ND-22-0739, ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.i (Index Number 415)

ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.i (Index Number 415)

ML23031A298
Person / Time
Site:	Vogtle
Issue date:	01/31/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0739
Download: ML23031A298 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel January 31, 2023 Docket No.: 52-026 ND-22-0739 10 CFR 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 4 ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.i [Index Number 415]

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 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.08.02.i [Index Number 415], for verifying the Service Water System (SWS) pump flow through its Component Cooling Water System (CCS) heat exchanger and that controls and displays are available in the Main Control Room (MCR) as listed in Table 2.3.8-1. The closure process for this ITAAC is based on the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52, which is 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, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 ITAAC Completion of ITAAC 2.3.08.02.i [Index Number 415]

JMC/CWM/sfr

U.S. Nuclear Regulatory Commission ND-22-0739 Page 2 of 2 cc: Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

U.S. Nuclear Regulatory Commission ND-22-0739 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-22-0739 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.08.02.i [Index Number 415]

U.S. Nuclear Regulatory Commission ND-22-0739 Enclosure Page 2 of 5 ITAAC Statement Design Commitment

2. The SWS provides the nonsafety-related function of transferring heat from the component cooling water system to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling.

3. Controls exist in the MCR to cause the components identified in Table 2.3.8-1 to perform the listed function.

4. Displays of the parameters identified in Table 2.3.8-1 can be retrieved in the MCR.

Inspections/Tests/Analyses i) Testing will be performed to confirm that the SWS can provide cooling water to the CCS heat exchangers.

Testing will be performed on the components in Table 2.3.8-1 using controls in the MCR.

Inspection will be performed for retrievability of parameters in the MCR.

Acceptance Criteria i) Each SWS pump can provide at least 10,000 gpm of cooling water through its CCS heat exchanger.

Controls in the MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions.

The displays identified in Table 2.3.8-1 can be retrieved in the MCR.

ITAAC Determination Basis This ITAAC requires testing and inspections be performed to demonstrate that the Service Water System (SWS) provides the nonsafety-related function of transferring heat from the Component Cooling Water System (CCS) to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling, ensure controls in the Main Control Room (MCR) operate to cause the components listed in Table 2.3.8-1 to perform the listed function, and ensure the displays of parameters identified in Table 2.3.8-1 can be retrieved in the MCR.

i) Each SWS pump can provide at least 10,000 gpm (gallons per minute) of cooling water through its CCS heat exchanger.

Multiple ITAAC were performed to demonstrate the SWS provided the nonsafety-related function of transferring heat from the component cooling water system to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling. Testing was performed in accordance with Unit 4 preoperational test procedure 4-SWS-ITPP-501 (Reference 1), utilizing

U.S. Nuclear Regulatory Commission ND-22-0739 Enclosure Page 3 of 5 Work Order 1206770 (Reference 2), to verify that each SWS pump provided at least 10,000 gpm of cooling water through its CCS heat exchanger.

Initial conditions were established with the SWS train B pump in service with a temporary flow instrument installed upstream of the CCS B heat exchanger. The temporary flow instrument was monitored and the flow value was determined in accordance with B-GEN-ITPA-004 (Reference

4) and verified to be greater than 10,000 gpm. This testing was repeated with the SWS pump A and the A CCS heat exchanger.

The test results demonstrated that the Unit 4 B SWS pump provided 11,795 gpm through Unit 4 B CCS heat exchanger and the Unit 4 A SWS pump provided 11,969 gpm through Unit 4 A CCS heat exchanger and was documented in Reference 2.

These test results confirmed that each SWS pump provided at least 10,000 gpm of cooling water through its CCS heat exchanger.

Controls in the MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions.

Testing was performed in accordance with appropriate operating procedures to verify that controls exist in the MCR and the controls operate to cause the components listed in COL Appendix C Table 2.3.8-1 (Attachment A) to perform the listed functions.

The components identified in Attachment A performed their listed function by using controls at an operator workstation in the MCR. Control Room Operators started Service Water Pumps A and B (SWS-MP-01A/B) and verified their discharge valves (SWS-PL-V002A/B) opened from the MCR. Service Water Cooling Tower Fans A and B (SWS-MA-01A/B) were started from an operator workstation in the MCR by adjusting their temperature controllers.

These test results confirmed that controls in the MCR operate to cause the components listed in Attachment A to perform the listed functions and was documented in Reference 3.

The displays identified in Table 2.3.8-1 can be retrieved in the MCR.

An inspection was performed as described in Reference 3 to verify that the displays identified in COL Appendix C Table 2.3.8-1 (Attachment B) can be retrieved in the MCR.

An inspection was conducted at an operator workstation in the MCR and verified all the displays identified in Attachment B can be retrieved. This confirmed that the displays identified in Attachment B can be retrieved in the MCR and was documented in Reference 3.

The completed test results (References 2 and 3) confirm that each SWS pump can provide at least 10,000 gpm of cooling water through its CCS heat exchanger, that the controls in the MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions, and that the displays identified in Table 2.3.8-1 can be retrieved in the MCR.

References 2 and 3 are available for NRC inspection as part of the Unit 4 ITAAC Completion Package (Reference 5).

U.S. Nuclear Regulatory Commission ND-22-0739 Enclosure Page 4 of 5 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 review found there were no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.08.02.i (Reference 5) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.08.02.i was performed for VEGP Unit 4 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. 4-SWS-ITPP-501, Ver. 1.0, Service Water System Preoperational Test

2. SV4-SWS-T0W-1206770, Rev. 0, (ITAAC) 4-SWS-ITPP-501 Preoperational Test

3. SV4-SWS-ITR-800415, Rev. 0, Unit 4 Recorded Results of Service Water System Component Test: ITAAC 2.3.08.02.i, Items 3 and 4

4. B-GEN-ITPA-004, Rev. 33.0, Conduct of Test

5. 2.3.08.02.i-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0739 Enclosure Page 5 of 5 Attachment A

• Excerpt from COL Appendix C Table 2.3.8-1 Equipment Name* Tag No.* Control Function*

Service Water Pump A (Motor) SWS-MP-01A Start Service Water Pump B (Motor) SWS-MP-01B Start Service Water Cooling Tower Fan A (Motor) SWS-MA-01A Start Service Water Cooling Tower Fan B (Motor) SWS-MA-01B Start Service Water Pump A Discharge Valve SWS-PL-V002A Open Service Water Pump B Discharge Valve SWS-PL-V002B Open Attachment B

• Excerpt from COL Appendix C Table 2.3.8-1 Equipment Name* Tag No.* Display*

Service Water Pump A (Motor) SWS-MP-01A Yes (Run Status)

Service Water Pump B (Motor) SWS-MP-01B Yes (Run Status)

Service Water Cooling Tower Fan A (Motor) SWS-MA-01A Yes (Run Status)

Service Water Cooling Tower Fan B (Motor) SWS-MA-01B Yes (Run Status)

Service Water Pump 1A Flow Sensor SWS-004A Yes Service Water Pump 1B Flow Sensor SWS-004B Yes Service Water Pump A Discharge Valve SWS-PL-V002A Yes (Valve Position)

Service Water Pump B Discharge Valve SWS-PL-V002B Yes (Valve Position)

Service Water Pump A Discharge SWS-005A Yes Temperature Sensor Service Water Pump B Discharge SWS-005B Yes Temperature Sensor Service Water Cooling Tower Basin Level SWS-009 Yes