ND-23-0446, ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250)

ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250)

ML23196A007
Person / Time
Site:	Vogtle
Issue date:	07/15/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ITAAC 2.2.04.12a, ND-23-0446
Download: ML23196A007 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel July 15, 2023 Docket No.: 52-026 ND-23-0446 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 2.2.04.12a.iii [Index Number 250]

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 2.2.04.12a.iii [Index Number 250]. This ITAAC confirms that:

• The valves identified in Combined License Appendix C Table 2.2.4-3 close after a signal is generated by the Protection and Safety Monitoring System (PMS).

• Safety-related displays identified in Combined License Appendix C Table 2.2.4-1 (Table 2.2.4-1) can be retrieved in the Main Control Room (MCR).

• Controls in the MCR operate to cause the remotely operated valves identified in Table 2.2.4-1 to perform active safety functions.

• The remotely-operated valves identified in Table 2.2.4-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS.

• Steam Generator System (SGS) isolation valves SGS-V027A/B, SGS-V040A/B, SGS-V057A/B and SGS-V250A/B close within the times identified in Combined License Appendix C Table 2.2.4-4 after receipt of an actuation signal.

• Each motor-operated valve identified in Table 2.2.4-1 changes position as indicated in Table 2.2.4-1 under preoperational test conditions.

• After loss of motive power, each remotely operated valve identified in Table 2.2.4-1 assumes the indicated loss of motive power position.

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) 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.

U.S. Nuclear Regulatory Commission ND-23-0446 Page 2 of 2 Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.12a.iii [Index Number 250]

JMC/TJC/sfr 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-23-0446 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-23-0446 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.12a.iii [Index Number 250]

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 2 of 13 ITAAC Statement Design Commitment 9.a) Components within the main steam system, main and startup feedwater system, and the main turbine system identified in Table 2.2.4-3 provide backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.

10. Safety-related displays identified in Table 2.2.4-1 can be retrieved in the MCR.

11.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.4-1 to perform active functions.

11.b) The valves identified in Table 2.2.4-1 as having PMS control perform an active safety function after receiving a signal from PMS.

12.a) The motor-operated valves identified in Table 2.2.4-1 perform an active safety-related function to change position as indicated in the table.

12.b) After loss of motive power, the remotely operated valves identified in Table 2.2.4-1 assume the indicated loss of motive power position.

Inspections/Tests/Analyses i) Testing will be performed to confirm closure of the valves identified in Table 2.2.4-3.

Inspection will be performed for retrievability of the safety-related displays in the MCR.

Stroke testing will be performed on the remotely operated valves listed in Table 2.2.4-1 using controls in the MCR.

i) Testing will be performed on the remotely operated valves listed in Table 2.2.4-1 using real or simulated signals into the PMS.

ii) Testing will be performed to demonstrate that remotely operated SGS isolation valves SGS-V027A/B, V040A/B, V057A/B, V250A/B close within the required response times.

iii) Tests of the motor-operated valves will be performed under pre-operational flow, differential pressure, and temperature conditions.

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

Acceptance Criteria i) The valves identified in Table 2.2.4-3 close after a signal is generated by the PMS.

Safety-related displays identified in Table 2.2.4-1 can be retrieved in the MCR.

Controls in the MCR operate to cause the remotely operated valves to perform active safety functions.

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 3 of 13 i) The remotely-operated valves identified in Table 2.2.4-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS.

ii) These valves close within the following times after receipt of an actuation signal:

V027A/B < 44 sec V040A/B, V057A/B < 5 sec V250A/B < 5 sec iii) Each motor-operated valve changes position as indicated in Table 2.2.4-1 under preoperational test conditions.

After loss of motive power, each remotely operated valve identified in Table 2.2.4-1 assumes the indicated loss of motive power position. Motive power to SGS-PL-V040A/B and SGS-PL-V057A/B is electric power to the actuator from plant services.

ITAAC Determination Basis Testing and inspections were performed to, verify that the valves identified in Combined License (COL) Appendix C Table 2.2.4-3 (Attachment A and Attachment B) close after a signal is generated by the Protection and Safety Monitoring System (PMS), that safety-related displays identified in COL Appendix C Table 2.2.4-1 (Attachment C) can be retrieved in the Main Control Room (MCR), that controls in the MCR operate to cause the remotely operated valves identified in COL Appendix C Table 2.2.4-1 (Attachment D) to perform active safety functions, and the remotely operated valves identified in COL Appendix C Table 2.2.4-1 (Attachment E) as having PMS control perform the active function identified in the table after receiving a real or simulated signal from the PMS. This ITAAC also verified selected Steam Generator System (SGS) valves (Attachment F) close within the prescribed time after receipt of an actuation signal, that each Motor-Operated Valve (MOV) changes position as indicated in COL Appendix C Table 2.2.4-1 (Attachment G) under preoperational test conditions, and that after a loss of motive power, each remotely operated valve identified in COL Appendix C Table 2.2.4-1 (Attachment H) assumes the indicated loss of motive power position.

i) The valves identified in Table 2.2.4-3 close after a signal is generated by the PMS.

Testing was performed as described in ITAAC Technical Report SV4-SGS-ITR-800250 (Reference 1) to verify that the valves identified in Attachment A and Attachment B close after a signal is generated by the PMS.

Testing was done to verify the valves in Attachment B close after a signal is generated by the PMS. Testing was performed by verifying the Main Turbine Stop Valves and Control Valves were open. The PMS reactor trip hand switch was placed to trip and the Main Turbine Stop and Control valves were verified to close on MCR displays. This testing confirms that the valves in Attachment B close after a signal is generated by the PMS.

Reference 1 describes the testing performed to verify the valves in Attachment A were open. A manual PMS actuation signal was generated from the PMS Maintenance and Test Cabinet (MTC) and the valves in Attachment A were verified to close locally. This testing confirmed that the valves in Attachment A close after a signal is generated by the PMS.

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 4 of 13 The combination of these tests for Unit 4 verified the valves identified in Table 2.2.4-3 close after a signal is generated by the PMS.

Safety-related displays identified in Table 2.2.4-1 can be retrieved in the MCR.

The inspection was performed as described in ITAAC Technical Report SV4-SGS-ITR-801250 (Reference 2) to verify that the safety-related displays identified in Attachment C can be retrieved in the MCR.

The inspection was conducted at the MCR PMS Visual Display Units (VDUs) and verified the safety-related displays in Attachment C can be retrieved in the MCR. Each valve and indication listed in Attachment C was located on the VDUs and verified to display. This confirms that all the safety-related displays identified in Table 2.2.4-1 can be retrieved in the Unit 4 MCR.

Controls in the MCR operate to cause the remotely operated valves to perform active safety functions.

Testing was performed as described in ITAAC Technical Report SV4-SGS-ITR-801250 (Reference 2) to verify that controls in the MCR operate to cause the remotely operated valves in Attachment D to perform active safety functions.

Testing was conducted at an operator workstation in the Unit 4 MCR to verify the valves identified in Attachment D as being remotely operated and having active safety functions are stroked open and closed from the MCR. The valve positions were locally verified and verified in the MCR. This confirms that controls in the Unit 4 MCR operate to cause the remotely operated valves to perform active safety functions.

i) The remotely-operated valves identified in Table 2.2.4-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS.

Testing was performed as described in ITAAC Technical Report SV4-SGS-ITR-802250 (Reference 3) to confirm the remotely-operated valves identified in Attachment E as having PMS control perform the active function identified in the table after receiving a signal from the PMS.

As described in Reference 3 the valves listed in Attachment E were verified to be Open and testing was performed by utilizing the PMS Maintenance and Test Cabinet (MTC) to generate a PMS output signal. The valves in Attachment E were verified to close by MCR indication and locally at the valves when the PMS output signal was generated.

The testing described in Reference 3 confirmed the remotely-operated valves identified in Table 2.2.4-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS for Unit 4.

ii) These valves close within the following times after receipt of an actuation signal:

V027A/B < 44 sec V040A/B, V057A/B < 5 sec V250A/B < 5 sec

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 5 of 13 Testing was performed as described in Reference 3 to confirm the following valves close within the following times after receipt of an actuation signal: V027A/B < 44 sec; V040A/B, V057A/B <

5 sec; V250A/B < 5 sec (Attachment F).

Testing was performed as described in Reference 3. The valves in Attachment F were verified to be Open, a trend was established to record valve timing information, and testing was performed utilizing the PMS MTC to generate a PMS output signal. The valves in Attachment F were verified to close, the valve closure time was recorded in the test, and valve closure time summarized in Attachment F.

This testing confirmed that these valves close within the following times after receipt of an actuation signal: V027A/B < 44 sec; V040A/B, V057A/B < 5 sec; V250A/B < 5 sec.

iii) Each motor-operated valve changes position as indicated in Table 2.2.4-1 under preoperational test conditions.

Testing was performed as described in ITAAC Technical Report SV4-SGS-ITR-803250 (Reference 4) to verify each motor-operated valve changes position as indicated in Attachment G under preoperational test conditions.

The testing ensured the Reactor Coolant System (RCS) was at the 557°F plateau to establish the secondary system conditions required for this preoperational testing. The steam generator power-operated relief valve was opened from the MCR, and SGS-PL-V027A (Power-operated Relief Valve Block MOV Steam Generator 01) was closed and locally verified to be closed. This testing was repeated for SGS-PL-V027B (Power-operated Relief Valve Block MOV Steam Generator 02).

Startup feedwater flow was verified to be 200 gpm or greater, and SGS-PL-V067A (Startup Feedwater Isolation MOV) was closed and locally verified to be closed. This testing was repeated for SGS-PL-V067B (Startup Feedwater Isolation MOV).

The test results verified that for Unit 4 each motor-operated valve changes position as indicated in Table 2.2.4-1 under preoperational test conditions.

After loss of motive power, each remotely operated valve identified in Table 2.2.4-1 assumes the indicated loss of motive power position. Motive power to SGS-PL-V040A/B and SGS-PL-V057A/B is electric power to the actuator from plant services.

Testing was performed as described in ITAAC Technical Report SV4-SGS-ITR-804250 (Reference 5) to demonstrate that after a loss of motive power, each remotely operated valve identified in Attachment H assumes the indicated loss of motive power position. Motive power to SGS-PL-V040A/B and SGS-PL-V057A/B is electric power to the actuator from plant services (plant electrical power to the operating solenoids).

Reference 5 describes and documents how each of the component tests were performed. The air operated valves were placed in the Open position and power removed to the solenoid valve supplying air to the valve actuators which removed motive power from the valves. The air operated valves were locally verified to fail to their loss of motive power position (closed). The motor-operated valves (MOVs) were each stroked to their fully Open position by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 6 of 13 the fully 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. Each MOV was also stroked fully Closed by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the fully Closed position was reached. This loss of power caused by the valve control circuit demonstrated the MOV failed As-Is (Closed) when motive power was removed. MOV positions were verified locally and in the MCR during the MOV testing. The hydraulic/pneumatic valves (SGS-PL-V040A/B and SGS-PL-V057A/B) were configured to the Open position, power was removed from the actuator (electrical power to the operating solenoids), and the valves were verified to fail to their loss of motive power position (As-Is). Testing was repeated with the hydraulic/pneumatic valves in the Closed position and the valves were again verified to fail to their loss of motive power position (As-Is).

The test results verified for Unit 4 that after loss of motive power, each remotely operated valve identified in Table 2.2.4-1 assumes the indicated loss of motive power position. Motive power to SGS-PL-V040A/B and SGS-PL-V057A/B is electric power to the actuator from plant services.

The completed test results (References 1 through 5) are available for NRC inspection as part of the Unit 4 ITAAC 2.2.04.12a.iii Completion Package (Reference 6).

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 were no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.04.12a.iii (Reference 6) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.04.12a.iii 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-SGS-ITR-800250, Unit 4 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 9.a) NRC Index Number: 250, Rev 0

2. SV4-SGS-ITR-801250, Unit 4 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Items 10 & 11a NRC Index Number: 250, Rev. 0

3. SV4-SGS-ITR-802250, Unit 4 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 11.b) NRC Index Number: 250, Rev. 1

4. SV4-SGS-ITR-803250, Unit 4 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 12.a) NRC Index Number: 250, Rev. 1

5. SV4-SGS-ITR-804250, Unit 4 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 12.b) NRC Index Number: 250, Rev. 0

6. 2.2.04.12a.iii-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 7 of 13 Attachment A

• Excerpt from COL Appendix C Table 2.2.4-3

• Equipment Name *Tag No. *Control Function Turbine Bypass Control Valve MSS-PL-V001 Close Turbine Bypass Control Valve MSS-PL-V002 Close Turbine Bypass Control Valve MSS-PL-V003 Close Turbine Bypass Control Valve MSS-PL-V004 Close Turbine Bypass Control Valve MSS-PL-V005 Close Turbine Bypass Control Valve MSS-PL-V006 Close Moisture Separator Reheater 2nd Stage Steam MSS-PL-V015A Close Isolation Valve Moisture Separator Reheater 2nd Stage Steam MSS-PL-V015B Close Isolation Valve Attachment B

• Excerpt from COL Appendix C Table 2.2.4-3

• Equipment Name *Tag No. *Control Function Turbine Stop Valve MTS-PL-V001A Close Turbine Stop Valve MTS-PL-V001B Close Turbine Control Valve MTS-PL-V002A Close Turbine Control Valve MTS-PL-V002B Close Turbine Stop Valve MTS-PL-V003A Close Turbine Stop Valve MTS-PL-V003B Close Turbine Control Valve MTS-PL-V004A Close Turbine Control Valve MTS-PL-V004B Close

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 8 of 13 Attachment C

• Excerpt from COL Appendix C Table 2.2.4-1

• Equipment Name *Tag No. *Safety-Related Display Power-operated Relief Valve Block SGS-PL-V027A Yes (Valve Position)

Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Yes (Valve Position)

Motor-operated Valve Steam Generator 02 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes (Valve Position)

Steam Line Condensate Drain Isolation Valve SGS-PL-V036B Yes (Valve Position)

Main Steam Line Isolation Valve SGS-PL-V040A Yes (Valve Position)

Main Steam Line Isolation Valve SGS-PL-V040B Yes (Valve Position)

Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes (Valve Position)

Steam Line Condensate Drain Control Valve SGS-PL-V086B Yes (Valve Position)

Main Feedwater Isolation Valve SGS-PL-V057A Yes (Valve Position)

Main Feedwater Isolation Valve SGS-PL-V057B Yes (Valve Position)

Startup Feedwater Isolation SGS-PL-V067A Yes (Valve Position)

Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Yes (Valve Position)

Motor-operated Valve Steam Generator Blowdown Isolation Valve SGS-PL-V074A Yes (Valve Position)

Steam Generator Blowdown Isolation Valve SGS-PL-V074B Yes (Valve Position)

Steam Generator Blowdown Isolation Valve SGS-PL-V075A Yes (Valve Position)

Steam Generator Blowdown Isolation Valve SGS-PL-V075B Yes (Valve Position)

Power-operated Relief Valve SGS-PL-V233A Yes (Valve Position)

Power-operated Relief Valve SGS-PL-V233B Yes (Valve Position)

Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes (Valve Position)

Main Steam Isolation Valve Bypass Isolation SGS-PL-V240B Yes (Valve Position)

Main Feedwater Control Valve SGS-PL-V250A Yes (Valve Position)

Main Feedwater Control Valve SGS-PL-V250B Yes (Valve Position)

Startup Feedwater Control Valve SGS-PL-V255A Yes (Valve Position)

Startup Feedwater Control Valve SGS-PL-V255B Yes (Valve Position)

Steam Generator 1 Narrow Range Level Sensor SGS-001 Yes Steam Generator 1 Narrow Range Level Sensor SGS-002 Yes Steam Generator 1 Narrow Range Level Sensor SGS-003 Yes Steam Generator 1 Narrow Range Level Sensor SGS-004 Yes Steam Generator 2 Narrow Range Level Sensor SGS-005 Yes Steam Generator 2 Narrow Range Level Sensor SGS-006 Yes

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 9 of 13 Attachment C (cont.)

• Equipment Name *Tag No. *Safety-Related Display Steam Generator 2 Narrow Range Level Sensor SGS-007 Yes Steam Generator 2 Narrow Range Level Sensor SGS-008 Yes Steam Generator 1 Wide Range Level Sensor SGS-011 Yes Steam Generator 1 Wide Range Level Sensor SGS-012 Yes Steam Generator 2 Wide Range Level Sensor SGS-013 Yes Steam Generator 2 Wide Range Level Sensor SGS-014 Yes Steam Generator 1 Wide Range Level Sensor SGS-015 Yes Steam Generator 1 Wide Range Level Sensor SGS-016 Yes Steam Generator 2 Wide Range Level Sensor SGS-017 Yes Steam Generator 2 Wide Range Level Sensor SGS-018 Yes Main Steam Line Steam Generator 1 Pressure Sensor SGS-030 Yes Main Steam Line Steam Generator 1 Pressure Sensor SGS-031 Yes Main Steam Line Steam Generator 1 Pressure Sensor SGS-032 Yes Main Steam Line Steam Generator 1 Pressure Sensor SGS-033 Yes Main Steam Line Steam Generator 2 Pressure Sensor SGS-034 Yes Main Steam Line Steam Generator 2 Pressure Sensor SGS-035 Yes Main Steam Line Steam Generator 2 Pressure Sensor SGS-036 Yes Main Steam Line Steam Generator 2 Pressure Sensor SGS-037 Yes Steam Generator 1 Startup Feedwater Flow Sensor SGS-55A Yes Steam Generator 1 Startup Feedwater Flow Sensor SGS-55B Yes Steam Generator 2 Startup Feedwater Flow Sensor SGS-56A Yes Steam Generator 2 Startup Feedwater Flow Sensor SGS-56B Yes

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 10 of 13 Attachment D

• Excerpt from COL Appendix C Table 2.2.4-1

• Equipment Name *Tag No. *Remotely *Active Function Operated Valve Power-operated Relief Valve Block SGS-PL-V027A Yes Transfer Closed Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Yes Transfer Closed Motor-operated Valve Steam Generator 02 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes Transfer Closed Steam Line Condensate Drain Isolation Valve SGS-PL-V036B Yes Transfer Closed Main Steam Line Isolation Valve SGS-PL-V040A Yes Transfer Closed Main Steam Line Isolation Valve SGS-PL-V040B Yes Transfer Closed Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes Transfer Closed Steam Line Condensate Drain Control Valve SGS-PL-V086B Yes Transfer Closed Main Feedwater Isolation Valve SGS-PL-V057A Yes Transfer Closed Main Feedwater Isolation Valve SGS-PL-V057B Yes Transfer Closed Startup Feedwater Isolation SGS-PL-V067A Yes Transfer Closed Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Yes Transfer Closed Motor-operated Valve Steam Generator Blowdown Isolation Valve SGS-PL-V074A Yes Transfer Closed Steam Generator Blowdown Isolation Valve SGS-PL-V074B Yes Transfer Closed Steam Generator Blowdown Isolation Valve SGS-PL-V075A Yes Transfer Closed Steam Generator Blowdown Isolation Valve SGS-PL-V075B Yes Transfer Closed Power-operated Relief Valve SGS-PL-V233A Yes Transfer Closed Power-operated Relief Valve SGS-PL-V233B Yes Transfer Closed Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Transfer Closed Main Steam Isolation Valve Bypass Isolation SGS-PL-V240B Yes Transfer Closed Main Feedwater Control Valve SGS-PL-V250A Yes Transfer Closed Main Feedwater Control Valve SGS-PL-V250B Yes Transfer Closed Startup Feedwater Control Valve SGS-PL-V255A Yes Transfer Closed Startup Feedwater Control Valve SGS-PL-V255B Yes Transfer Closed

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 11 of 13 Attachment E

• Excerpt from COL Appendix C Table 2.2.4-1

• Equipment Name *Tag No. *Remotely *Control *Active Operated PMS Function Valve Steam Line Condensate Drain SGS-PL-V036A Yes Yes Transfer Closed Isolation Valve Steam Line Condensate Drain SGS-PL-V036B Yes Yes Transfer Closed Isolation Valve Main Steam Line Isolation Valve SGS-PL-V040A Yes Yes Transfer Closed Main Steam Line Isolation Valve SGS-PL-V040B Yes Yes Transfer Closed Steam Line Condensate Drain SGS-PL-V086A Yes Yes Transfer Closed Control Valve Steam Line Condensate Drain SGS-PL-V086B Yes Yes Transfer Closed Control Valve Main Feedwater Isolation Valve SGS-PL-V057A Yes Yes Transfer Closed Main Feedwater Isolation Valve SGS-PL-V057B Yes Yes Transfer Closed Steam Generator Blowdown SGS-PL-V074A Yes Yes Transfer Closed Isolation Valve Steam Generator Blowdown SGS-PL-V074B Yes Yes Transfer Closed Isolation Valve Steam Generator Blowdown SGS-PL-V075A Yes Yes Transfer Closed Isolation Valve Steam Generator Blowdown SGS-PL-V075B Yes Yes Transfer Closed Isolation Valve Main Steam Isolation Valve SGS-PL-V240A Yes Yes Transfer Closed Bypass Isolation Main Steam Isolation Valve SGS-PL-V240B Yes Yes Transfer Closed Bypass Isolation Startup Feedwater Control Valve SGS-PL-V255A Yes Yes Transfer Closed Startup Feedwater Control Valve SGS-PL-V255B Yes Yes Transfer Closed Power-operated Relief Valve Block SGS-PL-V027A Yes Yes Transfer Closed Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Yes Yes Transfer Closed Motor-operated Valve Steam Generator 02 Startup Feedwater Isolation SGS-PL-V067A Yes Yes Transfer Closed Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Yes Yes Transfer Closed Motor-operated Valve Power-operated Relief Valve SGS-PL-V233A Yes Yes Transfer Closed Power-operated Relief Valve SGS-PL-V233B Yes Yes Transfer Closed Main Feedwater Control Valve SGS-PL-V250A Yes Yes Transfer Closed Main Feedwater Control Valve SGS-PL-V250B Yes Yes Transfer Closed

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 12 of 13 Attachment F

• Excerpt from COL Appendix C Table 2.2.4-1 Unit *Equipment Name *Tag No. Closure time (Sec) 4 Power-operated Relief Valve Block SGS-PL-V027A 25.84 Motor-operated Valve Steam Generator 01 4 Power-operated Relief Valve Block SGS-PL-V027B 24.84 Motor-operated Valve Steam Generator 02 4 Main Steam Line Isolation Valve SGS-PL-V040A 4.66 4 Main Steam Line Isolation Valve SGS-PL-V040B 4.76 4 Main Feedwater Isolation Valve SGS-PL-V057A 4.74 4 Main Feedwater Isolation Valve SGS-PL-V057B 4.56 4 Main Feedwater Control Valve SGS-PL-V250A 4.14 4 Main Feedwater Control Valve SGS-PL-V250B 4.20 Attachment G

• Excerpt from COL Appendix C Table 2.2.4-1

• Equipment Name *Tag No. *Active Function Power-operated Relief Valve Block SGS-PL-V027A Transfer Closed Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Transfer Closed Motor-operated Valve Steam Generator 02 Startup Feedwater Isolation SGS-PL-V067A Transfer Closed Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Transfer Closed Motor-operated Valve

U.S. Nuclear Regulatory Commission ND-23-0446 Enclosure Page 13 of 13 Attachment H

• Excerpt from COL Appendix C Table 2.2.4-1

• Equipment Name *Tag No. *Remotely *Loss of Operated Motive Power Valve Position Power-operated Relief Valve Block SGS-PL-V027A Yes As Is Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Yes As Is Motor-operated Valve Steam Generator 02 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes Closed Steam Line Condensate Drain Isolation Valve SGS-PL-V036B Yes Closed Main Steam Line Isolation Valve SGS-PL-V040A Yes As Is Main Steam Line Isolation Valve SGS-PL-V040B Yes As Is Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes Closed Steam Line Condensate Drain Control Valve SGS-PL-V086B Yes Closed Main Feedwater Isolation Valve SGS-PL-V057A Yes As Is Main Feedwater Isolation Valve SGS-PL-V057B Yes As Is Startup Feedwater Isolation SGS-PL-V067A Yes As Is Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Yes As Is Motor-operated Valve Steam Generator Blowdown Isolation Valve SGS-PL-V074A Yes Closed Steam Generator Blowdown Isolation Valve SGS-PL-V074B Yes Closed Steam Generator Blowdown Isolation Valve SGS-PL-V075A Yes Closed Steam Generator Blowdown Isolation Valve SGS-PL-V075B Yes Closed Power-operated Relief Valve SGS-PL-V233A Yes Closed Power-operated Relief Valve SGS-PL-V233B Yes Closed Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Closed Main Steam Isolation Valve Bypass Isolation SGS-PL-V240B Yes Closed Main Feedwater Control Valve SGS-PL-V250A Yes Closed Main Feedwater Control Valve SGS-PL-V250B Yes Closed Startup Feedwater Control Valve SGS-PL-V255A Yes Closed Startup Feedwater Control Valve SGS-PL-V255B Yes Closed