ND-23-0394, ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703)

ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703)

ML23193B038
Person / Time
Site:	Vogtle
Issue date:	07/13/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0394
Download: ML23193B038 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel July 12, 2023 Docket No.:

52-026 ND-23-0394 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 2.7.02.03a [Index Number 703]

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 2.7.02.03a [Index Number 703] which verifies component flow rates, Main Control Room (MCR) controls, and MCR indications for the Central Chilled Water System (VWS). 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 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, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.7.02.03a [Index Number 703]

JMC/PAW/sfr

U.S. Nuclear Regulatory Commission ND-23-0394 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-23-0394 Enclosure Page 1 of 7 Southern Nuclear Operating Company ND-23-0394 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.7.02.03a [Index Number 703]

U.S. Nuclear Regulatory Commission ND-23-0394 Enclosure Page 2 of 7 ITAAC Statement Design Commitment 3.a) The VWS provides chilled water to the supply air handling units serving the MCR, the Class 1E electrical rooms, and the unit coolers serving the RNS and CVS pump rooms.

4. Controls exist in the MCR to cause the components identified in Table 2.7.2-1 to perform the listed function.

5. Displays of the parameters identified in Table 2.7.2-1 can be retrieved in the MCR.

Inspections/Tests/Analyses Testing will be performed by measuring the flow rates to the chilled water cooling coils.

Testing will be performed on the components in Table 2.7.2-1 using controls in the MCR.

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

Acceptance Criteria The water flow to each cooling coil equals or exceeds the following:

Coil Flow (gpm)

VBS MY C01A/B 96 VBS MY C02A/C 97 VBS MY C02B/D 52 VAS MY C07A/B 12.3 VAS MY C12A/B 8.2 VAS MY C06A/B 8.2 Controls in the MCR operate to cause the components listed in Table 2.7.2-1 to perform the listed functions.

The displays identified in Table 2.7.2-1 can be retrieved in the MCR.

ITAAC Determination Basis This ITAAC required testing and inspections to be performed to verify that the Central Chilled Water System (VWS) provides the required chilled water flows to the air handling units for the Main Control Room (MCR), the Class 1E electrical rooms, and the Normal Residual Heat Removal System (RNS) pump room coolers and Chemical and Volume Control System (CVS) pump room coolers (Attachment A). Testing also verifies controls in the MCR operated to cause components listed in COL Appendix C Table 2.7.2-1 (Attachment B) to perform their listed function and an inspection was performed to verify the displays identified in COL Appendix C Table 2.7.2-1 can be retrieved in the MCR (Attachment C).

U.S. Nuclear Regulatory Commission ND-23-0394 Enclosure Page 3 of 7 The water flow to each cooling coil equals or exceeds the following:

Coil Flow (gpm)

VBS MY C01A/B 96 VBS MY C02A/C 97 VBS MY C02B/D 52 VAS MY C07A/B 12.3 VAS MY C12A/B 8.2 VAS MY C06A/B 8.2 Testing was performed in accordance with the work order and preoperational test procedures found in Reference 1 that verified the cooling water flow to each cooling coil equals or exceeded the required flow rates.

Initial conditions were established with Low Capacity Chiller MS-02 in service and temporary flow instruments were installed on the outlet line from each of the coolers tested. The flow control valves were manually opened to ensure full flow through the affected 6 coolers. When the chilled water flow stabilized, 10 flow readings were taken at 3 minute intervals. The flow value for each cooler was verified to be above the required values, and the system was restored to normal. This testing was then repeated with the Low Capacity Chiller MS-03 and the remaining 6 cooler units. This testing shows that the flows obtained (Attachment A) were greater than or equal to the ITAAC acceptance criteria required flows.

Controls in the MCR operate to cause the components listed in Table 2.7.2-1 to perform the listed functions.

Testing was performed in accordance with component test work order found in Reference 1 and verified that controls exist in the MCR and the controls operated to cause the components listed in Table 2.7.2-1 (Attachment B) to perform the listed functions.

The component test began with the components in Attachment B in the closed position or shutdown condition. The valves were stroked to the open position using controls in the MCR, were locally verified to be in the correct position, and documented in the test. The ventilation components were started using controls in the MCR, were locally verified to have started and documented in the test. The test results confirm that controls in Unit 4 MCR operate to cause the components listed in Table 2.7.2-1 to perform the listed functions.

The displays identified in Table 2.7.2-1 can be retrieved in the MCR.

The inspection was performed in accordance with component test work order listed in Reference 1 and verified that the displays identified in Table 2.7.2-1 (Attachment C) can be retrieved in the MCR.

Inspection occurred at an operator work station in the Unit 4 MCR and verified all of the displays identified in Attachment C could be retrieved. This confirms that the displays identified in Table 2.7.2-1 can be retrieved in the Unit 4 MCR.

The completed test results (Reference 1) confirm that the low capacity chillers provide the required flow to the listed components, that the controls in the MCR operate to cause the

U.S. Nuclear Regulatory Commission ND-23-0394 Enclosure Page 4 of 7 components listed in Table 2.7.2-1 to perform the listed functions, and that the displays identified in Table 2.7.2-1 can be retrieved in the MCR.

Reference 1 is available for NRC inspection as part of Unit 4 ITAAC 2.7.02.03a Completion Package (Reference 2).

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 are no relevant ITAAC findings associated with this ITAAC.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.7.02.03a 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. SV4-VWS-ITR-800703, Rev 0, Unit 4 Recorded Results of VWS Chilled Water Cooling Coils Flow: ITAAC 2.7.02.03a Items 3.a, 4 and 5. NRC Index Number: 703

2. 2.7.02.03a-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0394 Enclosure Page 5 of 7 Attachment A Chiller Unit Unit Coil Number ITAAC Required Flow (gpm)

Actual Flow (gpm)

MS-02 4

VBS MY C01A 96 108.0 4

VBS MY C02A 97 108.9 4

VBS MY C02D 52 58.6 4

VAS MY C06A 8.2 9.9 4

VAS MY C07A 12.3 14.8 4

VAS MY C12B 8.2 10.2 MS-03 4

VBS MY C01B 96 104.3 4

VBS MY C02B 52 58.5 4

VBS MY C02C 97 108.4 4

VAS MY C06B 8.2 9.7 4

VAS MY C07B 12.3 14.6 4

VAS MY C12A 8.2 9.7

U.S. Nuclear Regulatory Commission ND-23-0394 Enclosure Page 6 of 7 Attachment B

• Excerpt from COL Appendix C Table 2.7.2-1

• Equipment Name

• Tag No.

• Control Function Air-cooled Chiller VWS-MS-02 Start Air-cooled Chiller VWS-MS-03 Start Air-cooled Chiller Pump VWS-MP-02 Start Air-cooled Chiller Pump VWS-MP-03 Start CVS Pump Room Unit Cooler Fan A VAS-MA-07A Start CVS Pump Room Unit Cooler Fan B VAS-MA-07B Start RNS Pump Room Unit Cooler Fan A VAS-MA-08A Start RNS Pump Room Unit Cooler Fan B VAS-MA-08B Start Air-cooled Chiller Water Valve VWS-PL-V210 Open Air-cooled Chiller Water Valve VWS-PL-V253 Open

U.S. Nuclear Regulatory Commission ND-23-0394 Enclosure Page 7 of 7 Attachment C

• Excerpt from COL Appendix C Table 2.7.2-1

• Equipment Name

• Tag No.

• Display Air-cooled Chiller VWS-MS-02 Yes (Run Status)

Air-cooled Chiller VWS-MS-03 Yes (Run Status)

Air-cooled Chiller Pump VWS-MP-02 Yes (Run Status)

Air-cooled Chiller Pump VWS-MP-03 Yes (Run Status)

CVS Pump Room Unit Cooler Fan A VAS-MA-07A Yes (Run Status)

CVS Pump Room Unit Cooler Fan B VAS-MA-07B Yes (Run Status)

RNS Pump Room Unit Cooler Fan A VAS-MA-08A Yes (Run Status)

RNS Pump Room Unit Cooler Fan B VAS-MA-08B Yes (Run Status)

Air-cooled Chiller Water Valve VWS-PL-V210 Yes (Position Status)

Air-cooled Chiller Water Valve VWS-PL-V253 Yes (Position Status)