ND-18-0087, Vogtie, Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.10.05a.i (Index Number 437)

Vogtie, Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.10.05a.i (Index Number 437)

ML18032A471
Person / Time
Site:	Vogtle
Issue date:	01/26/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0087
Download: ML18032A471 (10)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 hk. Southern Nuclear Vogtie 3 & 4 706-848-6459 410-474-8587 tei cell JAN 2 ^ 2018 myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0087 10CFR 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 2.3.10.05a.i findex Number 4371 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 23, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.10.05a.i

[Index Number437] 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.

AjQ'IAAOJ-Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4

U.S. Nuclear Regulatory Commission ND-18-0087 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.10.OSa.i [Index Number 437]

MJY/PGL/amw

U.S. Nuclear Regulatory Commission ND-18-0087 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. R. L. Beiike 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. Emstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Oalethorpe Power Corporation Mr. K. T. Haynes Mr. R. B. Brinkman Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0087 Page 4 of 4 Daiton Utilities Mr. T. Bundros Westlnqhouse 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. 8. DITommaso 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., GDS Associates, Inc.

Mr. 8. Roetger, Georgia Pubiic 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-18-0087 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-18-0087 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.10.OSa.i [Index Number 437]

U.S. Nuclear Regulatory Commission ND-18-0087 Enclosure Page 2 of 6 ITAAC Statement Desion Commitment:

5.a) The seismic Category I equipment identified in Table 2.3.10-1 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 2.3.10-1 is located on the Nuclear Island.

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

ill) 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 Iequipment identified in Table 2.3.10-1 is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category Iequipment 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 seismically bounded by the tested or analyzed conditions.

ITAAC Completion Description This ITAAC requires that inspections, tests, and analyses be performed and documentedto ensure the Liquid Radwaste System (WLS) components identified as seismic Category I in the Combined License (COL) Appendix C, Table 2.3.10-1 (the Table) are designed and constructed in accordance with applicable requirements.

ii The seismic Cateoorv I equipment identified in Table 2.3.10-1 is located on the Nuclear Island.

To assure that seismic Category I components can withstandseismic design basis loads without loss of safety function, all the components in the Table are 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 WLS to confirm the satisfactory installation of the seismically qualified components. The inspection includes verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). The EG As-Built Reconciliation Reports (EQRR) (Reference 2) identified in Attachment A document the results of the inspection and conclude that the seismic Category I components are located on the Nuclear Island.

U.S. Nuclear Regulatory Commission ND-18-0087 Enclosure Page 3 of 6

11) A report exists and concludes that the seismic Cateoorv I eouioment can withstand seismic desion basis loads without loss of safety function.

Seismic Category I components in the Table require type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category Ivalves, as well as other passive seismic Category I mechanical equipment, 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).

The specific qualification method (i.e., type testing, analysis, or combination) used for each component inthe Table is identified in Attachment A. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 5). The EQ Reports (Reference 6) identified in Attachment A contain 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.

iii) A report exists and concludes that the as-built eouioment including anchorage is seismicallv bounded bv the tested or analvzed conditions.

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

As part of the seismic qualification program, consideration is given to the definition of the clearances needed around the equipment mounted in the plant to permit the equipment to move during a postulated seismic event without causing impact between adjacent pieces of safety-related equipment. This is done as part of seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment. EQ Reports (Reference 6) 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 other design requirements.

Attachment A identifies the EQRR (Reference 2) completed to verify that the as-built seismic Category I equipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions and NRG Regulatory Guide 1.100 (Reference 7).

Together, these reports (References 2 and 6) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 2.3.10-1 is located on the Nuclear Island:

U.S. Nuclear Regulatory Commission ND-18-0087 Enclosure Page 4 of 6

• 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 6 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.10.OSa.i Completion Packages (References 8 and 9, 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 438 and 439, found no relevant ITAAC findings associated with this iTAAC.

References (available for NRC inspection)

1. ND-xx-xx-001, "EQ Waikdown iTAAC Guideline"

2. EQ As-Built Reconciliation Reports (EQRR) as identified in Attachment A for 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. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, "Methodology for Qualifying API 000 Safety-Related Electrical and Mechanical Equipment"

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

7. Regulatory Guide 1.100, Rev. 2, "SeismicQualification of Electric and Mechanical Equipment for Nuclear Power Plants"

8. 2.3.10.05a.i-U3-CP-Rev X, "Completion Package for Unit 3 ITAAC 2.3.10.OSa.i [Index Number 437]"

9. 2.3.10.05a.i-U4-CP-Rev X, "Completion Package for Unit 4 ITAAC 2.3.10.OSa.i [Index Number 437]"

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

U.S. Nuclear Regulatory Commission ND-18-0087 Enclosure Page 5 of 6 Attachment A System: Liquid Radwaste System (WLS)

As-Built EQ EQ Reports Reconciliation Equipment Name ^ Tag No. ^ Seismic Cat. 1 ^ Type of Qual. (Reference 6) Report (EORR)

(Reference 2)*

2.3.10.05a.i-U3-WLS Containment Sump Level WLS-034 APP-JE27-VBR-XXX /

Yes Type Testing & Analysis APP-JE27-VBR-YYY EQRR-PCDXXX-Sensor Rev 0 2.3.10.05a.i-U3-WLS Containment Sump Level APP-JE27-VBR-XXX /

WLS-035 Yes Type Testing & Analysis APP-JE27-VBR-YYY EQRR-PCDXXX-Sensor RevO 2.3.10.05a.i-U3-WLS Containment Sump Level APP-JE27-VBR-XXX /

WLS-036 Yes Type Testing & Analysis APP-JE27-VBR-YYY EQRR-PCDXXX-Sensor Rev 0 WLS Drain from Passive Core 2.3.10.05a.i-U3-Cooling System (PXS) WLS-PL- APP-PV03-VBR-014/

Yes Type Testing & Analysis APP-PV03-VBR-013 EQRR-PCDXXX-Compartment A (Room 11206) V071B Rev 0 Check Valve WLS Drain from PXS 2.3.10.05a.i-U3-WLS-PL- APP-PV03-VBR-014 /

Compartment A (Room 11206) Yes Type Testing & Analysis APP-PV03-VBR-013 EQRR-PCDXXX-V072B Check Valve Rev 0 WLS Drain from PXS 2.3.10.05a.i-U3-WLS-PL- APP-PV03-VBR-014 /

Compartment B (Room 11207) Yes Type Testing & Analysis APP-PV03-VBR-013 EQRR-PCDXXX-V071C Check Valve Rev 0 WLS Drain from PXS 2.3.10.05a.i-U3-WLS-PL- APP-PV03-VBR-014 /

Compartment B (Room 11207) Yes Type Testing & Analysis APP-PV03-VBR-013 EQRR-PCDXXX-V072C Rev 0 Check Valve WLS Drain from Chemical and 2.3.10.05a.i-U3-Volume Control System (CVS) WLS-PL- APP-PV03-VBR-014 /

Yes Type Testing & Analysis APP-PV03-VBR-013 EQRR-PCDXXX-Compartment (Room 11209) V071A RevO Check Valve

U.S. Nuclear Regulatory Commission ND-18-0087 Enclosure Page 6 of 6 As-Buiit EQ EQ Reports Reconciliation Equipment Name ^ Tag No. + Seismic Cat. i ^ Type of Quai.

(Reference 6) Report (EQRR)

(Reference 2)*

WLS Drain from CVS 2.3.10.05a.i-U3-WLS-PL- APP-PV03-VBR-014 /

Compartment (Room 11209) Yes Type Testing & Analysis EQRR-PCDXXX-V072A APP-PV03-VBR-013 Check Valve Rev 0 Notes:

• Excerpt from COL Appendix C Table 2.3.10-1

• The Unit 4 As-Built EQRR are numbered "2.3.10.05a.i-U4-EQRR-PCDXXX-Rev 0"