ND-19-1118, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.11a.ii (Index Number 47)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.1.02.11a.ii (Index Number 47)

ML19268B720
Person / Time
Site:	Vogtle
Issue date:	09/25/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-1118
Download: ML19268B720 (14)

Text

^Southern Nuclear Michael J. Vox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel SEP 2 5 2019 Docket Nos.: 52-025 52-026 ND-19-1118 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.1.02.11a.ii [Index Number 471 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of August 26, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.1.02.1 la.ii

[Index Number 47] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.1.02.1 la.ii [Index Number 47]. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.

All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).

This letter contains no new NRC regulatory commitments.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted, Michael J. Vox Regulatory Affairs Directof Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.1 la.ii [Index Number 47]

MJY/JBN/sfr

U.S. Nuclear Regulatory Commission ND-19-1118 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKinney (w/o enclosures)

Mr. M. D. Meier (w/o enclosures)

Mr. D. H. Jones (w/o enclosures)

Mr. G. Chick Mr. M. Page Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Mr. W.Jones (w/o enclosures)

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1118 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 1 of 11 Southern Nuclear Operating Company ND-19-1118 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.1.02.1 la.ii [Index Number 47]

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 2 of 11 ITAAC Statement Desion 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-I to perform active functions.

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

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/Analvses 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 RMS.

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 RMS control perform the active function identified in the table after receiving a signal from RMS.

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

V001A/B <40 sec V002A/B, V003A/B Si GO sec veil A/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-19-1118 Enclosure Page 3 of 11 ITAAC Completion Description Multiple ITAAC are 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 that 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 are performed to demonstrate that safety-related displays identified in Table 2.1.2-1 can be retrieved in the MCR and that after the loss of motive power, the remotely operated valves identified in Table 2.1.2-1 assume the indicated loss of motive power position.

Safetv-related displavs identified in Table 2.1.2-1 can be retrieved in the MCR.

Inspections performed in accordance with the Unit 3 and Unit 4 component test package work orders SNC921644 and SNCYYYYYY (References 1 and 2), visually confirm 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 display appears on the PMS VDU.

The completed inspection results confirm that safety-related displays identified in Table 2.1.2-1 can be retrieved in Unit 3 and Unit 4 MCR.

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

ITAAC 2.1.02.11a.ii item lla.ii is 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)follows the guidance of NEI 08-01 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 PMS Software Program Manual WCAP-16096(Reference 3), PMS Test Plan APP-PMS-T5-001 (Reference 4) and applicable Codes and Standards described in Vogtle 3 and 4 UFSAR Section 7.

Testing performed in accordance with FAT procedures SV3/SV4/APP-PMS-T1P-009 (References 5 through 7) verifies 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 are documented in SV3/SV4/APP-PMS-T2R-009 (References 8 through 10). Attachment B provides a listing of test cases used to test the logic and functionality.

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 4 of 11 Software installation and testing are performed on site to verify that the cabinets are intact and functional in accordance with Units 3 and 4 Field Change Notification (FCN) xxxx (References 11 and 12). References 11 and 12 include steps that confirm and document successful software load and further confirm the physical properties of the as-built RMS. A regression analysis (i.e.,

change evaluation) is performed post delivery and installation for hardware and software changes to determine if additional testing is needed for the as-built system.

Testing from the CIM to the remotely operated valves identified in Attachment B is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 13 and 14). These component test packages utilize B-GEN-ITPCI-039(Reference

15) to direct the performance of test procedures 3/4-RCS-OTS-10-001 (References 16 and 17).

Each valve is stroked to its active function from the PMS Maintenance and Test Panel(MTP) which actuates the CIM and proper valve position indication is verified locally and in the MGR.

The completed test results (References 8 through 14) confirm that controls in Unit 3 and Unit 4 MGR operate to cause the remotely operated valves identified in Table 2.1.2-1 to perform active functions.

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

Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 13 and 14). These component test packages utilize B-GEN-ITPCI-039(Reference 15) to direct the performance of test procedures 3/4-RCS-OTS-10-001 (References 16 and 17) to confirm that the remotely operated valves other than squib valves perform the active o function identified in Attachment C after a signal is input to the PMS. OC IV References 16 and 17 establish initial conditions with each valve verified locally and in the MCR to be in the required position. An actuation signal is 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 is verified locally and in the MCR.

The completed test results (References 13 and 14) confirm 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 3 and Unit 4.

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

V001A/B <40 sec V002A/B. V003A/B <1001 sec V011A/B sec V012A/B. V013A/B <60 sec Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 13 and 14). These component test packages utilize B-GEN-ITPCI-039(Reference 15) to direct the performance of test procedures 3/4-RCS-OTS-10-001 (References 16 and 17) to confirm that remotely operated RCS valves RCS-V001A/B open within 40 seconds, V002A/B and V003A/B open within 100 seconds, V01 l/VB

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 5 of 11 opens within 30 seconds, and V012A/B and V013A/B open within 60 seconds after receipt of an actuation signal.

References 16 and 17 establish initial conditions with each valve verified locally and in the MGR to be in the closed position and a digital trend is established to time the valve actuation. An actuation signal is 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 MGR.

The completed test results (References 13 and 14) confirm that remotely operated RGS valves RGS-V001A/B open within 40 seconds, V002A/B and V003A/B open within 100 seconds, V011A/B opens within 30 seconds, and V012A/B and V013A/B open within 60 seconds after receipt of an actuation signal for Unit 3 and Unit 4 and the test results are documented in Attachment D.

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

Testing is performed in accordance with Unit 3 and Unit 4 component test work packages, SNG921652 and SNGYYYYYY (References 18 and 19) to verify that each remotely operated valve identified in Attachment E assumes the indicated loss of motive power position upon a loss of motive power.

Testing is performed on the Motor-Operated Valves(MOVs)listed in Attachment E by opening the power supply to the MOVs when they are closed and verifying they remain closed in the MGR. Power is restored to the MOVs and they are opened. The power supply to the MOVs is opened and they are verified to remain open in the MGR.

Testing on the air operated valves is 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 causes the solenoid to de-energize which closes the air supply to the valve and opens a vent port to vent off the air in the actuator. The valves are verified in the MGR 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 Gurrent(DG) 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 ITAAG.

The completed test results (References 18 and 19) confirm that after loss of motive power, each remotely operated valve identified in Table 2.1.2-1 assumes the indicated loss of motive power position for Unit 3 and Unit 4.

References 1 through 19 are available for NRG inspection as part of Unit 3 and Unit 4 ITAAG Gompletion Packages (Reference 20 and 21).

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 6 of 11 List of ITAAC Findings 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.

References(available for NRG inspection)

1. SNC921644,"Reactor Coolant System Indication Verifications ITAAC: SV3-2.1.02.11a.ii Item 10"

2. SNCYYYYYY,"Reactor Coolant System Indication Verifications ITAAC: SV4-2.1.02.1 la.ii Item 10"

3. WCAP-16096,"Software Program Manual for Common Q Systems" Revision 4A

4. APP-PMS-T5-001,"API000 Protection and Safety Monitoring System Test Plan"

5. APP-PMS-T1P-009 "API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Procedure"

6. SV3-PMS-T1 P-009 "API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Procedure"

7. SV4-PMS-T1 P-009 "API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Procedure"

8. APP-PMS-T2R-009 "API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Report"

9. SV3-PMS-T2R-009 "API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Report"

10. SV4-PMS-T2R-009 "API000 Protection and Safety Monitoring System Integrated Logic Processor Component Logic Channel Integration Test Report"

11. Unit 3 Field Change Notice "PMS Software"

12. Unit 4 Field Change Notice "PMS Software"

13. SNCXXXXXX

14. SNCYYYYYY

15. B-GEN-ITPCI-039,"PMS CIM Component Test Procedure" 16.3-RCS-OTS-10-001,"Reactor Coolant System Valve Stroke Test" 17.4-RCS-0TS-10-001,"Reactor Coolant System Valve Stroke Test"

18. SNC921652,"Loss of Motive Power Test for RCS - ITAAC: SV3-2.1.02.1 la.ii. Item 12b"

19. SNCYYYYYY, Loss of Motive Power Test for RCS - ITAAC: SV3-2.1.02.1 la.ii. Item 12b" 20.2.1.02.11a.ii-U3-CP-RevO, ITAAC Completion Package 21.2.1.02.11a.ii-U4-CP-Rev0, ITAAC Completion Package

22. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 7 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 Posit on)

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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 IB Dual Range Temperature Sensor RCS-125C Yes(Wide Range RCS Cold Leg 28 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-19-1118 Enclosure Page 8 of 11 Attachment A(continued)

'Excerpt from COL Appendix C Table 2.1.2-1 Equipment Name* Tag No.* Safety-Related 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 Bear ng Water Temperature Sensor RCS-211A Yes RCP 1A Bear ng Water Temperature Sensor RCS-211B Yes RCP 1A Bear ng Water Temperature Sensor RCS-211C Yes RCP 1A Bear ng Water Temperature Sensor RCS-211D Yes RCP 1B Bear ng Water Temperature Sensor RCS-212A Yes RCP 1B Bear ng Water Temperature Sensor RCS-212B Yes RCP 1B Bear ng Water Temperature Sensor RCS-212C Yes RCP 1B Bear ng Water Temperature Sensor RCS-212D Yes RCP 2A Bear ng Water Temperature Sensor RCS-213A Yes RCP 2A Bear ng Water Temperature Sensor RCS-213B Yes RCP 2A Bear ng Water Temperature Sensor RCS-213C Yes RCP 2A Bear ng Water Temperature Sensor RCS-213D Yes RCP 2B Bear ng Water Temperature Sensor RCS-214A Yes RCP 2B Bear ng Water Temperature Sensor RCS-214B Yes RCP 2B Bear ng Water Temperature Sensor RCS-214C Yes RCP 2B Bear ng 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-19-1118 Enclosure Page 9 of 11 Attachment B "Excerpt from COL Appendix C Table 2.1.2-1 Equipment Name* Tag No.* Active Function* Test Case First-stage ADS Motor-operated RCS-PL-V001A Transfer Open TPS03A-01.41 Valve(MOV)

First-stage ADS MOV RCS-PL-V001B Transfer Open TPS03B-01.48 Second-stage ADS MOV RCS-PL-V002A Transfer Open TPS03C-01.27 Second-stage ADS MOV RCS-PL-V002B Transfer Open TPS03D-01.48 Third-stage ADS MOV RCS-PL-V003A Transfer Open TPS03A-01.42 Third-stage ADS MOV RCS-PL-V003B Transfer Open TPS03B-01.49 First-stage ADS Isolation MOV RCS-PL-V011A Transfer Open TPS03A-01.31 First-stage ADS Isolation MOV RCS-PL-V011B Transfer Open TPS03B-01.18 Second-stage ADS Isolation MOV RCS-PL-V012A Transfer Open TPS03C-01.20 Second-stage ADS Isolation MOV RCS-PL-V012B Transfer Open TPS03D-01.39 Third-stage ADS Isolation MOV RCS-PL-V013A Transfer Open TPS03A-01.32 Third-stage ADS Isolation MOV RCS-PL-V013B Transfer Open TPS03B-01.19 Reactor Vessel Head Vent Valve RCS-PL-V150A Transfer Closed/ Transfer Open TPS03A-01.18 Reactor Vessel Head Vent Valve RCS-PL-V150B Transfer Closed/ Transfer Open TPS03B-01.28 Reactor Vessel Head Vent Valve RCS-PL-V150C Transfer Closed/ Transfer Open TPS03C-01.7 Reactor Vessel Head Vent Valve RCS-PL-V150D Transfer Closed/ Transfer Open TPS03D-01.18

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 10 of 11 Attachment C

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

RMS/

DAS*

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

First-stage ADS MOV RCS-PL-V001B YesA'es Transfer Open Second-stage ADS MOV RCS-PL-V002A YesA'es Transfer Open Second-stage ADS MOV RCS-PL-V002B YesA'es Transfer Open Third-stage ADS MOV RCS-PL-V003A YesA'es Transfer Open Third-stage ADS MOV RCS-PL-V003B YesA'es Transfer Open First-stage ADS Isolation MOV RCS-PL-V011A YesA'es Transfer Open First-stage ADS Isolation MOV RCS-PL-V011B YesA'es Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012A YesA'es Transfer Open Second-stage ADS Isolation MOV RCS-PL-V012B YesA'es Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013A YesA'es Transfer Open Third-stage ADS Isolation MOV RCS-PL-V013B YesA'es 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 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 XX sec First-stage ADS MOV RCS-PL-V001B XX sec Second-stage ADS MOV RCS-PL-V002A XX sec Second-stage ADS MOV RCS-PL-V002B XX sec Third-stage ADS MOV RCS-PL-V003A XX sec Third-stage ADS MOV RCS-PL-V003B XX sec First-stage ADS Isolation MOV RCS-PL-V011A XX sec First-stage ADS Isolation MOV RCS-PL-V011B XX sec Second-stage ADS Isolation MOV RCS-PL-V012A XX sec Second-stage ADS Isolation MOV RCS-PL-V012B XX sec Third-stage ADS Isolation MOV RCS-PL-V013A XX sec Third-stage ADS Isolation MOV RCS-PL-V013B XX sec

U.S. Nuclear Regulatory Commission ND-19-1118 Enclosure Page 11 of 11 Attachment E

'Excerpt from COL Appendix 0 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