ND-23-0478, ITAAC Closure Notification on Completion of ITAAC Item 2.2.03.10 (Index Number 206)

ITAAC Closure Notification on Completion of ITAAC Item 2.2.03.10 (Index Number 206)

ML23167C144
Person / Time
Site:	Vogtle
Issue date:	06/16/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0478
Download: ML23167C144 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel June 16, 2023 Docket No.: 52-026 ND-23-0478 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 Item 2.2.03.10 [Index Number 206]

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 2.2.03.10 [Index Number 206]. This ITAAC confirms that for Passive Core Cooling System (PXS); specified displays can be retrieved in the Main Control Room (MCR), specified controls in the MCR operate remotely operated valves and that valves function as required. 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) request 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 2.2.03.10 [Index Number 206]

JMC/MKO/sfr

U.S. Nuclear Regulatory Commission ND-23-0478 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-23-0478 Enclosure Page 1 of 9 Southern Nuclear Operating Company ND-23-0478 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC Item 2.2.03.10 [Index Number 206]

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 2 of 9 ITAAC Statement Design Commitment

10. Safety-related displays of the parameters identified in Table 2.2.3-1 can be retrieved in the MCR.

11.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.3-1 to perform their active function(s).

11.b) The valves identified in Table 2.2.3-1 as having PMS control perform their active function after receiving a signal from the PMS.

12.b) After loss of motive power, the remotely operated valves identified in Table 2.2.3-1 assume the indicated loss of motive power position.

13. Displays of the parameters identified in Table 2.2.3-3 can be retrieved in the MCR.

Inspections/Tests/Analyses Inspection will be performed for the retrievability of the safety-related displays in the MCR.

ii) Stroke testing will be performed on remotely operated valves other than squib valves identified in Table 2.2.3-1 using the controls in the MCR.

ii) Testing will be performed on the remotely operated valves other than squib valves identified in Table 2.2.3-1 using real or simulated signals into the PMS.

iii) Testing will be performed to demonstrate that remotely operated PXS isolation valves PXS-V014A/B, V015A/B, V108A/B open within the required response times.

Testing of the remotely operated valves will be performed under the conditions of loss of motive power.

Inspection will be performed for retrievability of the displays identified in Table 2.2.3-3 in the MCR.

Acceptance Criteria Safety-related displays identified in Table 2.2.3-1 can be retrieved in the MCR.

ii) Controls in the MCR operate to cause remotely operated valves other than squib valves to perform their active functions.

ii) Remotely operated valves other than squib valves perform the active function identified in the table after a signal is input to the PMS.

iii) These valves open within 20 seconds after receipt of an actuation signal.

After loss of motive power, each remotely operated valve identified in Table 2.2.3-1 assumes the indicated loss of motive power position.

Displays identified in Table 2.2.3-3 can be retrieved in the MCR.

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 3 of 9 ITAAC Determination Basis Multiple ITAAC are performed to verify by inspections and tests that:

Safety-related displays of the parameters identified in the Combined License (COL)

Table 2.2.3-1 (Attachment A) can be retrieved in the Main Control Room (MCR).

Controls exist in the MCR to cause the remotely operated valves identified in COL Table 2.2.3-1 (Attachment B) to perform their active function(s).

The valves identified in Table 2.2.3-1 (Attachment C) as having Protection and Safety Monitoring System (PMS) control perform their active function after receiving a signal from the PMS.

Remotely operated PXS isolation valves PXS-V014A/B, V015A/B, V108A/B open within the required response times. (Attachment D)

After loss of motive power, the remotely operated valves identified in COL Table 2.2.3-1 (Attachment E) assume the indicated loss of motive power position.

Displays of the parameters identified in COL Table 2.2.3-3 (Attachment F) can be retrieved in the MCR.

Safety-related displays identified in Table 2.2.3-1 can be retrieved in the MCR.

Inspections were performed, as documented in Reference 1, which visually confirmed that when each of the displays of the plant parameter identified in Attachment A was summoned using the MCR PMS Visual Display Units (VDUs), the expected display appeared on the PMS VDU.

The completed inspection results in Reference 1 confirms that safety-related displays identified in Table 2.2.3-1 can be retrieved in Unit 4 MCR.

ii) Controls in the MCR operate to cause remotely operated valves other than squib valves to perform their active functions.

Using Plant Control System (PLS) controls in the MCR, stroke testing each valve in Attachment B was performed in accordance with testing listed in Reference 2. Each valve was stroked to its active function and proper valve position indication was verified locally and in the MCR. This testing demonstrated PLS controls in the MCR operate to cause the remotely operated valves identified in COL Appendix C Table 2.2.3-1 to perform their active functions.

The completed test results in Reference 2 confirms that controls in the Unit 4 MCR operated to cause the remotely operated valves identified in Table 2.2.3-1 to perform active functions.

ii) Remotely operated valves other than squib valves perform the active function identified in the table after a signal is input to the PMS.

Testing was performed in accordance with Unit 4 component test packages listed in Reference 3 to confirm that the remotely operated valves other than squib valves performed the active function identified in Attachment C after a signal is input to the PMS.

The component test packages established initial conditions with each valve verified locally and in the MCR to be in the required position. An actuation signal was generated by PMS using the PMS Maintenance and Test Panel (MTP) to generate a signal to cause the valves in Attachment C to transfer to the active function position and each valve was verified locally and in the MCR.

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 4 of 9 The completed test results in Reference 3 confirmed the remotely operated valves other than squib valves perform the active function identified in the table after a signal is input to the PMS for Unit 4.

iii) These valves open within 20 seconds after receipt of an actuation signal.

Testing was performed in accordance with Unit 4 component test packages listed in Reference 3 to confirm that remotely operated PXS isolation valves PXS-V014A/B, V015A/B, V108A/B opened within 20 seconds after receipt of an actuation signal.

The component test packages established initial conditions with each valve verified locally and in the MCR to be in the closed position and a digital trend was established to time the valve actuation. An actuation signal was generated by PMS using the PMS Maintenance and Test Panel (MTP) to generate a signal to cause the valves in Attachment D to transfer open and each valve is verified locally and in the MCR.

The completed test results in Reference 3 confirm that remotely operated PXS isolation valves PXS-V014A/B, V015A/B, V108A/B opened within 20 seconds after receipt of an actuation signal for Unit 4 and the test results are documented in Attachment D.

After loss of motive power, each remotely operated valve identified in Table 2.2.3-1 assumes the indicated loss of motive power position.

Testing was performed in accordance with Unit 4 component test packages listed in Reference 4 to verify that each remotely operated valve identified in Attachment E assumed the indicated loss of motive power position upon a loss of motive power.

Testing was performed on the Motor-Operated Valves (MOVs) listed in Attachment E by ensuring each MOV was in their pretest position of closed. Each MOV was stroked open by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the open position was reached. This loss of power caused by the valve control circuit demonstrated the MOV

- . Actual valve position was verified locally and in the MCR. Each MOV was also stroked Closed by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the Closed position was reached. This when motive power was removed. Actual valve position was verified locally and in the MCR.

Testing on the air operated valves listed in Attachment E was performed by placing the valves in a position opposite their loss of motive power position and opening the power supply to their air supply solenoid. This caused the solenoid to de-energize which closed the air supply to the valve and opened a vent port to vent off the air in the actuator. The valves were verified locally and in the MCR to transfer to their loss of motive power position.

The motive power for the squib valves is a single-use explosive device powered by Direct Current (DC)

Power. By design, this configuration results in the squib valves maintaining their as-is position upon a loss of motive power, as power is required to ignite the explosive device which repositions the valve.

As a result, no loss of motive power testing is required for the squib valves. Functional testing of the squib valve actuation circuits is performed by other ITAAC.

The completed test results in Reference 4 confirms that after loss of motive power, each remotely operated valve identified in Table 2.2.3-1 assumes the indicated loss of motive power position for Unit 4.

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 5 of 9 Displays identified in Table 2.2.3-3 can be retrieved in the MCR.

An inspection was performed as documented in Reference 1 to confirm displays identified in Attachment F can be retrieved in the MCR.

Testing was performed at an operator workstation by navigating to several PXS system screens, locating the items identified in Attachment F, and ensuring the items identified can be retrieved in the MCR.

Reference 1 confirms that the displays identified in Table 2.2.3-3 can be retrieved in the Unit 4 MCR.

References 1 through 4 are available for NRC inspection as part of Unit 4 ITAAC Completion Package (Reference 5).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package (Reference 5) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.10 was performed for VEGP Unit 4 and that the prescribed acceptance criteria are 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-PXS-ITR-800206, Rev. 0, Unit 4 Inspection Results of: ITAAC 2.2.03.10 (Items 10 and 13)

NRC Index Number: 206

2. SV4-PXS-ITR-801206, Rev. 0 Unit 4 Testing Results of: ITAAC 2.2.03.10 (Item 11.a) NRC Index Number: 206

3. SV4-PXS-ITR- Unit 4 Inspection Results of: ITAAC 2.2.03.10 (Item 11.b) NRC

4. SV4-PXS-ITR-803206, Rev. 0 Unit 4 Recorded Results of Remotely Operated PXS Valves Response to Loss of Motive Power: ITAAC 2.2.03.10 Item 12.b)

NRC Index Number: 206

5. 2.2.03.10-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 6 of 9 Attachment A

• Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Safety-Related

• Equipment Name *Tag No. Display CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A Yes (Position)

CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B Yes (Position)

CMT A Discharge Isolation Valve PXS-PL-V014A Yes (Position)

CMT B Discharge Isolation Valve PXS-PL-V014B Yes (Position)

CMT A Discharge Isolation Valve PXS-PL-V015A Yes (Position)

CMT B Discharge Isolation Valve PXS-PL-V015B Yes (Position)

Nitrogen Supply Containment Isolation Valve PXS-PL-V042 Yes (Position)

PRHR HX Inlet Isolation Motor-operated Valve PXS-PL-V101 Yes (Position)

PRHR HX Control Valve PXS-PL-V108A Yes (Position)

PRHR HX Control Valve PXS-PL-V108B Yes (Position)

Containment Recirculation A Isolation PXS-PL-V117A Yes (Position)

Motor-operated Valve Containment Recirculation B Isolation PXS-PL-V117B Yes (Position)

Motor-operated Valve Containment Recirculation A Squib Valve PXS-PL-V118A Yes (Position)

Containment Recirculation B Squib Valve PXS-PL-V118B Yes (Position)

Containment Recirculation A Squib Valve PXS-PL-V120A Yes (Position)

Containment Recirculation B Squib Valve PXS-PL-V120B Yes (Position)

IRWST Injection A Squib Valve PXS-PL-V123A Yes (Position)

IRWST Injection A Squib Valve PXS-PL-V123B Yes (Position)

IRWST Injection A Squib Valve PXS-PL-V125A Yes (Position)

IRWST Injection A Squib Valve PXS-PL-V125B Yes (Position)

IRWST Gutter Isolation Valve PXS-PL-V130A Yes (Position)

IRWST Gutter Isolation Valve PXS-PL-V130B Yes (Position)

CMT A Level Sensor PXS-011A Yes CMT A Level Sensor PXS-011B Yes CMT A Level Sensor PXS-011C Yes CMT A Level Sensor PXS-011D Yes CMT B Level Sensor PXS-012A Yes CMT B Level Sensor PXS-012B Yes CMT B Level Sensor PXS-012C Yes CMT B Level Sensor PXS-012D Yes CMT A Level Sensor PXS-013A Yes CMT A Level Sensor PXS-013B Yes CMT A Level Sensor PXS-013C Yes CMT A Level Sensor PXS-013D Yes CMT B Level Sensor PXS-014A Yes CMT B Level Sensor PXS-014B Yes CMT B Level Sensor PXS-014C Yes CMT B Level Sensor PXS-014D Yes IRWST Wide Range Level Sensor PXS-046 Yes IRWST Wide Range Level Sensor PXS-047 Yes IRWST Wide Range Level Sensor PXS-048 Yes PRHR HX Flow Sensor PXS-049A Yes

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 7 of 9 Attachment A

• Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Safety-Related

• Equipment Name *Tag No. Display PRHR HX Flow Sensor PXS-049B Yes Containment Flood-up Level Sensor PXS-050 Yes Containment Flood-up Level Sensor PXS-051 Yes Containment Flood-up Level Sensor PXS-052 Yes IRWST Lower Narrow Range Level Sensor PXS-066 Yes IRWST Lower Narrow Range Level Sensor PXS-067 Yes IRWST Lower Narrow Range Level Sensor PXS-068 Yes IRWST Lower Narrow Range Level Sensor PXS-069 Yes Attachment B

• Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Remotely Operated

• Equipment Name *Tag No. Valve *Active Function CMT A Discharge Isolation Valve PXS-PL-V014A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V014B YES Transfer Open CMT A Discharge Isolation Valve PXS-PL-V015A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V015B YES Transfer Open Nitrogen Supply Containment Isolation Valve PXS-PL-V042 YES Transfer Closed PRHR HX Control Valve PXS-PL-V108A YES Transfer Open PRHR HX Control Valve PXS-PL-V108B YES Transfer Open IRWST Gutter Isolation Valve PXS-PL-V130A YES Transfer Closed IRWST Gutter Isolation Valve PXS-PL-V130B YES Transfer Closed Attachment C

• Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Equipment Name *Tag No. *Control PMS *Active Function CMT A Discharge Isolation Valve PXS-PL-V014A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V014B YES Transfer Open CMT A Discharge Isolation Valve PXS-PL-V015A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V015B YES Transfer Open Nitrogen Supply Containment Isolation Valve PXS-PL-V042 YES Transfer Closed PRHR HX Control Valve PXS-PL-V108A YES Transfer Open PRHR HX Control Valve PXS-PL-V108B YES Transfer Open IRWST Gutter Isolation Valve PXS-PL-V130A YES Transfer Closed IRWST Gutter Isolation Valve PXS-PL-V130B YES Transfer Closed

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 8 of 9 Attachment D

• Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Remotely *Control Opening Unit *Equipment Name *Tag No. Operated Valve PMS Time 4 CMT A Discharge Isolation Valve PXS-PL-V014A Yes Yes 10.84 4 CMT B Discharge Isolation Valve PXS-PL-V014B Yes Yes 6.84 4 CMT A Discharge Isolation Valve PXS-PL-V015A Yes Yes 10.84 4 CMT B Discharge Isolation Valve PXS-PL-V015B Yes Yes 12.84 4 PRHR HX Control Valve PXS-PL-V108A Yes Yes 12.84 4 PRHR HX Control Valve PXS-PL-V108B Yes Yes 11.84 Attachment E

• Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Remotely *Loss of Operated Motive Power

• Equipment Name *Tag No. Valve Position CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A Yes As Is CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B Yes As Is CMT A Discharge Isolation Valve PXS-PL-V014A Yes Open CMT B Discharge Isolation Valve PXS-PL-V014B Yes Open CMT A Discharge Isolation Valve PXS-PL-V015A Yes Open CMT B Discharge Isolation Valve PXS-PL-V015B Yes Open Accumulator A Discharge Isolation Valve PXS-PL-V027A Yes As Is Accumulator B Discharge Isolation Valve PXS-PL-V027B Yes As Is Nitrogen Supply Containment Isolation Valve PXS-PL-V042 Yes Closed PRHR HX Inlet Isolation Motor-operated Valve PXS-PL-V101 Yes As Is PRHR HX Control Valve PXS-PL-V108A Yes Open PRHR HX Control Valve PXS-PL-V108B Yes Open Containment Recirculation A Isolation PXS-PL-V117A Yes As Is Motor-operated Valve Containment Recirculation B Isolation PXS-PL-V117B Yes As Is Motor-operated Valve Containment Recirculation A Squib Valve PXS-PL-V118A Yes As Is Containment Recirculation B Squib Valve PXS-PL-V118B Yes As Is Containment Recirculation A Squib Valve PXS-PL-V120A Yes As Is Containment Recirculation B Squib Valve PXS-PL-V120B Yes As Is IRWST Injection A Squib Valve PXS-PL-V123A Yes As Is IRWST Injection A Squib Valve PXS-PL-V123B Yes As Is IRWST Injection A Squib Valve PXS-PL-V125A Yes As Is IRWST Injection A Squib Valve PXS-PL-V125B Yes As Is IRWST Gutter Isolation Valve PXS-PL-V130A Yes Closed IRWST Gutter Isolation Valve PXS-PL-V130B Yes Closed

U.S. Nuclear Regulatory Commission ND-23-0478 Enclosure Page 9 of 9 Attachment F

• Excerpt from COL Appendix C Table 2.2.3-3 Table 2.2.3-3

• Equipment *Tag No. *Display CMT A Discharge Isolation Valve (Position) PXS-PL-V014A Yes (Position)

CMT B Discharge Isolation Valve (Position) PXS-PL-V014B Yes (Position)

CMT A Discharge Isolation Valve (Position) PXS-PL-V015A Yes (Position)

CMT B Discharge Isolation Valve (Position) PXS-PL-V015B Yes (Position)

Accumulator A Nitrogen Vent Valve (Position) PXS-PL-V021A Yes (Position)

Accumulator B Nitrogen Vent Valve (Position) PXS-PL-V021B Yes (Position)

Accumulator A Discharge Isolation Valve (Position) PXS-PL-V027A Yes (Position)

Accumulator B Discharge Isolation Valve (Position) PXS-PL-V027B Yes (Position)

PRHR HX Control Valve (Position) PXS-PL-V108A Yes (Position)

PRHR HX Control Valve (Position) PXS-PL-V108B Yes (Position)

Containment Recirculation A Isolation PXS-PL-V117A Yes (Position)

Motor-operated Valve (Position)

Containment Recirculation B Isolation PXS-PL-V117B Yes (Position)

Motor-operated Valve (Position)

Containment Recirculation A Squib Valve (Position) PXS-PL-V118A Yes (Position)

Containment Recirculation B Squib Valve (Position) PXS-PL-V118B Yes (Position)

Containment Recirculation A Squib Valve (Position) PXS-PL-V120A Yes (Position)

Containment Recirculation B Squib Valve (Position) PXS-PL-V120B Yes (Position)

IRWST Line A Isolation Valve (Position) PXS-PL-V121A Yes (Position)

IRWST Line B Isolation Valve (Position) PXS-PL-V121B Yes (Position)

IRWST Injection A Squib Valve (Position) PXS-PL-V123A Yes (Position)

IRWST Injection A Squib Valve (Position) PXS-PL-V123B Yes (Position)

IRWST Injection A Squib Valve (Position) PXS-PL-V125A Yes (Position)

IRWST Injection A Squib Valve (Position) PXS-PL-V125B Yes (Position)

IRWST Gutter Isolation Valve (Position) PXS-PL-V130A Yes (Position)

IRWST Gutter Isolation Valve (Position) PXS-PL-V130B Yes (Position)

Accumulator A Level Sensor PXS-JE-L021 Yes Accumulator B Level Sensor PXS-JE-L022 Yes Accumulator A Level Sensor PXS-JE-L023 Yes Accumulator B Level Sensor PXS-JE-L024 Yes PRHR HX Inlet Temperature Sensor PXS-JE-L064 Yes IRWST Surface Temperature Sensor PXS-JE-L041 Yes IRWST Surface Temperature Sensor PXS-JE-L042 Yes IRWST Bottom Temperature Sensor PXS-JE-L043 Yes IRWST Bottom Temperature Sensor PXS-JE-L044 Yes