ND-19-0950, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.12a.iii (Index Number 250)

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Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.12a.iii (Index Number 250)
ML19221B718
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/09/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-19-0950
Download: ML19221B718 (19)
v • d • e


Text

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Southern Nuclear AUG 0 9 2019 Docket Nos.: 52-025 52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tei ND-19-0950 10CFR 52.99(c)(3)

Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.04.12a.iii [Index Number 2501 Ladies and Gentlemen; Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of August 1, 2019, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.2.04.12a.iii

[Index Number 250] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.04.12a.iii [Index Number 250]. 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.

Southern Nuclear Operating Company (SNC) previously submitted Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load for Item 2.2.04.12a.ill [Index Number 250] ND-19-0240

[ML19086A173], dated Mar. 27, 2019. This resubmittal supersedes ND-19-0240 in its entirety.

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. Yox Regulatory Affairs Director Vogtie 3 & 4

U.S. Nuclear Regulatory Commission ND-19-0950 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.12a.iii [Index Number 250]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0950 Page 3 of 4 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. 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 Reouiatorv 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 Qqlethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0950 Page 4 of 4 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., GDS Associates, Inc.

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

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 1 of 15 Southern Nuclear Operating Company ND-19-0950 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.12a.iii [Index Number 250]

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 2 of 15 ITAAC Statement Desion 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-I to perform active functions.

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

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.

I nspections/T ests/Analvses 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 RMS.

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 RMS.

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

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 3 of 15 Controls in the MCR operate to cause the remotely operated valves to perform active safety functions.

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

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-RL-V040A/B and SGS-RL-V057A/B is electric power to the actuator from plant services.

ITAAC Completion Description Testing and inspections are 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 (RMS), 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 RMS control perform the active function identified in the table after receiving a real or simulated signal from the RMS. This ITAAC also verifies 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 sional is Generated bv the RMS.

Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-TOS-ITRR-501, 4-TOS-ITRR-501 (References 1 and 2), and Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 3 and 4). These component test packages utilize B-GEN-ITRCI-039 (Reference 5) to direct the performance of test procedures to verify that the valves identified in Attachment A and Attachment B close after a signal is generated by the RMS.

Testing in references 1 and 2 is done to verify the valves in Attachment B close after a signal is generated by the RMS. Testing in reference 1 and 2 is performed by verifying the Main Turbine Stop Valves and Control Valves are open. The RMS reactor trip hand switch is placed to trip and the Main Turbine Stop and Control valves are verified to close locally. This testing confirms that the valves in Attachment B close after a signal is generated by the RMS.

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 4 of 15 Reference 5 directs tfie performance of 3/4-l\\/ITS-OTS-10-001 (References 6 and 7) and verifies the valves in Attachment A are open. A manual RMS Steamiine Actuation signal is generated using a hand switch in the MGR and the valves in Attachment A are verified to close locally.

This testing confirms that the valves in Attachment A close after a signal is generated by the RMS.

The combination of these tests for Unit 3 and Unit 4 verifies the valves identified in Table 2.2.4-3 close after a signal is generated by the RMS.

Safetv-related disolavs identified in Table 2.2.4-1 can be retrieved in the MGR.

The inspection is performed in accordance with Unit 3 and Unit 4 component test procedures SNG922107 and SNGYYYYYY (References 8 and 9) to verify that the safety-related displays identified in Attachment G can be retrieved in the MGR.

The component test is conducted at the MGR RMS Visual Display Units (VDUs) and verifies the safety-related displays in Attachment G can be retrieved in the MGR. Each valve and indication listed in Attachment G is 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 Unit 3 and Unit 4 MGR.

Gontrols in the MGR operate to cause the remotelv operated valves to perform active safetv functions.

Testing is performed in accordance with Unit 3 and Unit 4 component test procedures SNG922107 and SNGYYYYYY (References 8 and 9) to verify that controls in the MGR operate to cause the remotely operated valves in Attachment D to perform active safety functions.

Testing is conducted at an operator work station in Unit 3 and Unit 4 MGR to verify the valves identified in Attachment D as being remotely operated and having active safety functions are stroked open and closed from the MGR. The valve positions are locally verified and verified in the MGR. This confirms that controls in Unit 3 and Unit 4 MGR operate to cause the remotely operated valves to perform active safety functions.

i) The remotelv-ooerated valves identified in Table 2.2.4-1 as havino RMS control oerform the active function identified in the table after receiving a sional from the RMS.

Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNGXXXXXX and SNGYYYYYY (References 3 and 4) to confirm the remotely-operated valves identified in Attachment E as having RMS control perform the active function identified in the table after receiving a signal from the RMS.

Testing is performed in accordance with references 3 and 4 and utilizes B-GEN-ITRGI-039 (Reference 5) to direct the performance of test procedures 3/4-GEN-OTS-10-002 (References 10 and 11), 3/4-GEN-OTS-10-004 (References 12 and 13), 3/4-SGS-OTS-10-003 (References 14 and 15^ and 3/4-SGS-OTS-10-004 (References 16 and 17). The valves listed in Attachment E are verified to be Open and testing is performed by references 10 through 17 utilizing the RMS Maintenance and Test Ranel (MTR) to generate a RMS output signal. The valves in Attachment E are verified to close by MGR indication and locally at the valves when the RMS output signal is generated.

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 5 of 15 The combination of these tests confirm the remotely-operated valves identified in Table 2.2.4-1 as having RMS control perform the active function identified in the table after receiving a signal from the RMS for Unit 3 and Unit 4.

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

V027A/B

<44 sec V040A/B. V057A/B < 5 sec V250A/B

<5 sec Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 3 and 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 is performed in accordance with references 3 and 4 and utilizes B-GEN-ITRCI-039 (Reference 5) to direct the performance of test procedures 3/4-GEN-OTS-10-002 (References 10 and 11), 3/4-GEN-OTS-10-004 (References 12 and 13), 3/4-SGS-OTS-10-003 (References 14 and 15), and 3/4-SGS-OTS-10-004 (References 16 and 17). The valves in Attachment F are verified to be Open, a trend is established to record valve timing information, and testing is performed by references 10 through 17 utilizing the RMS MTR to generate a RMS output signal.

The valves in Attachment F are verified to close, the valve closure time is recorded in the test and valve closure time is summarized in Attachment F.

This testing confirms 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.

ill) Each motor-operated valve chances oosition as indicated in Table 2.2.4-1 under preoperational test conditions.

Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-SGS-ITRR-502 and 4-SGS-ITRR-502 (References 18 and 19) to verify each motor-operated valve changes position as indicated in Attachment G under preoperational test conditions.

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

Startup feedwater flow is verified to be 200 gpm or greater, and SGS-RL-067A (Startup Feedwater Isolation MOV) is closed and locally verified to be closed. This testing is repeated for SGS-RL-V067B (Startup Feedwater Isolation MOV).

The test results verify that for Unit 3 and 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 remotelv operated valve identified in Table 2.2.4-1 assumes the indicated loss of motive power position. Motive power to SGS-RL-V040A/B and SGS-RL-V057A/B is electric power to the actuator from plant services.

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 6 of 15 Testing is performed in accordance with Unit 3 and Unit 4 component test procedures SNC922110 and SNCXXXXXX (References 20 and 21) 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).

The component test configures and documents the air operated valves are in the Open position, removes power to the solenoid valve supplying air to the valve actuators which removes motive power from the valves. The air operated valves are locally verified to fail to their loss of motive power position (closed). The motor-operated valves (MOVs) are configured to the Open position, power is removed from the motor and the valves are verified to fail to their loss of motive power position (As-ls). The hydraulic/pneumatic valves (SGS-PL-V040A/B and SGS-PL-V057A/B) are configured to the Open position, power is removed from the actuator (electrical power to the operating solenoids), and the valves are verified to fail to their loss of motive power position (As-ls).

The test results verify for Unit 3 and 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 21) are available for NRC inspection as part of Unit 3 and Unit 4ITAAC Completion Packages (References 22 and 23).

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 NRC inspection)

1. 3-TOS-ITPP-501, "Main Turbine Control and Diagnostics System Preoperational Test Procedure"
2. 4-TOS-ITPP-501, "Main Turbine Control and Diagnostics System Preoperational Test Procedure"
3. SNCXXXXXX
4. SNCYYYYYY
5. B-GEN-ITPCI-039, "PMS CIM Component Test Procedure"
6. 3-MTS-0TS-10-001, "Main Turbine Inservice Valve Tesf
7. 4-MTS-0TS-10-001, "Main Turbine Inservice Valve Tesf
8. SNC922107, "SGS Remotely Operated Valve Stroke Test -

ITAAC: SV3-2.2.04.12a.iii, Item 11a and 10"

9. SNCYYYYYY, "SGS Remotely Operated Valve Stroke Test -

ITAAC: SV4-2.2.04.12a.iii, Item 11a and 10" 10.3-GEN-0TS-10-002, "Division B Quarterly Valve Stroke Test" 11.4-GEN-0TS-10-002, "Division B Quarterly Valve Stroke Test"

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 7 of 15 12.3-GEN-OTS-10-004, "Division D Quarterly Valve Stroke Tesf 13.4-GEN-OTS-10-004, "Division D Quarterly Valve Stroke Tesf 14.3-SGS-QTS-10-003, "Steam Generating System Valve Stroke Test Train A Modes 3-6" 15.4-SGS-0TS-10-003, "Steam Generating System Valve Stroke Test Train A Modes 3-6"

16. 3-SGS-0TS-10-004, "Steam Generating System Valve Stroke Test Train B Modes 3-6" 17.4-SGS-0TS-10-004, "Steam Generating System Valve Stroke Test Train 8 Modes 3-6" 18.3-SGS-ITPP-502, "Steam Generator System Hot Functional Preoperational Test Procedure" 19.4-SGS-ITPP-502, "Steam Generator System Hot Functional Preoperational Test Procedure"
20. SNC922110, "SGS Remotely Operated Valve Loss of Motive Power Test -

ITAAC: SV3-2.2.04.12a.iii, Item 12b"

21. SNCXXXXXX, "SGS Remotely Operated Valve Loss of Motive Power Test -

ITAAC: SV4-2.2.04.12a.iii, Item 12b" 22.2.2.04.12a.iii-U3-CP-RevO, ITAAC Completion Package 23.2.2.04.12a.iii-U4-CP-RevO, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 8 of 15 Attachment A

'Excerpt from COL Appendix C Table 2.2.4-3

  • Equipment Name
  • Tag No.
  • Controi 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 Isolation Valve MSS-PL-V015A Close Moisture Separator Reheater 2nd Stage Steam Isolation Valve MSS-PL-V015B Close 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-19-0950 Enclosure Page 9 of 15

'Excerpt from COL Appendix C Table 2.2.4-1

  • Equlpment Name
  • Tag No.

'Safety-Related Display Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A Yes (Valve Position)

Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027S Yes (Valve Position)

Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes (Valve Position)

Steam Line Condensate Drain Isolation Valve SGS-PL-V036S Yes (Valve Position)

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

Main Steam Line Isolation Valve SGS-PL-V040S Yes (Valve Position)

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

Steam Line Condensate Drain Control Valve SGS-PL-V086S Yes (Valve Position)

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

Main Feedwater Isolation Valve SGS-PL-V057S Yes (Valve Position)

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

Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067S Yes (Valve Position)

Steam Generator Slowdown Isolation Valve SGS-PL-V074A Yes (Valve Position)

Steam Generator Slowdown Isolation Valve SGS-PL-V074S Yes (Valve Position)

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

Steam Generator Slowdown Isolation Valve SGS-PL-V075S Yes (Valve Position)

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

Power-operated Relief Valve SGS-PL-V233S Yes (Valve Position)

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

Main Steam Isolation Valve Bypass Isolation SGS-PL-V240S Yes (Valve Position)

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

Main Feedwater Control Valve SGS-PL-V250S Yes (Valve Position)

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

Startup Feedwater Control Valve SGS-PL-V255S 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-19-0950 Enclosure Page 10 of 15 (con't)

^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 1 Startup Feedwater Flow Sensor SGS-56A Yes Steam Generator 1 Startup Feedwater Flow Sensor SGS-56B Yes

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 11 of 15 Attachment D

'Excerpt from COL Appendix C Table 2.2.4-1

  • Equipment Name
  • Tag No.
  • Remotely Operated Valve
  • Active Function Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A Yes Transfer Closed Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027S Yes Transfer Closed Steam Line Condensate Drain Isolation Valve SGS-PL-V036A Yes Transfer Closed Steam Line Condensate Drain Isolation Valve SGS-PL-V036S Yes Transfer Closed Main Steam Line Isolation Valve SGS-PL-V040A Yes Transfer Closed Main Steam Line Isolation Valve SGS-PL-V040S Yes Transfer Closed Steam Line Condensate Drain Control Valve SGS-PL-V086A Yes Transfer Closed Steam Line Condensate Drain Control Valve SGS-PL-V086S Yes Transfer Closed Main Feedwater Isolation Valve SGS-PL-V057A Yes Transfer Closed Main Feedwater Isolation Valve SGS-PL-V057S Yes Transfer Closed Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A Yes Transfer Closed Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067S Yes Transfer Closed Steam Generator Slowdown Isolation Valve SGS-PL-V074A Yes Transfer Closed Steam Generator Slowdown Isolation Valve SGS-PL-V074S Yes Transfer Closed Steam Generator Slowdown Isolation Valve SGS-PL-V075A Yes Transfer Closed Steam Generator Slowdown Isolation Valve SGS-PL-V075S Yes Transfer Closed Power-operated Relief Valve SGS-PL-V233A Yes Transfer Closed Power-operated Relief Valve SGS-PL-V233S Yes Transfer Closed Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Transfer Closed

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 12 of 15 Attachment D (con't)

^Equipment Name

  • Tag No.

^Remotely Operated Valve

  • Active Function 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 Attachment E "Excerpt from COL Appendix C Table 2.2.4-1 "Equipment Name "Tag No.

"Remotely Operated Valve "Control RMS "Active Function Steam Line Condensate SGS-PL-Yes Yes Transfer Drain Isolation Valve V036A Closed Steam Line Condensate SGS-PL-Yes Yes Transfer Drain Isolation Valve V036S Closed Main Steam Line Isolation SGS-PL-Yes Yes Transfer Valve V040A Closed Main Steam Line Isolation SGS-PL-Yes Yes Transfer Valve V040S Closed Steam Line Condensate SGS-PL-Yes Yes Transfer Drain Control Valve V086A Closed Steam Line Condensate SGS-PL-Yes Yes Transfer Drain Control Valve V086S Closed Main Feedwater Isolation SGS-PL-Yes Yes Transfer Valve V057A Closed Main Feedwater Isolation SGS-PL-Yes Yes Transfer Valve V057S Closed Steam Generator SGS-PL-Yes Yes Transfer Slowdown Isolation Valve V074A Closed Steam Generator SGS-PL-Yes Yes Transfer Slowdown Isolation Valve V074S Closed Steam Generator SGS-PL-Yes Yes Transfer Slowdown Isolation Valve V075A Closed

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 13 of 15 Attachment E (con't)

^Equipment Name

  • Tag No.

^Remotely Operated Valve

^Active Function Steam Generator Slowdown Isolation Valve SGS-PL-V075B Yes Yes Transfer Closed Main Steam Isolation Valve Bypass Isolation SGS-PL-V240A Yes Yes Transfer Closed Main Steam Isolation Valve Bypass Isolation SGS-PL-V240B Yes Yes Transfer 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 Motor-operated Valve Steam Generator 01 SGS-PL-V027A Yes Yes Transfer Closed Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B Yes Yes Transfer Closed Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A Yes Yes Transfer Closed Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067B Yes Yes Transfer Closed 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-19-0950 Enclosure Page 14 of 15 Attachment F

'Excerpt from COL Appendix C Table 2.2.4-1 Unit

^Equipment Name

  • Tag No.

^Closure time (Sec) 3 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A XX 3

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

Main Steam Line Isolation Valve SGS-PL-V040A X

3 Main Steam Line Isolation Valve SGS-PL-V040B X

3 Main Feedwater Isolation Valve SGS-PL-V057A X

3 Main Feedwater Isolation Valve SGS-PL-V057B X

3 Main Feedwater Control Valve SGS-PL-V250A X

3 Main Feedwater Control Valve SGS-PL-V250B X

4 Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A XX 4

Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B XX 4

Main Steam Line Isolation Valve SGS-PL-V040A X

4 Main Steam Line Isolation Valve SGS-PL-V040B X

4 Main Feedwater Isolation Valve SGS-PL-V057A X

4 Main Feedwater Isolation Valve SGS-PL-V057B X

4 Main Feedwater Control Valve SGS-PL-V250A X

4 Main Feedwater Control Valve SGS-PL-V250B X

Attachment G

'Excerpt from COL Appendix C Table 2.2.4-1

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

U.S. Nuclear Regulatory Commission ND-19-0950 Enclosure Page 15 of 15 Attachment H

'Excerpt from COL Appendix C Table 2.2.4-1

^Equipment Name

  • Tag No.
  • Remotely Operated Valve
  • Loss of Motive Power Position Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A Yes As Is Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027S Yes As Is Steam Line Condensate Drain SGS-PL-V036A Yes Closed Isolation Valve Steam Line Condensate Drain SGS-PL-V036S Yes Closed Isolation Valve Main Steam Line Isolation Valve SGS-PL-V040A Yes As Is Main Steam Line Isolation Valve SGS-PL-V040S Yes As Is Steam Line Condensate Drain Control SGS-PL-V086A Yes Closed Valve Steam Line Condensate Drain Control SGS-PL-V086S Yes Closed Valve Main Feedwater Isolation Valve SGS-PL-V057A Yes As Is Main Feedwater Isolation Valve SGS-PL-V057S Yes As Is Startup Feedwater Isolation SGS-PL-V067A Yes As Is Motor-operated Valve Startup Feedwater Isolation SGS-PL-V067S Yes As Is Motor-operated Valve Steam Generator Slowdown Isolation SGS-PL-V074A Yes Closed Valve Steam Generator Slowdown Isolation SGS-PL-V074S Yes Closed Valve Steam Generator Slowdown Isolation SGS-PL-V075A Yes Closed Valve Steam Generator Slowdown Isolation SGS-PL-V075S Yes Closed Valve Power-operated Relief Valve SGS-PL-V233A Yes Closed Power-operated Relief Valve SGS-PL-V233S Yes Closed Main Steam Isolation Valve Bypass SGS-PL-V240A Yes Closed Isolation Main Steam Isolation Valve Bypass SGS-PL-V240S Yes Closed Isolation Main Feedwater Control Valve SGS-PL-V250A Yes Closed Main Feedwater Control Valve SGS-PL-V250S Yes Closed Startup Feedwater Control Valve SGS-PL-V255A Yes Closed Startup Feedwater Control Valve SGS-PL-V255S Yes Closed
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