ND-18-0225, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.05.i (Index Number 684)

Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.05.i (Index Number 684)

ML18054A306
Person / Time
Site:	Vogtle
Issue date:	02/22/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.7.01.05.i, ND-18-0225
Download: ML18054A306 (11)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynestxjro, GA 30830

^ Southern Nuclear Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell

' 2 2 2018 myox @southernco.com Docket Nos.: 52-025 52-026 ND-18-0225 10 CFR 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 2.7.01.05.1 [Index Number 684]

Ladles and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifiesthe NRC that as of February 16, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.7.01.05.1

[Index Number 684] 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-18-0225 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.05.1 [Index Number 684]

MJY/KJD/amw

U.S. Nuclear Regulatory Commission ND-18-0225 Page 3 of 4 To:

Southern Nuclear Operating ComDanv/ 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. P. B. Donnelly 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 Oalethoroe 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-18-0225 Page 4 of 4 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. 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. S. W. Kernizan, Georgia Public Sen/Ice Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Batch BIngham

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-18-0225 Enclosure Vogtle Electric Generating Riant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.05.1 [Index Number 684]

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 2 of 7 ITAAC Statement Desion Commitment:

5. The seismic Category I equipment identified in Table 2.7.1-1 can withstand seismic design basis loads without loss of safety function.

Inspections. Tests. Analyses:

i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 2.7.1-1 is located on the Nuclear Island.

ii) Type tests, analyses, or a combination of type tests and analyses of seismic Category I equipment will be performed.

iii) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

Acceptance Criteria:

i) The seismic Category I equipment identified in Table 2.7.1-1 is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

iii) A report exists and concludes that the as-built equipment including anchorage is seismicaily bounded by the tested or analyzed conditions.

ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Nuclear Island Nonradioactive Ventilation System (VBS) equipment identified as seismic Category I in the Combined License (COL) Appendix C, Table 2.7.1-1 (the Table) is designed and constructed in accordance with applicable requirements.

if The seismic Cateoorv I equipment identified in Table 2.7.1-1 is located on the Nuclear Island To assure that seismic Category I equipment can withstand seismic design basis loads without loss of safety function, all the equipment in the Table is designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EG) Walkdown ITAAC Guideline (Reference 1), an inspection is conducted of the VBS to confirm the satisfactory installation of the seismicallyqualified equipment. The inspection includes verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). The EQ As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category I equipment is located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 3 of 7 I!) A report exists and concludes that the seismic Cateoorv I eauioment can withstand seismic design basis loads without loss of safety function.

Seismic Category I equipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves is demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME) Code Section III (Reference 3). Functionality of the subset of active safety-related valves under seismic loads is determined using the guidance of ASME QME-1-2007 (Reference 4).

Safety-related (Class 1E) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1987 (Reference 5). This equipment includes safety-related active valve accessories such as electric actuators, position switches, pilot solenoid valves and electrical connector assemblies. The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment in the Table is identified in Attachment A.

Additional information about the methods used to qualify API 000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 6).

The EQ Reports (Reference 7) identified in Attachment Acontain applicable test reports and associated documentation and conclude that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

iiil A reoort exists and concludes that the as-built eauioment including anchorage is seismicallv bounded bv the tested or analyzed conditions.

An inspection (Reference 1) is conducted to confirm the satisfactory installation of the seismically qualified equipment in the Table. The inspection verifies the equipment make/model/serial number, as-designed equipment mounting orientation, anchorage and clearances, and electrical and otherinterfaces. The documentation of installed configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.

As part of the seismic qualification program, consideration isgiven to the definition of the clearances needed around the equipment mounted in the plant to permit the equipmentto move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This isdone as part of seismic testing by measuring the maximum dynamic relative displacement of thetop and bottom of the equipment. EQ Reports (Reference 7) identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification.

Interface requirements are defined based on the test configuration and otherdesign requirements.

Attachment A identifies the EQRR (Reference 2) completed to verify that the as-built seismic Category Iequipment listed in the Table, including anchorage, is seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 5), and NRG Regulatory Guide 1.100 (Reference 8).

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 4 of 7 Together, these reports (References 2 and 7) provide evidence that the ITAAC Acceptance Criteria requirements are met;

• The seismic Category I equipment identified in Table 2.7.1-1 is located on the Nuclear Island;

• A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function; and

• A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

References 2 and 7 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.7.01.05.1 Completion Packages (References 9 and 10, 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 included now-consolidated ITAAC Indexes 685 and 686, found the following relevant ITAAC finding associated with this ITAAC.

1) NGN 99901412/2012-201 -02 (Closed)

References favaiiabie for NRC inspection)

1. ND-xx-xx-001, "EG Walkdown ITAAC Guideline"

2. EG As-Built Reconciliation Reports (EQRR) as identified in Attachment Afor Units 3 and 4

3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

Code,Section III, "Rules for Construction of Nuclear Power Plant Components," 1998 Edition with 2000 Addenda

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

5. IEEE Standard 344-1987, "IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"

6. Vogtle 3&4 Updated Final SafetyAnalysis Report Appendix 3D, "Methodology forQualifying API 000 Safety-Related Electrical and Mechanical Equipment"

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

8. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 5 of 7

9. 2.7.01.05.l-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.7.01.05.i [Index Number 684]"

10.2.7.01.05.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.7.01.05.1 [Index Number 684]"

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

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 6 of 7 Attachment A System: Nuclear Island Nonradloactive Ventilation System Equipment Seismic Type of EQ Reports As-Built EQRR Tag No.

• Name^ Cat. 1 + Quai. (Reference 7) (Reference 2)

• APP-PV11-VBR-MGR Supply Type Test 006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V186 Yes

& Analysis APP-PV11-VBR- PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Supply Type Test 006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V187 Yes

& Analysis APP-PV11-VBR- PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Return Type Test 006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V188 Yes

& Analysis APP-PV11-VBR- PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Return Type Test 006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V189 Yes

& Analysis APP-PV11-VBR- PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Exhaust Type Test 006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V190 Yes

& Analysis APP-PV11-VBR- PGDXXX-Rev 0 Valve 005 APP-PV11-VBR-MGR Exhaust Type Test 006/ 2.7.01.05.i-U3-EQRR-Air Isolation VBS-PL-V191 Yes

& Analysis APP-PV11-VBR- PGDXXX-Rev 0 Valve 005 APP-PV02-VBR-PWS MGR Type Test 010/ 2.7.01.05.i-U3-EQRR-PWS-PL-V418 Yes Isolation Valve & Analysis APP-PV02-VBR- PGDXXX-Rev 0 009 APP-PV02-VBR-PWS MGR Type Test 010/ 2.7.01.05.i-U3-EQRR-PWS-PL-V420 Yes Isolation Valve & Analysis APP-PV02-VBR- PGDXXX-Rev 0 009 APP-PV18-VBR-PWS MGR Type Test 002/ 2.7.01.05.i-U3-EQRR-PWS-PL-V498 Yes Vacuum Relief & Analysis APP-PV18-VBR- PGDXXX-Rev 0 001 APP-PV11-VBR-MGR SDS Type Test 006/ 2.7.01.05.i-U3-EQRR-(Vent) Isolation SDS-PL-V001 Yes

& Analysis APP-PV11-VBR- PGDXXX-Rev 0 Valve 005

U.S. Nuclear Regulatory Commission ND-18-0225 Enclosure Page 7 of 7 Equipment Seismic Type of EQ Reports As-Built EQRR Tag No.

• Name^ Cat. i + Qual. (Reference 7) (Reference 2)

• APP-PV11-VBR-MCR SDS Type Test 006/ 2.7.01.05.i-U3-EQRR-(Vent) Isolation SDS-PL-V002 Yes

& Analysis APP-PV11-VBR- PCDXXX-Rev 0 Valve 005 APP-PV03-VBR-MCR WWS WWS-PL- 006/ 2.7.01.05.i-U3-EQRR-Yes Analysis PCDXXX-Rev 0 Isolation Valve V506 APP-PV03-VBR-005

+ Excerpt from COL Appendix C Table 2.7.1-1

• Tfie Unit 4 As-Built EQRR are numbered "2.7.01.05.i-U4-EQRR-PCDXXX-Rev 0"