ND-22-0341, ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250)

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ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250)
ML22126A195
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 05/06/2022
From: Coleman J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.2.04.12a, ND-22-0341
Download: ML22126A195 (17)
v • d • e


Text

>- Southern Nuclear Docket No.:

52-025 MAY O 6 2022 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-22-0341 10 CFR 52.99(c)(1)

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 3 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.

Respectfully submitted, 9J WM \\1 M ylAAfr Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

JMC/RLB/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC'2.2.04.12a.iii (Index Number 250]

U.S. Nuclear Regulatory Commission ND-22-0341 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena Ill Mr. D. L. McKinney Mr. H. Nieh Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. J. 8. Williams Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beilke Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil Mr. C. P. Patel Mr. G. J. Khouri Mr. C. J. Even Mr. 8. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. 0. Lopez-Santiago Mr. G. Armstrong Mr. M. Webb Mr. T. Fredette Mr. C. Santos Mr. 8. Davis Mr. J. Vasquez Mr. J. Eargle Ms. K. Mccurry Mr. J. Parent Mr. B. Griman Mr. V. Hall

U.S. Nuclear Regulatory Commission ND-22-0341 Page 3 of 3 Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani Mr. D. C. Durham Mr. M. M. Corletti Mr. Z. S. Harper Ms. S. L. Zwack Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

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

Mr. S. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 1 of 14 Southern Nuclear Operating Company ND-22-0341 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.04.12a.iii [Index Number 250]

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 2 of 14 IT AAC 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-V027 NB, V040NB, V057 NB, V250NB 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-22-0341 Enclosure Page 3 of 14 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:

V027 NB

< 44 sec V040NB, V057NB < 5 sec V250NB

< 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-V040NB and SGS-PL-V057 NB 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 SV3-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 locally. 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-22-0341 Enclosure Page 4 of 14 The combination of these tests for Unit 3 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 SV3-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 3 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 SV3-SGS-ITR-805250 (Reference 3) 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 work station in the Unit 3 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 3 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 SV3-SGS-ITR-802250 (Reference 4) 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 4 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 4 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 3.

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

V027 NB

< 44 sec V040NB, V057 NB < 5 sec V250NB

< 5 sec

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 5 of 14 Testing was performed as described in Reference 4 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 4. 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: V027 A/B < 44 sec; V040A/B, V057 A/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 SV3-SGS-ITR-803250 (Reference 5) 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-V027 A (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-V067 A (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 3 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-V057 A/B is electric power to the actuator from plant services.

Testing was performed as described in ITAAC Technical Report SV3-SGS-ITR-804250 (Reference 6) 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-V057 A/B is electric power to the actuator from plant services (plant electrical power to the operating solenoids).

Reference 6 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-22-0341 Enclosure Page 6 of 14 the fully Open position was reached. This loss of power caused by the valve control circuit demonstrated the MOV failed "As-ls" (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-ls" (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-ls). 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-ls).

The test results verified for Unit 3 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-V057 A/8 is electric power to the actuator from plant services.

The completed test results (References 1 through 6) are available for NRC inspection as part of the Unit 3 ITAAC 2.2.04.12a.iii Completion Package (Reference 7).

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 7) 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 3 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. SV3-SGS-ITR-800250, Unit 3 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 9.a) NRC Index Number: 250, Rev 1
2. SV3-SGS-ITR-801250, Unit 3 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 10 NRC Index Number: 250, Rev. 1
3. SV3-SGS-ITR-805250, Unit 3 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 11.a) NRC Index Number: 250, Rev. 1
4. SV3-SGS-ITR-802250, Unit 3 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 11.b) NRC Index Number: 250, Rev. 1
5. SV3-SGS-ITR-803250, Unit 3 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 12.a) NRC Index Number: 250, Rev. 1

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 7 of 14

6. SV3-SGS-ITR-804250, Unit 3 Recorded Results of Steam Generator System: ITAAC 2.2.04.12a.iii Item 12.b) NRC Index Number: 250, Rev. 0
7. 2.2.04.12a.iii-U3-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 8 of 14 Attachment A

  • Excerpt from COL Appendix C Table 2.2.4-3
  • Equipment Name
  • Tag No.

Turbine Bypass Control Valve MSS-PL-V001 Turbine Bypass Control Valve MSS-PL-V002 Turbine Bypass Control Valve MSS-PL-V003 Turbine Bypass Control Valve MSS-PL-V004 Turbine Bypass Control Valve MSS-PL-V005 Turbine Bypass Control Valve MSS-PL-V006 Moisture Separator Reheater 2nd Stage Steam MSS-PL-V015A Isolation Valve Moisture Separator Reheater 2nd Stage Steam MSS-PL-V015B Isolation Valve Attachment B

  • Excerpt from COL Appendix C Table 2.2.4-3
  • Equipment Name
  • Tag No.

Turbine Stop Valve MTS-PL-V001A Turbine Stop Valve MTS-PL-V001 B Turbine Control Valve MTS-PL-V002A Turbine Control Valve MTS-PL-V002B Turbine Stop Valve MTS-PL-V003A Turbine Stop Valve MTS-PL-V003B Turbine Control Valve MTS-PL-V004A Turbine Control Valve MTS-PL-V004B

  • Control Function Close Close Close Close Close Close Close Close
  • Control Function Close Close Close Close Close Close Close Close

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 9 of 14 Attachment C

  • Excerpt from COL Appendix C Table 2.2.4-1
  • Equipment Name
  • Tag No.

Power-operated Relief Valve Block SGS-PL-V027 A Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Motor-operated Valve Steam Generator 02 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Steam Line Condensate Drain Isolation Valve SGS-PL-V0368 Main Steam Line Isolation Valve SGS-PL-V040A Main Steam Line Isolation Valve SGS-PL-V0408 Steam Line Condensate Drain Control Valve SGS-PL-V086A Steam Line Condensate Drain Control Valve SGS-PL-V086B Main Feedwater Isolation Valve SGS-PL-V057 A Main Feedwater Isolation Valve SGS-PL-V0578 Startup Feedwater Isolation SGS-PL-V067 A Motor-operated Valve Startup Feedwater Isolation SGS-PL-V0678 Motor-operated Valve Steam Generator Slowdown Isolation Valve SGS-PL-VO? 4A Steam Generator Slowdown Isolation Valve SGS-PL-VO? 48 Steam Generator Slowdown Isolation Valve SGS-PL-V075A Steam Generator Slowdown Isolation Valve SGS-PL-V0758 Power-operated Relief Valve SGS-PL-V233A Power-operated Relief Valve SGS-PL-V2338 Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Main Steam Isolation Valve Bypass Isolation SGS-PL-V2408 Main Feedwater Control Valve SGS-PL-V250A Main Feedwater Control Valve SGS-PL-V250B Startup Feedwater Control Valve SGS-PL-V255A Startup Feedwater Control Valve SGS-PL-V255B Steam Generator 1 Narrow Ranoe Level Sensor SGS-001 Steam Generator 1 Narrow Ranoe Level Sensor SGS-002 Steam Generator 1 Narrow Range Level Sensor SGS-003 Steam Generator 1 Narrow Ranqe Level Sensor SGS-004 Steam Generator 2 Narrow Ranae Level Sensor SGS-005 Steam Generator 2 Narrow Ranqe Level Sensor SGS-006

  • Safety-Related Disolay Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes <Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes (Valve Position)

Yes Yes Yes Yes Yes Yes

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 10 of 14 Attachment C (con't)

  • Tag No.
  • Safety-Related Display SGS-007 Yes SGS-008 Yes SGS-011 Yes SGS-012 Yes SGS-013 Yes SGS-014 Yes SGS-015 Yes SGS-016 Yes SGS-017 Yes SGS-018 Yes SGS-030 Yes SGS-031 Yes SGS-032 Yes SGS-033 Yes SGS-034 Yes SGS-035 Yes SGS-036 Yes SGS-037 Yes SGS-55A Yes SGS-55B Yes SGS-56A Yes SGS-56B Yes

U.S. Nuclear Regulatory Commission N D-22-0341 Enclosure Page 11 of 14 Attachment D

  • Excerpt from COL Appendix C Table 2.2.4-1
  • Equipment Name
  • Tag No.
  • Remotely Operated Valve Power-operated Relief Valve Block SGS-PL-V027 A Yes Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Yes Motor-operated Valve Steam Generator 02 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes Steam Line Condensate Drain Isolation Valve SGS-PL-V0368 Yes Main Steam Line Isolation Valve SGS-PL-V040A Yes Main Steam Line Isolation Valve SGS-PL-V0408 Yes Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes Steam Line Condensate Drain Control Valve SGS-PL-V0868 Yes Main Feedwater Isolation Valve SGS-PL-V057 A Yes Main Feedwater Isolation Valve SGS-PL-V0578 Yes Startup Feedwater Isolation SGS-PL-V067 A Yes Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Yes Motor-operated Valve Steam Generator Slowdown Isolation Valve SGS-PL-V074A Yes Steam Generator Slowdown Isolation Valve SGS-PL-VO? 48 Yes Steam Generator Slowdown Isolation Valve SGS-PL-V075A Yes Steam Generator Slowdown Isolation Valve SGS-PL-V075B Yes Power-operated Relief Valve SGS-PL-V233A Yes Power-operated Relief Valve SGS-PL-V233B Yes Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Main Steam Isolation Valve Bypass Isolation SGS-PL-V2408 Yes Main Feedwater Control Valve SGS-PL-V250A Yes Main Feedwater Control Valve SGS-PL-V2508 Yes Startup Feedwater Control Valve SGS-PL-V255A Yes Startup Feedwater Control Valve SGS-PL-V255B Yes
  • Active Function Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 12 of 14 Attachment E

  • Excerpt from COL Appendix C Table 2.2.4-1
  • Equipment Name
  • Tag No.
  • Remotely
  • Control Operated PMS Valve Steam Line Condensate Drain SGS-PL-V036A Yes Yes Isolation Valve Steam Line Condensate Drain SGS-PL-V036B Yes Yes Isolation Valve Main Steam Line Isolation Valve SGS-PL-V040A Yes Yes Main Steam Line Isolation Valve SGS-PL-V040B Yes Yes Steam Line Condensate Drain SGS-PL-V086A Yes Yes Control Valve Steam Line Condensate Drain SGS-PL-V086B Yes Yes Control Valve Main Feedwater Isolation Valve SGS-PL-VOS? A Yes Yes Main Feedwater Isolation Valve SGS-PL-V057B Yes Yes Steam Generator Slowdown SGS-PL-V074A Yes Yes Isolation Valve Steam Generator Slowdown SGS-PL-V074B Yes Yes Isolation Valve Steam Generator Slowdown SGS-PL-V075A Yes Yes Isolation Valve Steam Generator Slowdown SGS-PL-VO? 5B Yes Yes Isolation Valve Main Steam Isolation Valve SGS-PL-V240A Yes Yes Bypass Isolation Main Steam Isolation Valve SGS-PL-V240B Yes Yes Bypass Isolation Startup Feedwater Control Valve SGS-PL-V255A Yes Yes Startup Feedwater Control Valve SGS-PL-V255B Yes Yes Power-operated Relief Valve Block SGS-PL-V027A Yes Yes Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Yes Yes Motor-operated Valve Steam Generator 02 Startup Feedwater Isolation SGS-PL-V067 A Yes Yes Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Yes Yes Motor-operated Valve Power-operated Relief Valve SGS-PL-V233A Yes Yes Power-operated Relief Valve SGS-PL-V233B Yes Yes Main Feedwater Control Valve SGS-PL-V250A Yes Yes Main Feedwater Control Valve SGS-PL-V250B Yes Yes
  • Active Function Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed Transfer Closed

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 13 of 14 Attachment F

  • Excerpt from COL Appendix C Table 2.2.4-1 Unit
  • Equipment Name
  • Tag No.

3 Power-operated Relief Valve Block SGS-PL-V027A Motor-operated Valve Steam Generator 01 3

Power-operated Relief Valve Block SGS-PL-V027B Motor-operated Valve Steam Generator 02 3

Main Steam Line Isolation Valve SGS-PL-V040A 3

Main Steam Line Isolation Valve SGS-PL-V040B 3

Main Feedwater Isolation Valve SGS-PL-V057 A 3

Main Feedwater Isolation Valve SGS-PL-V057B 3

Main Feedwater Control Valve SGS-PL-V250A 3

Main Feedwater Control Valve SGS-PL-V250B Attachment G

  • Excerpt from COL Appendix C Table 2.2.4-1
  • Equipment Name
  • Tag No.

Power-operated Relief Valve Block SGS-PL-V027 A Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027B Motor-operated Valve Steam Generator 02 Startup Feedwater Isolation SGS-PL-V067 A Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067B Motor-operated Valve Closure time (Sec) 21.84 23.84 4.231 4.604 4.357 4.350 4.149 3.943

  • Active Function Transfer Closed Transfer Closed Transfer Closed Transfer Closed

U.S. Nuclear Regulatory Commission ND-22-0341 Enclosure Page 14 of 14 Attachment H

  • Excerpt from COL Appendix C Table 2.2.4-1
  • Equipment Name
  • Tag No.
  • Remotely Operated Valve Power-operated Relief Valve Block SGS-PL-V027 A Yes Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V0278 Yes Motor-operated Valve Steam Generator 02 Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes Steam Line Condensate Drain Isolation Valve SGS-PL-V036B Yes Main Steam Line Isolation Valve SGS-PL-V040A Yes Main Steam Line Isolation Valve SGS-PL-V0408 Yes Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes Steam Line Condensate Drain Control Valve SGS-PL-V0868 Yes Main Feedwater Isolation Valve SGS-PL-V057 A Yes Main Feedwater Isolation Valve SGS-PL-V057B Yes Startup Feedwater Isolation SGS-PL-V067A Yes Motor-operated Valve Startup Feedwater Isolation SGS-PL-V0678 Yes Motor-operated Valve Steam Generator Slowdown Isolation Valve SGS-PL-V074A Yes Steam Generator Slowdown Isolation Valve SGS-PL-V074B Yes Steam Generator Slowdown Isolation Valve SGS-PL-V075A Yes Steam Generator Slowdown Isolation Valve SGS-PL-V0758 Yes Power-operated Relief Valve SGS-PL-V233A Yes Power-operated Relief Valve SGS-PL-V2338 Yes Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Main Steam Isolation Valve Bypass Isolation SGS-PL-V2408 Yes Main Feedwater Control Valve SGS-PL-V250A Yes Main Feedwater Control Valve SGS-PL-V250B Yes Startup Feedwater Control Valve SGS-PL-V255A Yes Startup Feedwater Control Valve SGS-PL-V2558 Yes
  • Loss of Motive Power Position As Is As Is Closed Closed As Is As Is Closed Closed As Is As Is As Is As Is Closed Closed Closed Closed Closed Closed Closed Closed Closed Closed Closed Closed
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