ND-18-1101, Unit 4 - Resubmittal Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.02.11a.i (Index Number 154)

Unit 4 - Resubmittal Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.02.11a.i (Index Number 154)

ML18235A313
Person / Time
Site:	Vogtle
Issue date:	08/20/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.2.02.11a.i, ND-18-1101
Download: ML18235A313 (8)

Text

Southern Nuclear AUG 2 0 2018 Docket Nos.:

52-025 52-026 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 Resubmittal Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.02.11a.i [Index Number 1541 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as ofAugust 14, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.02.1 la.i [Index Number 154] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the planfor completing this ITAAC. Southern Nuclear Operating Companywill, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

Southern Nuclear Operating Company(SNC) previously submitted Notice of Uncompleted ITAAC 225-days Priorto Initial Fuel Loadfor Item 2.2.02.1 la.i [Index Number 154] ND-18-0805

[ML18171A075] dated June 18, 2018. This resubmittal supersedes ND-18-0805 in itsentirety.

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 NRCto 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.

Respectfully submitted Michael J. Yox Regulatory Affairs Direc^r Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.02.1la.i [Index Number 154]

MJY/SBB/amw Michael J. Yox Regulatory Affairs Director Vogtle 3 &4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei 410-474-8587 ceii myox@southernco.com ND-18-1101 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission ND-18-1101 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

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

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

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

Mr. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Parton Ms. A. L. Pugh Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. C. T. Defnall Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc; Nuclear Reoulatorv Commission Mr. W. Jones (w/o enclosures)

Mr. F. D. Brown Ms. J. M. Heisserer Ms. A. E. Rivera-Varona Mr. M. E. Ernstes Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Oalethorpe Power Corporation Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-18-1101 Page 3 of 3 Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan 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. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-1101 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-18-1101 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.02.1 la.i [Index Number 154]

U.S. Nuclear Regulatory Commission ND-18-1101 Enclosure Page 2 of 5 ITAAC Statement Desion Commitment 11.a)The motor-operated valves identified in Table 2.2.2-1 perform an active safety-related function to change position as indicated inthe table.

Insoections/Tests/Analvses i) Tests ortype tests ofmotor-operated valves will be performed to demonstrate the capability of the valve to operate under its design conditions.

ii) Inspection will be performed for the existence ofa report verifying thatthe capability ofthe as-built motor-operated valves bound the tested conditions.

Acceptance Criteria i) Atest report exists and concludesthat each motor-operated valve changes position as indicated in Table 2.2.2-1 under design conditions.

ii) Areport existsand concludes thatthe capability ofthe as-built motor-operated valves bound the tested conditions.

ITAAC Completion Description Multiple Inspections, Tests, Analyses, and AcceptanceCriteria (ITAAC) are performed to demonstrate that the Passive Containment Cooling System (PCS) motor-operated valves identified inthe Combined License (COL) Appendix C, Table 2.2.2-1 perform an active safety-related function to change position as indicated inthe table.

\\) A test report exists and concludes that each motor-ooerated valve changes position as indicated in Table 2.2.2-1 under desion conditions.

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

The motor-operated valves identified inCOL Appendix C, Table 2.2.2-1 are qualified in accordance with the provisionsof American Societyof 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 conditionsidentified inthe 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.

U.S. Nuclear Regulatory Commission ND-18-1101 Enclosure Page 3 of 5 Type testing is performed, including natural frequency determination, sideload static deflection testing, final static seat and stem leakage testing, steamtesting, and water testing, for the ranges of the pressure, temperature andflow for eachvalve andthe 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 andactuator internal inspections and measurement, orientation requirements, seat andstem leakage limitations, diagnostic datacollection andanalysis methods, static and dynamic flow diagnostic testing, and pressurelocking and thermal binding evaluations. Thequalification alsofollowed the provisions of ASME QME-1-2007 forthe extrapolation offunctional qualification to another valve assembly, and demonstration of functional capability of production valve assemblies.

The results ofthe qualification are documented in the Equipment Qualification (EQ) Reports (Reference 3) which are identified in Attachment Aforeach applicablevalve. These reports summarize the test methodology and ASME QME-1-2007 functional qualification that demonstrate that each motor-operated valve changes position as indicated inVEGP Unit 3 and Unit 4 COL Appendix 0 Table 2.2.2-1 under design conditions.

iil A reoort exists and concludes that the caoabilitv of the as-built motor-operated valves bound the tested conditions.

This portion of the subject ITAAC requires that an inspection is performedfor the existence of a report verifying that the capabilityof the as-built motor-operated valves bound the tested conditions.

The motor-operated valves in VEGP Unit 3 and Unit 4 CQL Appendix C Table 2.2.2-1 are verified by tests in accordance with section i) above, to demonstrate the capabilityof 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 PCS to confirm the satisfactory installation of the motor-operated valves. The inspection includes verificationof equipment make/model/serial number, verificationof equipment mounting and location, and verificationthat 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 verifythat the installed configuration of the motor-operated valves identified in VEGP Unit3 and Unit4 CQL Appendix C Table 2.2.2-1 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 2.2.2-1 under design conditions; and

U.S. Nuclear Regulatory Commission ND-18-1101 Enclosure Page 4 of 5 Areport exists and concludes thatthe capability of theas-built motor-operated valves bound the tested conditions.

References 3 and 5 are available for NRG inspection as part ofthe Unit 3 and Unit 4 ITAAC 2.2.02.11a.iCompletion Packages (References 6 and 7, respectively).

List of ITAAC Findings In accordance with plantproceduresfor ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review ofall ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which includes now-consolidated ITAAC Index 155, 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 /available for NRC 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 MotorOperated 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 IT/\\AC Guideline" 5.

As-Built Equipment Qualification Reconciliation Reports (EQRR) as identified in Attachment A for Units 3 and 4 6.

2.2.02.11a.i-U3-CP-RevO, "Completion Package for Unit 3 ITAAC 2.2.02.1 la.i [Index Number 154]"

7.

2.2.02.11 a.i-U4-CP-RevO, "Completion Package for Unit 4 ITAAC 2.2.02.11 a.i [Index Number 154]"

8.

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

U.S. Nuclear Regulatory Commission ND-18-1101 Enclosure Page 5 of 5 Attachment A System: Passive ContainmentCooling System (PCS)

Equipment Name

• Tag No. +

Active Function ^

EQ Reports (Reference 3)

As-Bullt EQRR (Reference 5)*

PCCWST Isolation Valve MOV PCS-PL-V001C Transfer Open APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.2.02.11a.i-U3-EQRR-PCDXXX PCCWST Isolation Block MOV PCS-PL-V002A Transfer Open APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.2.02.11a.i-U3-EQRR-PCDXXX PCCWST Isolation Block MOV PCS-PL-V002B Transfer Open APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.2.02.11a.i-U3-EQRR-PCDXXX PCCWST Isolation Block MOV PCS-PL-V002C Transfer Open APP-PV01-VBR-011 /

APP-PV01-VBR-012 2.2.02.11a.i-U3-EQRR-PCDXXX Notes:

Excerpt from COL Appendix C Table 2.2.2-1

• The Unit 4 As-Built EQRR are numbered "2.2.02.11a.i-U4-EQRR-PCDXXX"