest report exists and concludes thateach motor-operated valve changes position as indicated in Table 2.1.2-1 under design conditions.

ii) Areport exists and concludes that the as-built motor-operated 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) motor-operated 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.

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

This portion of the subject ITAAC requires tests or type tests of motor-operated valves to be performed to demonstrate the capability of the valve to operate under its design conditions.

The motor-operated valves identified in COL Appendix C, Table 2.1.2-1 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 under the 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 issubstantiated by demonstrating the relationship between the service requirements and the type testing and analysis thatwas 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-18-0845 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 2.1.2-1 under design conditions.

ii) A report exists an^ 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 2.1.2-1 are verified by type tests in accordance with ITAAC 2.1.02.12a.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 RCS 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 2.1.2-1 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 2.1.2-1 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-18-0845 Enclosure Page 4 of 5 References 3 and 5 are available for NRG inspection as part of the Unit 3 and Unit 4 ITAAC 2.1.02.12a.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 54, found the following relevant ITAAC findings associated with this ITAAC:

  • Notice of Nonconformance 99900905/2012-201-01 (closed)
  • Notice of Nonconformance 99900905/2012-201 -04 (closed)

References favailable 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-PV01 -ZO-001 Revision X, "3" and Larger Motor Operated Gate and Globe Valves, ASME Boiler and Pressure Vessel Code Section III, Class 1,2, 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. 2.1.02.12a.i-U3-CP-RevO, ITAAC Completion Package
7. 2.1.02.12a.i-U4-CP-RevO, IT/\AC Completion Package
8. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-18-0845 Enclosure Page 5 of 5 Attachment A System: Reactor Coolant System (RCS)

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

Function * (Reference 3)

First-stage ADS Motor- RCS-PL-Transfer Open APP-PV01-VBR-013/ 2.1.02.12a.i-U3-operated Valve (MOV) V001A APP-PV01-VBR-014 EQRR-PCDXXX RCS-PL- APP-PV01-VBR-013/ 2.1.02.12a.i-U3-First-stage ADS MOV Transfer Open V001B APP-PV01-VBR-014 EQRR-PCDXXX Second-stage ADS RCS-PL-Transfer Open APP-PV01-VBR-013/ 2.1.02.12a.i-U3-MOV V002A APP-PV01-VBR-014 EORR-PCDXXX Second-stage ADS RCS-PL- APP-PV01-VBR-013/ 2.1.02.12a.i-U3-Transfer Open EORR-PCDXXX MOV V002B APP-PV01-VBR-014 RCS-PL- APP-PV01-VBR-013/ 2.1.02.12a.i-U3-Third-stage ADS MOV Transfer Open EORR-PCDXXX V003A APP-PV01-VBR-014 RCS-PL- APP-PV01-VBR-013/ 2.1.02.12a.i-U3-Third-stage ADS MOV Transfer Open EORR-PCDXXX V003B APP-PV01-VBR-014 First-stage ADS RCS-PL- APP-PV01-VBR-011 / 2.1.02.12a.i-U3-Transfer Open EORR-PCDXXX Isolation MOV V011A APP-PV01-VBR-012 First-stage ADS RCS-PL- APP-PV01-VBR-011 / 2.1.02.12a.i-U3-Transfer Open APP-PV01-VBR-012 EORR-PCDXXX Isolation MOV V011B Second-stage ADS RCS-PL- APP-PV01-VBR-011 / 2.1.02.12a.i-U3-Transfer Open EORR-PCDXXX Isolation MOV V012A APP-PV01-VBR-012 Second-stage ADS RCS-PL- APP-PV01-VBR-011 / 2.1.02.12a.i-U3-Transfer Open EORR-PCDXXX Isolation MOV V012B APP-PV01-VBR-012 Third-stage ADS RCS-PL- APP-PV01-VBR-011 / 2.1.02.12a.i-U3-Transfer Open APP-PV01-VBR-012 EORR-PCDXXX Isolation MOV V013A Third-stage ADS RCS-PL- APP-PV01-VBR-011 / 2.1.02.12a.i-U3-Transfer Open EORR-PCDXXX Isolation MOV V013B APP-PV01-VBR-012 Notes:

Excerpt from COL Appendix C Table 2.1.2-1

  • Tfie Unit 4 As-Built EQRR are numbered "2.1.02.12a.i-U4-EQRR-PCDXXX"
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