ND-23-0294, ITAAC Closure Notification on Completion of ITAAC 2.1.02.11a.ii (Index Number 47)

ITAAC Closure Notification on Completion of ITAAC 2.1.02.11a.ii (Index Number 47)

ML23103A299
Person / Time
Site:	Vogtle
Issue date:	04/13/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0294
Download: ML23103A299 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel April 13, 2023 Docket No.: 52-026 ND-23-0294 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 2.1.02.11a.ii [Index Number 47]

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 2.1.02.11a.ii [Index Number 47] for verifing the following items: safety-related displays identified in Table 2.1.2-1 can be retrieved in the Main Control Room (MCR), controls exist in the MCR to cause the valves identified in Table 2.1.2-1 to perform active functions, valves having Protection and Safety Monitoring System (PMS) control perform active safety function after receiving a signal from the PMS, certain valves open within the required response time, and upon loss of motive power, required valves assume the indicated loss of motive power position. 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 2.1.02.11a.ii [Index Number 47]

JMC/CWM/sfr

U.S. Nuclear Regulatory Commission ND-23-0294 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-23-0294 Enclosure Page 1 of 11 Southern Nuclear Operating Company ND-23-0294 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.1.02.11a.ii [Index Number 47]

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 2 of 11 ITAAC Statement Design Commitment

10. Safety-related displays identified in Table 2.1.2-1 can be retrieved in the MCR.

11.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.1.2-1 to perform active functions.

11.b) The valves identified in Table 2.1.2-1 as having PMS control perform an active safety function after receiving a signal from the PMS.

12.b) After loss of motive power, the remotely operated valves identified in Table 2.1.2-1 assume the indicated loss of motive power position.

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

ii) Stroke testing will be performed on the other remotely operated valves listed in Table 2.1.2-1 using controls in the MCR.

ii) Testing will be performed on the other remotely operated valves identified in Table 2.1.2-1 using real or simulated signals into the PMS.

iii) Testing will be performed to demonstrate that remotely operated RCS valves RCS-V001A/B, V002A/B, V003A/B, V011A/B, V012A/B, V013A/B open within the required response times.

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

Acceptance Criteria Safety-related displays identified in Table 2.1.2-1 can be retrieved in the MCR.

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

ii) The other remotely operated valves identified in Table 2.1.2-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS.

iii) These valves open within the following times after receipt of an actuation signal:

V001A/B 48 sec V002A/B, V003A/B 120 sec V011A/B 30 sec V012A/B, V013A/B 60 sec Upon loss of motive power, each remotely operated valve identified in Table 2.1.2-1 assumes the indicated loss of motive power position.

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 3 of 11 ITAAC Determination Basis Multiple ITAAC were performed to verify that controls exist in the Main Control Room (MCR) to cause the remotely operated valves identified in Table 2.1.2-1 to perform active functions and the valves identified in Table 2.1.2-1 as having Protection and Safety Monitoring System (PMS) control perform an active safety function after receiving a signal from the PMS. The subject ITAAC requires stroke testing on these remotely operated valves using controls in the MCR, testing on these remotely operated valves using real or simulated signals into the PMS, and response time testing on RCS-V001A/B, V002A/B, V003A/B, V011A/B, V012A/B, and V013A/B.

Additionally, inspections and tests were performed to demonstrate that safety-related displays identified in Table 2.1.2-1 were retrieved in the MCR and that after the loss of motive power, the remotely operated valves identified in Table 2.1.2-1 assumed the indicated loss of motive power position.

Safety-related displays identified in Table 2.1.2-1 can be retrieved in the MCR.

Inspections performed in accordance with the Unit 4 component test package work order listed in SV4-RCS-ITR-802047 (Reference 1) 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 confirmed that safety-related displays identified in Table 2.1.2-1 were retrieved in the Unit 4 MCR.

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

ITAAC 2.1.02.11a.ii item 11a.ii was completed as a combination of:

• Factory Acceptance Test - Functional testing of PMS soft controls to the Component Interface Module (CIM) output

• Site software installation and regression test - Hardware and software integration verification and testing of post system delivery changes

• Component testing - Testing from the CIM to the remotely operated valves The Factory Acceptance Testing (FAT) followed the guidance of NEI 08-01 (Reference 2)

Section 9.4 for the as-built tests to be performed at other than the final installed location. The FAT was performed in accordance with the Software Program Manual for Common Q Systems WCAP-16096 (Reference 3), AP1000 Protection and Safety Monitoring System Test Plan (Reference 4), AP1000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Procedure (Reference 5), and applicable Codes and Standards described in Vogtle 3 and 4 UFSAR Chapter 7.

Testing performed in accordance with FAT procedure SV4-PMS-T1P-009 (Reference 5) verified the logic and functionality from the PMS soft controls through to the Component Interface Module (CIM) outputs for the remotely operated valves identified in Attachment B. The results of the testing were documented in SV4-PMS-T2R-009 (Reference 6).

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 4 of 11 Additional hardware and software installation and associated inspections and testing were performed on-site to verify that the cabinets were intact and functional in accordance with Field Change Notifications (FCNs) AP1000 Vogtle Unit 4 PMS Software Installation - Software Release 9.0.0.1 (Reference 7) and PMS Software Installation - Software Release 9.0.0.4 (Reference 8). These FCNs were implemented by work orders listed in ITAAC Technical Report SV4-PMS-Cabinet Software Loading-001 (Reference 10), and B-GEN-ITPCI-001 (Reference 9).

SV4-PMS Cabinet Software Loading-001 (Reference 10) summarizes the software loading. SV4-PMS Cabinet Diagnostic Testing -001 (Reference 14) documents the performance of diagnostic testing, using individual WOs for each cabinet, and verified the diagnostics were satisfactory for each cabinet. References 10 and 14 include steps that confirm and document successful software load and further confirm the physical properties of the as-built PMS. A regression analysis (i.e., change evaluation) was performed for software changes (Reference 11) to determine if additional testing was needed for the as-built system.

Testing from the CIM to the remotely operated valves identified in Attachment B was performed in accordance with Unit 4 component test packages listed in SV4-RCS-ITR-800047 (Reference 12). Each valve was stroked to its active function from the PMS Maintenance and Test Panel (MTP) which actuated the CIM and proper valve position indication was verified locally and in the MCR.

The completed Unit 4 FAT (References 3 through 6), software installation (Reference 10),

regression test results (Reference 11), cabinet diagnostics (Reference 14), and component test results (Reference 12) confirmed that controls in Unit 4 MCR operated to cause the remotely operated valves identified in Table 2.1.2-1 to perform active functions.

ii) The other remotely operated valves identified in Table 2.1.2-1 as having PMS control perform the active function identified in the table after receiving a signal from PMS.

Testing was performed in accordance with Unit 4 component test packages listed in SV4-RCS-ITR-800047 (Reference 12). These component test packages 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.

Referenced work packages listed in Reference 12 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.

The completed test results (Reference 12) 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 the following times after receipt of an actuation signal:

V001A/B 48 sec V002A/B, V003A/B 120 sec V011A/B 30 sec

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 5 of 11 V012A/B, V013A/B 60 sec Testing was performed in accordance with Unit 4 component test packages listed in SV4-RCS-ITR-800047 (Reference 12). These component test packages confirm that remotely operated RCS valves RCS-V001A/B opened within 48 seconds, V002A/B and V003A/B opened within 120 seconds, V011A/B opened within 30 seconds, and V012A/B and V013A/B opened within 60 seconds after receipt of an actuation signal.

Referenced work packages listed in Reference 12 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 was verified locally and in the MCR.

The completed test results (Reference 12) confirmed that remotely operated RCS valves RCS-V001A/B opened within 48 seconds, V002A/B and V003A/B opened within 120 seconds, V011A/B opened within 30 seconds, and V012A/B and V013A/B opened within 60 seconds after receipt of an actuation signal for Unit 4 and the test results were documented in Attachment D.

Upon loss of motive power, each remotely operated valve identified in Table 2.1.2-1 assumes the indicated loss of motive power position.

Testing was performed in accordance with Unit 4 component test work packages listed in SV4-RCS-ITR-801047 (Reference 13) 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 verifying each MOV locally to be in the Closed position. 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 failed As-Is (Open) when motive power was removed. Actual valve position was verified locally. 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 loss of power caused by the valve control circuit demonstrated that each MOV failed As-Is (Closed) when motive power was removed. Actual valve position was verified locally.

Testing on the solenoid operated valves was performed by placing the valves in a position opposite their loss of motive power position (Open) and opening the power supply to their solenoid. This caused the solenoid to de-energize which closed the valve. The valves were verified 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 was required for the squib valves. Functional testing of the squib valve actuation circuits was performed by other ITAAC.

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 6 of 11 The completed test results (Reference 13) confirmed that after loss of motive power, each remotely operated valve identified in Table 2.1.2-1 assumed the indicated loss of motive power position for Unit 4.

References 1 through 14 are available for NRC inspection as part of Unit 4 ITAAC Completion Package (Reference 15).

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 2.1.02.11a.ii (Reference 15) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.1.02.11a.ii 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-RCS-ITR-802047, Unit 4 Reactor Coolant System Safety-Related Displays Verification:

ITAAC 2.1.02.11a.ii Item 10 NRC Index Number: 47

2. NEI 08-01, Rev. 5 Corrected, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

3. WCAP-16096, Rev. 4, Software Program Manual for Common Q Systems

4. APP-PMS-T5-001, Rev. 5 ,AP1000 Protection and Safety Monitoring System Test Plan

5. SV4-PMS-T1P-009, Rev. 0, AP1000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Procedure

6. SV4-PMS-T2R-009, Rev. 2, AP1000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Report

7. SV4-GW-GCW-740, AP1000 Vogtle 4 PMS Software Installation - Software Release 9.0.0.1

8. SV4-GW-GCW-848, AP1000 Vogtle 4 PMS Software Installation - Software Release 9.0.0.4

9. B-GEN-ITPCI-001, Rev. 4, PMS CABINETS

10. SV4-PMS Cabinet Software Loading-001, Rev. 0, Unit 4 Software Loading for PMS Cabinets for Multiple ITAACs: ITAAC 2.1.02.11a.ii [NRC Index No. 47], ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No. 543], ITAAC 2.5.02.09d [NRC Index No. 548], ITAAC 2.5.04.02.i [NRC Index No. 557]

11. SV4-PMS-T2R-050, Rev. 1, "Vogtle AP1000 Protection and Safety Monitoring System Fuel Load Regression Test Report"

12. SV4-RCS-ITR-800047, Rev. 0, Unit 4 Recorded Results of Remotely Operated RCS Valves Controlled by PMS Listed in Table 2.1.2-1 Perform Active Safety Function: ITAAC 2.1.02.11a.ii Item 11.a) and 11.b) NRC Index Number: 47

13. SV4-RCS-ITR-801047, Rev. 0, Unit 4 Recorded Results of Remotely Operated RCS Valves Response to Loss of Motive Power: ITAAC 2.1.02.11a.ii Item 12.b) NRC Index Number: 47

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 7 of 11

14. SV4-PMS Cabinet Diagnostic Testing -001, Unit 4 PMS Cabinet Diagnostic Testing for Multiple ITAACs: ITAAC 2.1.02.11a.ii [NRC Index No. 47], ITAAC 2.5.02.06a.ii [NRC Index No. 530], ITAAC 2.5.02.08a.ii [NRC Index No. 540], ITAAC 2.5.02.08b.ii [NRC Index No.

543], ITAAC 2.5.02.09d [NRC Index No. 548], ITAAC 2.5.04.02.i [NRC Index No. 557]

15. 2.1.02.11a.ii-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 8 of 11 Attachment A

• Excerpt from COL Appendix C Table 2.1.2-1 Safety-Related Equipment Name* Tag No.* Display*

First-stage ADS Motor-operated Valve (MOV) RCS-PL-V001A Yes (Valve Position)

First-stage ADS MOV RCS-PL-V001B Yes (Valve Position)

Second-stage ADS MOV RCS-PL-V002A Yes (Valve Position)

Second-stage ADS MOV RCS-PL-V002B Yes (Valve Position)

Third-stage ADS MOV RCS-PL-V003A Yes (Valve Position)

Third-stage ADS MOV RCS-PL-V003B Yes (Valve Position)

Fourth-stage ADS Squib Valve RCS-PL-V004A Yes (Valve Position)

Fourth-stage ADS Squib Valve RCS-PL-V004B Yes (Valve Position)

Fourth-stage ADS Squib Valve RCS-PL-V004C Yes (Valve Position)

Fourth-stage ADS Squib Valve RCS-PL-V004D Yes (Valve Position)

First-stage ADS Isolation MOV RCS-PL-V011A Yes (Valve Position)

First-stage ADS Isolation MOV RCS-PL-V011B Yes (Valve Position)

Second-stage ADS Isolation MOV RCS-PL-V012A Yes (Valve Position)

Second-stage ADS Isolation MOV RCS-PL-V012B Yes (Valve Position)

Third-stage ADS Isolation MOV RCS-PL-V013A Yes (Valve Position)

Third-stage ADS Isolation MOV RCS-PL-V013B Yes (Valve Position)

Fourth-stage ADS MOV RCS-PL-V014A Yes (Valve Position)

Fourth-stage ADS MOV RCS-PL-V014B Yes (Valve Position)

Fourth-stage ADS MOV RCS-PL-V014C Yes (Valve Position)

Fourth-stage ADS MOV RCS-PL-V014D Yes (Valve Position)

Reactor Vessel Head Vent Valve RCS-PL-V150A Yes (Valve Position)

Reactor Vessel Head Vent Valve RCS-PL-V150B Yes (Valve Position)

Reactor Vessel Head Vent Valve RCS-PL-V150C Yes (Valve Position)

Reactor Vessel Head Vent Valve RCS-PL-V150D Yes (Valve Position)

RCS Hot Leg 1 Flow Sensor RCS-101A Yes RCS Hot Leg 1 Flow Sensor RCS-101B Yes RCS Hot Leg 1 Flow Sensor RCS-101C Yes RCS Hot Leg 1 Flow Sensor RCS-101D Yes RCS Hot Leg 2 Flow Sensor RCS-102A Yes RCS Hot Leg 2 Flow Sensor RCS-102B Yes RCS Hot Leg 2 Flow Sensor RCS-102C Yes RCS Hot Leg 2 Flow Sensor RCS-102D Yes RCS Cold Leg 1A Dual Range Temperature Sensor RCS-125A Yes (Wide Range)

RCS Cold Leg 2A Dual Range Temperature Sensor RCS-125B Yes (Wide Range)

RCS Cold Leg 1B Dual Range Temperature Sensor RCS-125C Yes (Wide Range)

RCS Cold Leg 2B Dual Range Temperature Sensor RCS-125D Yes (Wide Range)

RCS Hot Leg 1 Wide Range Temperature Sensor RCS-135A Yes RCS Hot Leg 2 Wide Range Temperature Sensor RCS-135B Yes RCS Wide Range Pressure Sensor RCS-140A Yes RCS Wide Range Pressure Sensor RCS-140B Yes RCS Wide Range Pressure Sensor RCS-140C Yes RCS Wide Range Pressure Sensor RCS-140D Yes

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 9 of 11 Attachment A

• Excerpt from COL Appendix C Table 2.1.2-1 Safety-Related Equipment Name* Tag No.* Display*

RCS Hot Leg 1 Level Sensor RCS-160A Yes RCS Hot Leg 2 Level Sensor RCS-160B Yes Passive Residual Heat Removal (PRHR) Return Line RCS-161 Yes Temperature Sensor Pressurizer Pressure Sensor RCS-191A Yes Pressurizer Pressure Sensor RCS-191B Yes Pressurizer Pressure Sensor RCS-191C Yes Pressurizer Pressure Sensor RCS-191D Yes Pressurizer Level Reference Leg Temperature RCS-193A Yes Sensor Pressurizer Level Reference Leg Temperature RCS-193B Yes Sensor Pressurizer Level Reference Leg Temperature RCS-193C Yes Sensor Pressurizer Level Reference Leg Temperature RCS-193D Yes Sensor Pressurizer Level Sensor RCS-195A Yes Pressurizer Level Sensor RCS-195B Yes Pressurizer Level Sensor RCS-195C Yes Pressurizer Level Sensor RCS-195D Yes RCP 1A Bearing Water Temperature Sensor RCS-211A Yes RCP 1A Bearing Water Temperature Sensor RCS-211B Yes RCP 1A Bearing Water Temperature Sensor RCS-211C Yes RCP 1A Bearing Water Temperature Sensor RCS-211D Yes RCP 1B Bearing Water Temperature Sensor RCS-212A Yes RCP 1B Bearing Water Temperature Sensor RCS-212B Yes RCP 1B Bearing Water Temperature Sensor RCS-212C Yes RCP 1B Bearing Water Temperature Sensor RCS-212D Yes RCP 2A Bearing Water Temperature Sensor RCS-213A Yes RCP 2A Bearing Water Temperature Sensor RCS-213B Yes RCP 2A Bearing Water Temperature Sensor RCS-213C Yes RCP 2A Bearing Water Temperature Sensor RCS-213D Yes RCP 2B Bearing Water Temperature Sensor RCS-214A Yes RCP 2B Bearing Water Temperature Sensor RCS-214B Yes RCP 2B Bearing Water Temperature Sensor RCS-214C Yes RCP 2B Bearing Water Temperature Sensor RCS-214D Yes RCP 1A Pump Speed Sensor RCS-281 Yes RCP 1B Pump Speed Sensor RCS-282 Yes RCP 2A Pump Speed Sensor RCS-283 Yes RCP 2B Pump Speed Sensor RCS-284 Yes

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 10 of 11 Attachment B

• Excerpt from COL Appendix C Table 2.1.2-1 Equipment Name* Tag No.* Active Function*

First-stage ADS Motor-operated RCS-PL-V001A Transfer Open Valve (MOV)

First-stage ADS MOV RCS-PL-V001B Transfer Open Second-stage ADS MOV RCS-PL-V002A Transfer Open Second-stage ADS MOV RCS-PL-V002B Transfer Open Third-stage ADS MOV RCS-PL-V003A Transfer Open Third-stage ADS MOV RCS-PL-V003B Transfer Open First-stage ADS Isolation MOV RCS-PL-V011A Transfer Open First-stage ADS Isolation MOV RCS-PL-V011B Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012A Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012B Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013A Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013B Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150A Transfer Closed/ Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150B Transfer Closed/ Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150C Transfer Closed/ Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150D Transfer Closed/ Transfer Open Attachment C

• Excerpt from COL Appendix C Table 2.1.2-1 Equipment Name* Tag No.* Control Active Function*

PMS/

DAS*

First-stage ADS Motor-operated RCS-PL-V001A Yes/Yes Transfer Open Valve (MOV)

First-stage ADS MOV RCS-PL-V001B Yes/Yes Transfer Open Second-stage ADS MOV RCS-PL-V002A Yes/Yes Transfer Open Second-stage ADS MOV RCS-PL-V002B Yes/Yes Transfer Open Third-stage ADS MOV RCS-PL-V003A Yes/Yes Transfer Open Third-stage ADS MOV RCS-PL-V003B Yes/Yes Transfer Open First-stage ADS Isolation MOV RCS-PL-V011A Yes/Yes Transfer Open First-stage ADS Isolation MOV RCS-PL-V011B Yes/Yes Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012A Yes/Yes Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012B Yes/Yes Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013A Yes/Yes Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013B Yes/Yes Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150A Yes/No Transfer Closed/ Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150B Yes/No Transfer Closed/ Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150C Yes/No Transfer Closed/ Transfer Open Reactor Vessel Head Vent Valve RCS-PL-V150D Yes/No Transfer Closed/ Transfer Open

U.S. Nuclear Regulatory Commission ND-23-0294 Enclosure Page 11 of 11 Attachment D

• Excerpt from COL Appendix C Table 2.1.2-1 Equipment Name* Tag No.* Opening Time**

First-stage ADS Motor-operated Valve (MOV) RCS-PL-V001A 26 sec First-stage ADS MOV RCS-PL-V001B 29 sec Second-stage ADS MOV RCS-PL-V002A 56 sec Second-stage ADS MOV RCS-PL-V002B 57 sec Third-stage ADS MOV RCS-PL-V003A 61 sec Third-stage ADS MOV RCS-PL-V003B 60 sec First-stage ADS Isolation MOV RCS-PL-V011A 15 sec First-stage ADS Isolation MOV RCS-PL-V011B 18 sec Second-stage ADS Isolation MOV RCS-PL-V012A 27 sec Second-stage ADS Isolation MOV RCS-PL-V012B 27 sec Third-stage ADS Isolation MOV RCS-PL-V013A 27 sec Third-stage ADS Isolation MOV RCS-PL-V013B 27 sec

• • rounded up to be consistent with the significant figures in COL Appendix C Attachment E

• Excerpt from COL Appendix C Table 2.1.2-1 Equipment Name* Tag No.* Loss of Motive Power Position*

First-stage ADS Motor-operated Valve (MOV) RCS-PL-V001A As Is First-stage ADS MOV RCS-PL-V001B As Is Second-stage ADS MOV RCS-PL-V002A As Is Second-stage ADS MOV RCS-PL-V002B As Is Third-stage ADS MOV RCS-PL-V003A As Is Third-stage ADS MOV RCS-PL-V003B As Is Fourth-stage ADS Squib Valve RCS-PL-V004A As Is Fourth-stage ADS Squib Valve RCS-PL-V004B As Is Fourth-stage ADS Squib Valve RCS-PL-V004C As Is Fourth-stage ADS Squib Valve RCS-PL-V004D As Is First-stage ADS Isolation MOV RCS-PL-V011A As Is First-stage ADS Isolation MOV RCS-PL-V011B As Is Second-stage ADS Isolation MOV RCS-PL-V012A As Is Second-stage ADS Isolation MOV RCS-PL-V012B As Is Third-stage ADS Isolation MOV RCS-PL-V013A As Is Third-stage ADS Isolation MOV RCS-PL-V013B As Is Fourth-stage ADS MOV RCS-PL-V014A As Is Fourth-stage ADS MOV RCS-PL-V014B As Is Fourth-stage ADS MOV RCS-PL-V014C As Is Fourth-stage ADS MOV RCS-PL-V014D As Is Reactor Vessel Head Vent Valve RCS-PL-V150A Closed Reactor Vessel Head Vent Valve RCS-PL-V150B Closed Reactor Vessel Head Vent Valve RCS-PL-V150C Closed Reactor Vessel Head Vent Valve RCS-PL-V150D Closed