ND-23-0307, ITAAC Closure Notification on Completion of ITAAC Item 2.2.01.09 (Index Number 110)

ITAAC Closure Notification on Completion of ITAAC Item 2.2.01.09 (Index Number 110)

ML23111A244
Person / Time
Site:	Vogtle
Issue date:	04/21/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ITAAC 2.2.01.09, ND-23-0307
Download: ML23111A244 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel April 21, 2023 Docket No.:

52-026 ND-23-0307 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 2.2.01.09 [Index Number 110]

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 2.2.01.09 [Index Number 110]. This ITAAC confirms that safety related displays and controls exist in the main control room, including controls from PMS, for valves associated with the Containment System (CNS) identified as having active safety functions. 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 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 Completion of ITAAC Item 2.2.01.09 [Index Number 110]

JMC/PCM/sfr

U.S. Nuclear Regulatory Commission ND-23-0307 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-23-0307 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-23-0307 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC Item 2.2.01.09 [Index Number 110]

U.S. Nuclear Regulatory Commission ND-23-0307 Enclosure Page 2 of 5 ITAAC Statement Design Commitment

9. Safety-related displays identified in Table 2.2.1-1 can be retrieved in the MCR.

10.a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions.

10.b) The valves identified in Table 2.2.1-1 as having PMS control perform an active safety function after receiving a signal from the PMS.

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

Stroke testing will be performed on remotely operated valves identified in Table 2.2.1-1 using the controls in the MCR.

Testing will be performed on remotely operated valves listed in Table 2.2.1-1 using real or simulated signals into the PMS.

Acceptance Criteria Safety-related displays identified in Table 2.2.1-1 can be retrieved in the MCR.

Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.1-1 to perform active safety functions.

The remotely operated valves identified in Table 2.2.1-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS.

ITAAC Determination Basis Inspections and testing were performed to confirm the valves listed in Combined License (COL)

Appendix C Table 2.2.1-1 (Attachment A) have safety related displays retrievable in the Main Control Room (MCR), controls exist in the MCR to cause those remotely operated valves identified in Table 2.2.1-1 to perform active functions, and the valves identified as having Protection and Safety Monitoring System (PMS) control perform the active function identified in the table after receiving a signal from the PMS.

Safety-related displays identified in Table 2.2.1-1 can be retrieved in the MCR.

Inspections were performed as described in the Unit 4 ITAAC Technical Report (Reference 1) which visually confirmed that when each of the displays of the plant parameter identified in Attachment A is summoned using the MCR PMS Visual Display Units (VDUs), the expected valve position appears on the PMS VDU.

U.S. Nuclear Regulatory Commission ND-23-0307 Enclosure Page 3 of 5 Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.1-1 to perform active safety functions.

Using Plant Control System (PLS) controls in the MCR, stroke testing each valve in Attachment A was performed in accordance with test package work orders for Unit 4 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 demonstrates PLS controls in the MCR operate to cause the remotely operated valves identified in COL Appendix C Table 2.2.1-1 to perform their active safety functions.

The remotely operated valves identified in Table 2.2.1-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS.

Testing is performed in accordance with Unit 4 test package work orders listed in Reference 3 to confirm that the remotely operated valves identified in Attachment A as having PMS control perform the active safety function identified in the table after receiving a signal from the PMS.

The test package work orders establish initial conditions for each valve, verified locally and in the MCR to be in the open position. An actuation signal is generated by PMS using the PMS Maintenance and Test Panel (MTP) to generate a signal to close the valves in Attachment A.

Each valve is verified locally and in the MCR to be closed. Additionally, for VFS-PL-V800A/B initial conditions were established with each valve verified locally and in the MCR to be in the closed position. An actuation signal is generated by PMS using the PMS Maintenance and Test Panel (MTP) to generate a signal to open the valves. VFS-PL-V800A/B are verified locally and in the MCR to be open. This verifies that the remotely operated valves identified in Table 2.2.2-1 as having PMS control perform the active safety function identified in the table after receiving a signal from the PMS.

Together, these test results (References 1 through 3) provide evidence that the ITAAC Acceptance Criteria requirements are met:

Safety-related displays identified in Table 2.2.1-1 can be retrieved in the MCR.

Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.1-1 to perform active safety functions.

The remotely operated valves identified in Table 2.2.1-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS.

References 1 through 3 are available for NRC inspection as part of the Unit 4 ITAAC 2.2.01.09 Completion Package (Reference 4).

ITAAC Finding Review 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 review found that there are no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.01.09 Unit 4 (Reference 4) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.01.09 was performed for VEGP Unit 4 and that the prescribed acceptance criteria were met.

U.S. Nuclear Regulatory Commission ND-23-0307 Enclosure Page 4 of 5 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-CNS-ITR-800110, Rev 0 Unit 4 Inspection Results of: ITAAC 2.2.01.09 (Item 9), NRC Index Number:110

2. SV4-CNS-ITR-801110, Rev 0 Unit 4 Testing Results of ITAAC 2.2.01.09 (Item 10.a), NRC Index Number:110

3. SV4-CNS-ITR-802110, Rev 0 Unit 4 Testing Results of Containment Isolation Valves ITAAC 2.2.01.09 (Item 10.b), NRC Index Number 110

4. 2.2.01.09-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0307 Enclosure Page 5 of 5 Attachment A Containment System (CNS) Remotely Operated Valves Display, Control, and Active Function Equipment Name*

Tag No.*

Remotely Operated Valve*

Safety-Related Display*

Control PMS/DAS*

Active Function*

Instrument Air Supply Outside Containment Isolation Valve CAS-PL-V014 YES Yes (Valve Position)

Yes/No Transfer Closed Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve (MOV) Inlet Line Outside Reactor Containment (ORC)

CCS-PL-V200 YES Yes (Valve Position)

Yes/No Transfer Closed CCS containment isolation MOV-outlet line IRC CCS-PL-V207 YES Yes (Valve Position)

Yes/No Transfer Closed CCS containment isolation MOV-outlet line ORC CCS-PL-V208 YES Yes (Valve Position)

Yes/No Transfer Closed SFS Discharge Line containment isolation MOV - ORC SFS-PL-V038 YES Yes (Valve Position)

Yes/No Transfer Closed SFS Suction Line containment isolation MOV - IRC SFS-PL-V034 YES Yes (Valve Position)

Yes/No Transfer Closed SFS Suction Line containment isolation MOV - ORC SFS-PL-V035 YES Yes (Valve Position)

Yes/No Transfer Closed Containment Purge Inlet containment isolation valve -ORC VFS-PL-V003 YES Yes (Valve Position)

Yes/Yes Transfer Closed Containment Purge Inlet containment isolation valve - IRC VFS-PL-V004 YES Yes (Valve Position)

Yes/Yes Transfer Closed Containment Purge Discharge containment isolation valve - IRC VFS-PL-V009 YES Yes (Valve Position)

Yes/Yes Transfer Closed Containment Purge Discharge containment isolation valve -ORC VFS-PL-V010 YES Yes (Valve Position)

Yes/Yes Transfer Closed Vacuum Relief containment isolation A MOV - ORC VFS-PL-V800A YES Yes (Valve Position)

Yes/No Transfer Closed/

Transfer Open Vacuum Relief containment isolation B MOV - ORC VFS-PL-V800B YES Yes (Valve Position)

Yes/No Transfer Closed/

Transfer Open Fan Cooler Return containment isolation valve - IRC VWS-PL-V082 YES Yes (Valve Position)

Yes/No Transfer Closed Fan Cooler Return containment isolation valve - ORC VWS-PL-V086 YES Yes (Valve Position)

Yes/No Transfer Closed Fan Cooler Supply containment isolation valve - ORC VWS-PL-V058 YES Yes (Valve Position)

Yes/No Transfer Closed Reactor Coolant Drain Tank (RCDT)

Gas Outlet containment isolation valve - IRC WLS-PL-V067 YES Yes (Valve Position)

Yes/No Transfer Closed RCDT Gas Outlet containment isolation valve - ORC WLS-PL-V068 YES Yes (Valve Position)

Yes/No Transfer Closed Sump Discharge containment isolation valve - IRC WLS-PL-V055 YES Yes (Valve Position)

Yes/Yes Transfer Closed Sump Discharge containment isolation valve - ORC WLS-PL-V057 YES Yes (Valve Position)

Yes/Yes Transfer Closed

• Excerpt from COL Appendix C Table 2.2.1-1