ND-19-0240, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.12a.iii (Index Number 250)

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

ML19086A173
Person / Time
Site:	Vogtle
Issue date:	03/27/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0240
Download: ML19086A173 (19)

Text

^Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tet MAR 2 7 2019 Docket Nos.: 52-025 52-026 ND-19-0240 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.04.12a.iii flndex Number 2501 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 20, 2019, Vogtle 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.

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)(3) 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.

U.S. Nuclear Regulatory Commission ND-19-0240 Page 2 of 4 Respectfully submitted, Michael J. Yox Regulatory Affairs Dfrector Vogtle 3 & 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-19-0240 Page 3of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost(w/o enclosures)

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

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

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

Mr. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman 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 Ms. J. M. Heisserer 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. I. Cozens Mr. J. Gaslevic Mr. V. Hall Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipai Eiectric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-19-0240 Page 4 of 4 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan 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. Kemlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 1 of 15 Southern Nuclear Operating Company ND-19-0240 Enclosure Vogtle Electric Generating Riant(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-19-0240 Enclosure Page 2of 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/Tests/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-19-0240 Enclosure Page 3of 15 Controls in the 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 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 ill) 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 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 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 and Attachment F)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 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.

i1 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-RMS-ITRR-523, 4-RMS-ITRR-523(References 1 and 2), 3-RMS-ITRR-504, 4-RMS-ITRR-504 (References 11 and 12), 3-TOS-ITRR-501, 4-TOS-ITRR-501 (References 13 and 14), and 3-RMS-ITRR-521, 4-RMS-ITRR-521 (References 15 and 16)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, 2,15, and 16 is done to verify the valves in Attachment A close after a signal is generated by the RMS. Testing in reference 1 and 2 is performed by verifying the Moisture Separator Reheater 2nd Stage Steam Supply Isolation Valves(MSS-RL-V015A/B) are open. A High-2 containment pressure signal is simulated on 2 containment pressure instruments, the High-2 Containment Rressure Actuation signal is verified, and MSS-RL-V015A/B are locally verified to close.

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 4 of 15 Testing Is performed in accordance with references 15 and 16 by verifying the Turbine Bypass Control Valves(MSS-PL-V001 through V006) are open. A low Tave signal is generated in the PMS system and the Turbine Bypass Control Valves are locally verified to close. This testing confirms that the valves in Attachment A close after a signal is generated by the PMS.

Testing in references 11, 12,13, and 14 is done in 2 parts to verify the valves in Attachment B close after a signal is generated by the PMS. Testing is performed in accordance with references 13 and 14 to perform a trip solenoid valve functional test by verifying that when the master trip pilot solenoids(TOS-V174A1/A2, TOS-V174B1/B2)are de-energized, the spool moves to the tripped position and the main turbine stop and control valves close. Testing is performed in accordance with references 11 and 12 to verify the master trip pilot solenoids de-energize due to opening the Passive Residual Heat Removal(PRHR) heat exchanger outlet valve resulting in a signal from PMS to the reactor trip logic, causing a reactor trip and subsequent main turbine-generator trip signal. This testing confirms that the Unit 3 and Unit 4 valves In Attachment B close after a signal Is generated by the PMS.

The combination of these tests verifies the valves identified in Table 2.2.4-3 close after a signal is generated by the PMS.

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 SNCXXXXXX and SNCYYYYYY (References 3 and 4)to verify that the safety-related displays identified in Attachment C can be retrieved in the MGR.

The component test is conducted at the MCR PMS Visual Display Units(VDUs)and verifies the safety-related displays In Attachment 0 can be retrieved in the MCR. Each valve and indication listed in Attachment0 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 MCR.

Controls in the MCR operate to cause the remotelv operated valves to perform active safetv functions.

The testing is performed in accordance with Unit 3 and Unit 4 component test procedures SNCXXXXXX and SNCYYYYYY (References 3 and 4)to verify that controls in the MCR 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 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 are locally verified and also verified in the MCR. This confirms that controls in Unit 3 and Unit 4 MCR operate to cause the remotely operated valves to perform active safety functions.

i) The remotelv-operated valves identified in Table 2.2.4-1 as having PMS control oerform the active function Identified in the table after receivlnc a sional from the PMS.

Testing Is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3-PMS-ITPP-523 and 4-PMS-ITPP-523(References 1 and 2)and 3-PMS-ITPP-524 and 4-PMS-ITPP-524(References 5 and 6)to confirm the remotely-operated valves identified in

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 5 of 15 Attacfiment E and Attachment F as having RMS control perform the active function identified in the table after receiving a signal from the PMS.

The testing is performed in accordance with references 1 and 2 and ensures the valves listed in Attachment E are Open. A High-2 containment pressure signal is simulated on 2 containment pressure instruments, the High-2 Containment Pressure Actuation signal is verified, and the valves in Attachment E are locally verified to transfer closed. This testing verifies the valves in Attachment E transfer closed.

Testing is performed in accordance with references 5 and 6 and ensures the feedwater valves listed in Attachment F are Open. A manual Feedwater Isolation signal is generated, the Feedwater Isolation Actuation signal is verified, and the feedwater isolation valves are locally verified to transfer closed. Then the steam generator relief valves listed in Attachment F are opened, a manual Steam Generator Relief Isolation is actuated, the Steam Generator Relief Actuation signal is verified, and the steam generator relief valves are locally verified to transfer closed. This testing verifies the valves in Attachment F transfer closed.

The combination of these tests confirms 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 and Unit 4.

iil These valves close within the followino times after receipt of an actuation sional:

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 preoperational test procedures 3-PMS-ITPP-523 and 4-PMS-ITPP-523(References 1 and 2)and 3-PMS-ITPP-524 and 4-PMS-ITPP-524(References 5 and 6)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.

Testing is performed in accordance with references 1 and 2 and begins by ensuring a trend is established to measure valve stroke time for V040A/B and V057A/B. These valves are verified to be Open, a High-2 containment pressure signal is simulated on 2 containment pressure instruments, the High-2 Containment Pressure Actuation signal is verified, and V040A/B and V057A/B are locally verified to close. The valve closure time is retrieved from the trend data and shows that Unit 3 SGS-PL-V040A closes in X sec, SGS-PL-V040B closes in Y sec, SGS-PL-V057A closes in X sec, and SGS-PL-V057B closes in Y sec. The valve closure time for Unit 4 shows that SGS-PL-V040A closes in X sec, SGS-PL-V040B closes in Y sec, SGS-PL-V057A closes in X sec, and SGS-PL-V057B closes in Y sec.

The testing performed by references 5 and 6 begins by ensuring a trend is established to measure valve stroke time for V250A/B. V250A and V250B are verified to be Open, a manual Feedwater Isolation signal is initiated, the Feedwater Isolation Actuation signal is verified, and V250A and V250B are locally verified to close.

In accordance with references 5 and 6 a trend is established to measure valve stroke time for V027A/B, both valves are verified to be Open, and a manual Steam Generator Relief Isolation is actuated. The Steam Generator Relief Actuation signal is verified, and V027A and V027B are

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page6 of 15 locally verified to close. The valve closure time Is retrieved from the trend data and shows that Unit 3 SGS-PL-V027A closes In X sec, SGS-PL-V027B closes In Y sec, SGS-PL-250A closes In X sec, and SGS-PL-250B closes In Y sec. The valve closure time for Unit 4 shows that SGS-PL-V027A closes In X sec, SGS-PL-V027B closes In Y sec, SGS-PL-V250A closes In X sec, and SGS-PL-V250B closes In Y sec.

The combination of these tests confirm 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-ooerated valve chances position as Indicated In Table 2.2.4-1 under preoperatlonal test conditions.

Testing Is performed In accordance with Unit 3 and Unit 4 preoperatlonal test procedures 3-SGS-ITPP-502 and 4-SGS-ITPP-502(References 7 and 8)to verify each motor-operated valve changes position as Indicated In Attachment G under preoperatlonal 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 preoperatlonal testing. The steam generator power operated relief valve Is opened from the MGR,and SGS-PL-V027A (Power-operated Relief Valve Block MOV Steam Generator 01) Is closed and locally verified to be closed. This testing Is repeated for SGS-PL-V027B (Power-operated Relief Valve Block MOV Steam Generator 02).

Startup feedwater flow Is verified to be 200 gpm or greater, and SGS-PL-067A (Startup Feedwater Isolation MOV)Is closed and locally verified to be closed. This testing Is repeated for SGS-PL-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 preoperatlonal test conditions.

After loss of motive power, each remotelv ooerated valve Identified In Table 2.2.4-1 assumes the Indicated loss of motive power position. Motive oower to SGS-PL-V040A/B and SGS-PL-V057A/B Is electric oower to the actuator from plant services.

Testing Is performed In accordance with Unit 3 and Unit 4 component test procedures SNG922110 and SNGXXXXXX (References 9 and 10)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 fall 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 fall 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 fall to their loss of motive power position (As-ls).

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 7 of 15 The test results verify that 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 16) are available for NRG inspection as part of Unit 3 and Unit 4 ITAAC Completion Packages(References 17 and 18).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company(SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References(available for NRG inspection)

1. 3-PMS-ITPP-523,"Containment Pressure High-2 Actuation Preoperational Test Procedure"

2. 4-PMS-ITPP-523,"Containment Pressure High-2 Actuation Preoperational Test Procedure"

3. SNCXXXXXX,"SGS Remotely Operated Valve Stroke Test- ITAAC: SV3-2.2.04.12a.iii, Item 11a and 10"

4. SNCYYYYYY,"SGS Remotely Operated Valve Stroke Test- ITAAC: SV4-2.2.04.12a.iii, Item 11a and 10"

5. 3-PMS-ITPP-524,"PMS Cold Actuations Preoperational Test Procedure"

6. 4-PMS-ITPP-524,"PMS Cold Actuations Preoperational Test Procedure"

7. 3-SGS-ITPP-502,"Steam Generator System Hot Functional Preoperational Test Procedure"

8. 4-SGS-ITPP-502,"Steam Generator System Hot Functional Preoperational Test Procedure"

9. SNC922110,"SGS Remotely Operated Valve Loss of Motive Power Test- ITAAC: SV3-2.2.04.12a.iii, Item 12b"

10. SNCXXXXXX,"SGS Remotely Operated Valve Loss of Motive Power Test- ITAAC: SV4-2.2.04.12a.iii, Item 12b"

11. 3-PMS-ITPP-504,"PMS REACTOR TRIP BREAKERS"

12. 4-PMS-ITPP-504,"PMS REACTOR TRIP BREAKERS"

13. 3-TOS-ITPP-501,"Main Turbine Control and Diagnostics System Preoperational Test Procedure" 14.4-TOS-ITPP-501,"Main Turbine Control and Diagnostics System Preoperational Test Procedure"

15. 3-PMS-ITPP-521,"Protection and Safety Monitoring System Logic Test Preoperational Test Procedure" 16.4-PMS-ITPP-521,"Protection and Safety Monitoring System Logic Test Preoperational Test Procedure" 17.2.2.04.12a.iii-U3-CP-RevO, ITAAC Completion Package 18.2.2.04.12a.iii-U4-CP-Rev 0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 8 of 15 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-19-0240 Enclosure Page 9 of 15 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 Posit on)

Motor-operated Valve Steam Generator 01 Power-operated Relief Valve Block SGS-PL-V027S Yes(Valve Posit on)

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

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

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

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

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

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

Main Feedwater Isolation Valve SGS-PL-V057A Yes(Valve Posit on)

Main Feedwater Isolation Valve SGS-PL-V057S Yes(Valve Posit on)

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

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

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

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

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

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

Power-operated Relief Valve SGS-PL-V233A Yes(Valve Posit on)

Power-operated Relief Valve SGS-PL-V233S Yes(Valve Posit on)

Main Steam Isolation Valve Svpass Isolation SGS-PL-V240A Yes(Valve Posit on)

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

Main Feedwater Control Valve SGS-PL-V250A Yes(Valve Posit on)

Main Feedwater Control Valve SGS-PL-V250S Yes(Valve Posit on)

Startup Feedwater Control Valve SGS-PL-V255A Yes(Valve Posit on)

Startup Feedwater Control Valve SGS-PL-V255S Yes(Valve Posit on)

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

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 10 of 15 Attachment0(con't)

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

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 11 of 15 Attachment D Excerpt from COL Appendix C Table 2.2.4-1 Equipment Name Tag No. Remotely Active Operated Function Valve Power-operated Relief Valve Block SGS-PL-V027A Yes Transfer Motor-operated Valve Steam Closed Generator 01 Power-operated Relief Valve Block SGS-PL-V027S Yes Transfer Motor-operated Valve Steam Closed Generator 02 Steam Line Condensate Drain SGS-PL-V036A Yes Transfer Isolation Valve Closed Steam Line Condensate Drain SGS-PL-V036S Yes Transfer Isolation Valve 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 SGS-PL-V086A Yes Transfer Valve Closed Steam Line Condensate Drain Control SGS-PL-V086S Yes Transfer Valve Closed Main Feedwater Isolation Valve SGS-PL-V057A Yes Transfer Closed Main Feedwater Isoiation Valve SGS-PL-V057S Yes Transfer Closed Startup Feedwater Isolation Motor- SGS-PL-V067A Yes Transfer operated Closed Valve Startup Feedwater Isolation Motor- SGS-PL-V067S Yes Transfer operated Closed Valve Steam Generator Slowdown Isolation SGS-PL-V074A Yes Transfer Valve Closed Steam Generator Slowdown Isolation SGS-PL-V074S Yes Transfer Valve Closed Steam Generator Slowdown Isolation SGS-PL-V075A Yes Transfer Valve Closed Steam Generator Slowdown Isolation SGS-PL-V075S Yes Transfer Valve 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 SGS-PL-V240A Yes Transfer Isolation Closed

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 12 of 15 Attachment D (con't)

Equipment Name Tag No. Remotely Active Operated Function Valve Main Steam Isolation Valve Bypass SGS-PL-V240B Yes Transfer Isolation 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 Control Active Operated RMS Function Valve Steam Line Condensate Drain SGS-PL-V036A Yes Yes Transfer Isolation Valve Closed Steam Line Condensate Drain SGS-PL-V036S Yes Yes Transfer Isolation Valve Closed Main Steam Line Isolation SGS-PL-V040A Yes Yes Transfer Valve Closed Main Steam Line Isolation SGS-PL-V040S Yes Yes Transfer Valve Closed Steam Line Condensate Drain SGS-PL-V086A Yes Yes Transfer Control Valve Closed Steam Line Condensate Drain SGS-PL-V086S Yes Yes Transfer Control Valve Closed Main Feedwater Isolation Valve SGS-PL-V057A Yes Yes Transfer Closed Main Feedwater Isolation Valve SGS-PL-V057S Yes Yes Transfer Closed Steam Generator Slowdown SGS-PL-V074A Yes Yes Transfer Isolation Valve Closed Steam Generator Slowdown SGS-PL-V074S Yes Yes Transfer Isolation Valve Closed Steam Generator Slowdown SGS-PL-V075A Yes Yes Transfer Isolation Valve Closed

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 13 of 15 Attachment E (con't)

Equipment Name Tag No. Remotely Control Active Operated RMS Function Valve Steam Generator Slowdown SGS-PL-V075B Yes Yes Transfer Isolation Valve Closed Main Steam Isolation Valve SGS-PL-V240A Yes Yes Transfer Bypass Isolation Closed Main Steam Isolation Valve SGS-PL-V240B Yes Yes Transfer Bypass Isolation Startup Feedwater Control SGS-PL-V255A Yes Yes Transfer Valve Closed Startup Feedwater Control SGS-PL-V255B Yes Yes Transfer Valve Closed Attachment F Excerpt from COL Appendix C Table 2.2,4-1 Equipment Name Tag No. Remotely Control Active Operated RMS Function Valve Power-operated Relief Valve SGS-PL-V027A Yes Yes Transfer Block Closed Motor-operated Valve Steam Generator 01 Power-operated Relief Valve SGS-PL-V027B Yes Yes Transfer Block Closed Motor-operated Valve Steam Generator 02 Startup Feedwater Isolation SGS-PL-V067A Yes Yes Transfer Motor-operated Closed Valve Startup Feedwater Isolation SGS-PL-V067B Yes Yes Transfer Motor-operated Closed 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 Startup Feedwater Control SGS-PL-V255A Yes Yes Transfer Valve Closed Startup Feedwater Control SGS-PL-V255B Yes Yes Transfer Valve Closed

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 14 of 15 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 Motor-operated Valve Steam Generator 01 Closed Power-operated Relief Valve Block SGS-PL-V027B Transfer Motor-operated Valve Steam Generator 02 Closed Startup Feedwater Isolation Motor-operated SGS-PL-V067A Transfer Valve Closed Startup Feedwater Isolation Motor-operated SGS-PL-V067B Transfer Valve Closed Attachment H Excerpt from COL Appendix C Table 2.2.4-1 Equipment Name Tag No. Remotely Loss of Operated Motive Vaive Power 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 SGS-PL-V036A Yes Closed Isolation Valve Steam Line Condensate Drain SGS-PL-V036B Yes Closed Isolation Valve 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 SGS-PL-V086A Yes Closed Valve Steam Line Condensate Drain Control SGS-PL-V086B Yes Closed Valve 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

U.S. Nuclear Regulatory Commission ND-19-0240 Enclosure Page 15 of 15 Attachment H (con't)

Equipment Name Tag No. Remotely Loss of Operated Motive Valve Power Position 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 Sypass SGS-PL-V240A Yes Closed Isolation Main Steam Isolation Valve Sypass 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