ND-21-0093, ITAAC Closure Notification on Completion of ITAAC 2.3.07.05.i (Index Number 396)

ITAAC Closure Notification on Completion of ITAAC 2.3.07.05.i (Index Number 396)

ML21165A084
Person / Time
Site:	Vogtle
Issue date:	06/13/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0093
Download: ML21165A084 (9)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel JUN J 3 2021 Docket Nos.: 52-025 ND-21-0093 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.07.05.i [Index Number 3961 Ladies and Gentlemen; in accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC)of the completion of Vogtle Electric Generating Plant(VEGP) Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.07.05.1 [Index Number 396]. This ITAAC confirms that the seismic Category I Spent Fuel Pool Cooling System components identified in the VEGP Unit 3 Combined License (COL) Appendix C, Table 2.3.7-1 can withstand seismic design basis loads without loss of safety function. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC)requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.07.05.1 [Index Number 396]

MJY/RLB/sfr

U.S. Nuclear Regulatory Commission ND-21-0093 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Hi Mr. D. L. McKinney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc; Nuclear Requlatorv Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil M C. P. Patel M . G. J. Khouri M . C. J. Even M . B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. O. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. B. Davis Mr. J. Vasquez Mr. J. Eargle Mr. E. Davidson Mr. T. Fanelli Ms. K. McCurry Mr. J. Parent Mr. B. Griman

U.S. Nuclear Regulatory Commission ND-21-0093 Page 3 of 3 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani Mr. D. 0. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, 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 Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-21-0093 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-21-0093 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.07.05.i [index Number 396]

U.S. Nuclear Regulatory Commission ND-21-0093 Enclosure Page 2 of 6 ITAAC Statement Design Commitment

5. The seismic Category I components identified in Table 2.3.7-1 can withstand seismic design basis loads without loss of safety functions.

Inspections/Tests/Analvses i) Inspection will be performed to verify that the seismic Category I components identified in Table 2.3.7-1 are 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.

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 I components identified in Table 2.3.7-1 are 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 seismically bounded by the tested or analyzed conditions.

ITAAC Determination Basis This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Spent Fuel Pool Cooling System (SFS)components(equipment) identified as seismic Category I in the Combined License(COL) Appendix C, Table 2.3.7-1 are designed and constructed in accordance with applicable requirements.

i) The seismic Cateoorv I components identified in Table 2.3.7-1 are located on the Nuclear Island.

To assure that seismic Category I components can withstand seismic design basis loads without loss of safety function, all the components in the Table 2.3.7-1 were designed to be located on the seismic Category I Nuclear Island. In accordance with the Equipment Qualification (EG)ITAAC As-built Walkdown Guideline (Reference 1) and the EG ITAAC As-built Installation Documentation Guideline (Reference 2), inspections were conducted of the SFS to confirm the satisfactory installation of the seismically qualified components. The inspection included verification of component make/model/serial number and verification of component location (Building, Elevation, Room). The As-Built EG Reconciliation Reports(EGRRs)(Reference 3) identified in Attachment A document the results of the inspections and conclude that the seismic Category I components are located on the Nuclear Island.

ii) A report exists and concludes that the seismic Cateoorv I eauipment can withstand seismic design basis loads without loss of safetv function.

Seismic Category I equipment identified in Table 2.3.7-1 required type tests and/or analyses to demonstrate structural integrity and operability. Structural integrity of the seismic Category I valves

U.S. Nuclear Regulatory Commission ND-21-0093 Enclosure Page 3 of 6 was demonstrated by analysis in accordance with American Society of Mechanical Engineers (ASME)Code Section ill (Reference 4). Functionality of the active safety-related valves under seismic loads was determined using the guidance of ASME QME-1-2007(Reference 5).

The safety-related (Class 1E) electrical equipment identified in Table 2.3.7-1 was seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers(IEEE) Standard 344-1987(Reference 6).

The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment listed in Table 2.3.7-1 is identified in Attachment A. Additional information about the methods used to qualify API000 safety-related equipment is provided in the Updated Final Safety Analysis Report(UFSAR) Appendix 3D (Reference 7). The EQ Reports (Reference 8)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.

Inspections (Reference 1 and Reference 2) were conducted to confirm the satisfactory installation of the seismically qualified equipment identified in Table 2.3.7-1. The inspections verified 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 seismically qualified components includes photographs and/or sketches/drawings of equipment/mounting/interfaces.

As part of the seismic qualification program, consideration was 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. When required, seismic testing measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports (Reference 8) 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/or other design requirements.

Attachment A identifies the EQRR (Reference 3)completed to verify that the as-built seismic Category I equipment listed in Table 2.3.7-1, including anchorage, is seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987(Reference 6), and NRG Regulatory Guide 1.100 (Reference 9).

Together, these reports (References 3 and 8) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 2.3.7-1 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.

U.S. Nuclear Regulatory Commission ND-21-0093 Enclosure Page 4 of 6 References 3 and 8 are available for NRG inspection as part of the Unit 3 ITAAC 2.3.07.05.i Completion Package (Reference 10).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This finding review, which included now-consolidated ITAAC Index Numbers 397 and 398, found one relevant ITAAC finding associated with this ITAAC.

• Notice of Nonconformance 99901412/2012-201-02 (Closed)

The corrective actions for this finding have been completed and the finding closed. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.07.05.1 (Reference 10) and is available for NRC review.

ITAAC Compietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.07.05.1 was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References(available for NRC Inspection^

1. ND-RA-001-014, EQ IT/\AC As-built Walkdown Guideline, Version 3.1

2. ND-RA-001-016, EQ IT/\AC As-built Installation Documentation Guideline, Version 1.0

3. As-Built Equipment Qualification Reconciliation Reports(EQRRs)as identified in Attachment A

4. 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

5. ASME QME-1-2007, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants, June 2007

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

7. Vogtle 3&4 Updated Final Safety Analysis Fjteport Appendix 3D, Methodology for Qualifying APIOOO Safety-Related Electrical and Mechanical Equipment, Revision 9.1

8. Equipment Qualification (EQ) Reports as Identified in Attachment A

9. Regulatory Guide 1.100, Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants, Revision 2 10.2.3.07.05.i -U3-CP-RevO, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-21-0093 Enclosure Page 5 of 6 Attachment A System: Spent Fuel Pool Cooling System (SFS)

Seismic EQ Reports As-Built EQRR Component Name ^ Tag No. + Cat. 1 Type of Qua!.

(Reference 8) (Reference 3)

Spent Fuel Pool Level Sensor**'^'^* Type Testing SV3-JE52-VBR-002 / 2.3.07.05.i-U3-EQRR-SFS-019A Yes

& Analysis SV3-JE52-VBR-001 PCD005 Spent Fuel Pool Level Sensor*'^'^'^^ Type Testing SV3-JE52-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-019B Yes

& Analysis SV3-JE52-VBR-001 PCD005 Spent Fuel Pool Level Sensor**'^'^* Type Testing SV3-JE52-VBR-002 / 2.3.07.05.i-U3-EQRR-SFS-019C Yes

& Analysis SV3-JE52-VBR-001 PCD005 Refueling Cavity Drain to SGS Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V031 Yes Compartment Isoiation Valve & Analysis SV3-PV11-VBR-001 PCD001 Refueling Cavity to SFS Pump Suction Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V032 Yes Isolation Valve & Analysis SV3-PV11-VBR-001 PCD001 Refueling Cavity Drain to Type Testing SV3-PV10-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V033 Yes Containment Sump Isolation Valve & Analysis SV3-PV10-VBR-001 PCD004 IRWST to SFS Pump Suction Line Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V039 Yes Isolation Valve & Analysis SV3-PV11-VBR-001 PCD001 Fuel Transfer Canal to SFS Pump Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V040 Yes Suction Iso. Valve & Analysis SV3-PV11-VBR-001 PCD001 Cask Loading Pit to SFS Pump Suction Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V041 Yes Isolation Valve & Analysis SV3-PV11-VBR-001 PCD001 Cask Loading Pit to SFS Pump Suction Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V042 Yes Isolation Valve"^" & Analysis SV3-PV11-VBR-001 PCD001 SFS Pump Discharge Line to Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V045 Yes Cask Loading Pit Isolation Valve'^'^ & Analysis SV3-PV11-VBR-001 PCD001 Cask Loading Pit to WLS Isolation Type Testing SV3-PV10-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V049 Yes Valve"^"^ & Analysis SV3-PV10-VBR-001 PCD004 Spent Fuel Pool to Cask Washdown Pit Type Testing SV3-PV10-VBR-008/ 2.3.07.05.i-U3-EQRR-SFS-PL-V066 Yes Isolation Valve'^*'^ & Analysis SV3-PV10-VBR-007 PCD003 Cask Washdown Pit Drain Isolation Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V068 Yes Valve'^*'^ & Analysis SV3-PV11-VBR-001 PCD001 Refueling Cavity Drain Line Check SV3-PV03-VBR-014/ 2.3.07.05.i-U3-EQRR-SFS-PL-V071 Yes Analysis Valve'^'^'^'" SV3-PV03-VBR-013 PCD002

U.S. Nuclear Regulatory Commission ND-21-0093 Enclosure Page 6 of 6 Seismic EQ Reports As-Buiit EQRR Component Name ^ Tag No.* Cat. 1 +

Type of Quai.

(Reference 8) (Reference 3)

Refueling Cavity Drain Line Check SV3-PV03-VBR-014/ 2.3.07.05.i-U3-EQRR-SFS-PL-V072 Yes Analysis Valve'^^^^ SV3-PV03-VBR-013 PCD002 SFS Containment Floodup Isolation Type Testing SV3-PV11-VBR-002/ 2.3.07.05.i-U3-EQRR-SFS-PL-V075 Yes Valve & Analysis SV3-PV11-VBR-001 PCD001 Notes:

Excerpt from COL Appendix C Table 2.3.7-1 Active Function to Transfer Closed per COL Appendix C Table 2.3.7-1 Active Function to Transfer Open per COL Appendix C Table 2.3.7-1 Active Function to Transfer Open - Transfer Closed per COL Appendix C Table 2.3.7-1

^ Class 1E per COL Appendix C Table 2.3.7-1