ND-19-1054, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.10 (Index Number 206)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.10 (Index Number 206)

ML19240B002
Person / Time
Site:	Vogtle
Issue date:	08/28/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-1054
Download: ML19240B002 (15)

Text

^Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel AUG 2 8 2019 Docket Nos.;52-025 52-026 ND-19-1054 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 2.2.03.10 [Index Number 2061 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of August 26, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections Tests Analyses and Acceptance Criteria (ITAAC) Item 2.2.03.10

[Index Number 206] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing ITAAC 2.2.03.10 [Index Number 206]. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by the guidance described in NEI-08-01, Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52, which was endorsed by the NRC in Regulatory Guide 1.215. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed.

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

This letter contains no new NRC regulatory commitments.

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

Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogue 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.10 [Index Number 206]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-1054 Page 2 of 3 To:

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

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

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

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

Mr. G. Chick Mr. M. J. Vox 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 Reaulatorv 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 OalethorDe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1054 Page 3 of 3 MuniclDai Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

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

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

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

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

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 1 of 12 Southern Nuclear Operating Company ND-19-1054 Enclosure Vogtle Electric Generating Plant(VEGP)Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.10[Index Number 206]

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 2 of 12 ITAAC Statement Design Commitment

10. Safety-related displays of the parameters identified in Table 2.2.3-1 can be retrieved in the MCR.

11.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.3-I to perform their active function(s).

II.b) The valves identified in Table 2.2.3-1 as having RMS control perform their active function after receiving a signal from the RMS.

12.b) After loss of motive power, the remotely operated valves identified in Table 2.2.3-1 assume the indicated loss of motive power position.

13. Displays of the parameters identified in Table 2.2.3-3 can be retrieved in the MCR.

I nsoections/Tests/Analvses Inspection will be performed for the retrievability of the safety-related displays in the MCR.

ii) Stroke testing will be performed on remotely operated valves other than squib valves identified in Table 2.2.3-1 using the controls in the MCR.

ii) Testing will be performed on the remotely operated valves other than squib valves identified in Table 2.2.3-1 using real or simulated signals into the RMS.

iii) Testing will be performed to demonstrate that remotely operated RXS isolation valves RXS-V014A/B, V015A/B, V108A/B open within the required response times.

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

Inspection will be performed for retrievability of the displays identified in Table 2.2.3-3 in the MCR.

Acceptance Criteria Safety-related displays identified in Table 2.2.3-1 can be retrieved in the MCR.

ii) Controls in the MCR operate to cause remotely operated valves other than squib valves to perform their active functions.

ii) Remotely operated valves other than squib valves perform the active function identified in the table after a signal is input to the RMS.

iii) These valves open within 20 seconds after receipt of an actuation signal.

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 3 of 12 After loss of motive power, each remotely operated valve identified in Table 2.2.3-1 assumes the indicated loss of motive power position.

Displays identified in Table 2.2.3-3 can be retrieved in the MGR.

ITAAC Completion Description Multiple ITAAC are performed to verify by inspections and tests that:

• Safety-related displays of the parameters identified in the Combined License(COL)

Table 2.2.3-1 (Attachment A)can be retrieved in the Main Control Room (MCR).

• Controls exist in the MCR to cause the remotely operated valves identified in COL Table 2.2.3-1 (Attachment B)to perform their active function(s).

• The valves identified in Table 2.2.3-1 (Attachment C)as having Protection and Safety Monitoring System (PMS)control perform their active function after receiving a signal from the PMS.

• Remotely operated PXS isolation valves PXS-V014A/B, V015A/B, VI08A/B open within the required response times.

• After loss of motive power, the remotely operated valves identified in COL Table 2.2.3-1 (Attachment E)assume the indicated loss of motive power position.

• Displays of the parameters identified in COL Table 2.2.3-3(Attachment F)can be retrieved in the MCR.

Safetv-related disolavs identified in Table 2.2.3-1 can be retrieved in the MCR.

Inspections performed in accordance with the Unit 3 and Unit 4 component test package work orders SNC921612 and SNCYYYYYY (References 1 and 2), visually confirm that when each of the displays of the plant parameter identified in Attachment A is summoned using the MCR PMS Visual Display Units(VDUs), the expected display appears on the PMS VDU.

The completed inspection results confirm that safety-related displays identified in Table 2.2.3-1 can be retrieved in Unit 3 and Unit 4 MCR.

\\) Controls in the MCR operate to cause remotelv ooerated valves other than souib valves to perform their active functions.

Using Plant Control System (PLS)controls in the MCR,stroke testing each valve in Attachment B is performed in accordance with component test package work orders for Unit 3 and Unit 4 SNC921614 and SNCYYYYYY (References 3 and 4). Each valve is stroked to its active function and proper valve position indication is verified locally and in the MCR. This testing demonstrates PLS controls in the MCR operate to cause the remotely operated valves identified in COL Appendix C Table 2.2.3-1 to perform their active functions.

The completed test results(References 3& 4)confirm that controls in Unit 3 and Unit 4 MCR operate to cause the remotely operated valves identified in Table 2.2.3-1 to perform active functions.

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 4 of 12 ii) Remotely operated valves other than souib valves oerform the active function identified in the table after a sional is input to the RMS.

Testing is performed in accordance witfi Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 5 and 6). These component test packages utilize B-GEN-ITPCI-039(Reference 7)to direct the performance of test procedures 3/4-GEN-OTS 001 (References 8 and 9), 3/4-GEN-OTS-10-002(References 10 and 11), 3/4-GEN-OTS 003(References 12 and 13), 3/4-GEN-OTS-10-004(References 14 and 15), and 3/4-PXS-OTS-10-001 (References 16 and 17)to confirm that the remotely operated valves other than squib valves perform the active function identified in Attachment0 after a signal is input to the PMS.

References 8 through 17 establish initial conditions with each valve verified locally and in the MCR to be in the required position. An actuation signal is generated by PMS using the PMS Maintenance and Test Panel(MTP)to generate a signal to cause the valves in Attachment C to transfer to the active function position and each valve is verified locally and in the MCR.

The completed test results(References 5 & 6)confirm the remotely operated valves other than squib valves perform the active function identified in the table after a signal is input to the PMS for Unit 3 and Unit 4.

iii) These valves open within 20 seconds after receiot of an actuation sional.

Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 5 and 6). These component test packages utilize B-GEN-ITPCI-039(Reference 7)to direct the performance of test procedures 3/4-GEN-OTS 001 (References 8 and 9), 3/4-GEN-OTS-10-002(References 10 and 11), 3/4-GEN-OTS 003(References 12 and 13), 3/4-GEN-OTS-10-004(References 14 and 15), and 3/4-PXS-OTS-10-001 (References 16 and 17)to confirm that remotely operated PXS isolation valves PXS-V014A/B, V015A/B, V108A/B open within 20 seconds after receipt of an actuation signal.

References 8 through 17 establish initial conditions with each valve verified locally and in the MCR to be in the closed position and a digital trend is established to time the valve actuation.

An actuation signal is generated by PMS using the PMS Maintenance and Test Panel(MTP)to generate a signal to cause the valves in Attachment D to transfer open and each valve is verified locally and in the MCR.

The completed test results(References 5 and 6)confirm that remotely operated PXS isolation valves PXS-V014A/B, V015A/B, V108A/B open within 20 seconds after receipt of an actuation signal for Unit 3 and Unit 4 and the test results are documented in Attachment D.

After loss of motive power, each remotelv operated valve identified in Table 2.2.3-1 assumes the indicated loss of motive power oosition.

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

U.S. Nuclear Regulatory Commission ND-19-1054 Enciosure Page 5 of 12 Testing is performed on the Motor-Operated Valves(MOVs)listed in Attachment E by opening the power supply to the MOVs when they are closed and verifying they remain closed. Power is restored to the MOVs and they are opened. The power supply to the MOVs is opened and they are verified to remain open.

Testing on the air operated valves is performed by placing the valves in a position opposite their loss of motive power position and opening the power supply to their air supply solenoid. This causes the solenoid to de-energize which closes the air supply to the valve and opens a vent port to vent off the air in the actuator. The valves are verified locally and in the MCR to transfer to their loss of motive power position.

The motive power for the squib valves is a single-use explosive device powered by Direct Current(DC) Power. By design, this configuration results in the squib valves maintaining their as-is position upon a loss of motive power, as power is required to ignite the explosive device which repositions the valve. As a result, no loss of motive power testing is required for the squib valves. Functional testing of the squib valve actuation circuits is performed by other ITAAC.

The completed test results(References 18 and 19) confirm that after loss of motive power, each remotely operated valve identified in Table 2.2.3-1 assumes the indicated loss of motive power position for Unit 3 and Unit 4.

Displavs identified in Table 2.2.3-3 can be retrieved in the MCR.

An inspection is performed in accordance with Unit 3 and Unit 4 component test work packages, SNC921612 and SNCYYYYYY (References 1 and 2)to confirm displays identified in Attachment F can be retrieved in the MCR.

Testing is performed at an operator work station by navigating to several PXS system screens, locating the items identified in Attachment F, and ensuring the items identified can be retrieved in the MCR.

The completed test results (References 1 and 2)confirm that the displays identified in Table 2.2.3-3 can be retrieved in Unit 3 and Unit 4 MCR.

References 1 through 19 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC Completion Packages(Reference 20 and 21).

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 favailable for NRC inspection)

1. SNC921612,"PXS Indication Verifications - ITAAC: SV3-2.2.03.10 Items 10 and 13"

2. SNCYYYYYY,"PXS Indication Verifications - ITAAC: SV4-2.2.03.10 Items 10 and 13"

3. SNC921614,"PXS Remotely Operated Valve Stroke Test - ITAAC: SV3-2.2.03.10, Item 11a.ii"

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 6 of 12

4. SNCYYYYYY,"PXS Remotely Operated Valve Stroke Test- ITAAC: SV4-2.2.03.10, Item 11a.ii"

5. SNOXXXXXX

6. SNCYYYYYY

7. B-GEN-ITPCI-039,"PMS CIM Component Test Procedure"

8. 3-GEN-0TS-10-001,"DIVISION A QUARTERLY VALVE STROKE TEST'

9. 4-GEN-0TS-10-001,"DIVISION A QUARTERLY VALVE STROKE TEST'

10. 3-GEN-0TS-10-002,"DIVISION B QUARTERLY VALVE STROKE TEST'

11. 4-GEN-0TS-10-002,"DIVISION B QUARTERLY VALVE STROKE TEST'

12. 3-GEN-0TS-10-003,"DIVISION C QUARTERLY VALVE STROKE TEST' 13.4-GEN-0TS-10-003,"DIVISION C QUARTERLY VALVE STROKE TEST'

14. 3-GEN-0TS-10-004,"DIVISION D QUARTERLY VALVE STROKE TEST'

15. 4-GEN-0TS-10-004,"DIVISION D QUARTERLY VALVE STROKE TEST'

16. 3-PXS-0TS-10-001,"Passive Core Cooling System Valve Stroke Test" 17.4-PXS-0TS-10-001,"Passive Core Cooling System Valve Stroke Test"

18. SNCXXXXXX,"PXS Remotely Operated Valve Loss of Motive Power Test - ITAAC: SV3-2.2.03.10, Item 12b"

19. SNCYYYYYY,"PXS Remotely Operated Valve Loss of Motive Power Test- ITAAC: SV4-2.2.03.10, Item 12b" 20.2.2.03.10-U3-CP-Rev0, ITAAC Completion Package 21.2.2.03.10-U4-CP-Rev0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 7 of 12 Attachment A

'Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Equipment Name *Tag No. *Safety-Related Display CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A Yes (Position)

CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B Yes (Position)

CMT A Discharge Isolation Valve PXS-PL-V014A Yes (Position)

CMT B Discharge Isolation Valve PXS-PL-V014B Yes (Position)

CMT A Discharge Isolation Valve PXS-PL-V015A Yes(Position)

CMT B Discharge Isolation Valve PXS-PL-V015B Yes(Position)

Nitrogen Supply Containment Isolation PXS-PL-V042 Yes(Position)

Valve PRHR HX Inlet Isolation Motor-operated PXS-PL-V101 Yes (Position)

Valve PRHR HX Control Valve PXS-PL-V108A Yes (Position)

PRHR HX Control Valve PXS-PL-V108B Yes (Position)

Containment Recirculation A Isolation PXS-PL-V117A Yes (Position)

Motor-operated Valve Containment Recirculation B Isolation PXS-PL-V117B Yes (Position)

Motor-operated Valve Containment Recirculation A Squib PXS-PL-V118A Yes (Position)

Valve Containment Recirculation B Squib PXS-PL-V118B Yes (Position)

Valve Containment Recirculation A Squib PXS-PL-V120A Yes(Position)

Valve Containment Recirculation B Squib PXS-PL-V120B Yes (Position)

Valve IRWST Injection A Squib Valve PXS-PL-V123A Yes (Position)

IRWST Injection A Squib Valve PXS-PL-V123B Yes (Position)

IRWST Injection A Squib Valve PXS-PL-V125A Yes (Position)

IRWST Injection A Squib Valve PXS-PL-V125B Yes (Position)

IRWST Gutter Isolation Valve PXS-PL-V130A Yes (Position)

IRWST Gutter Isolation Valve PXS-PL-V130B Yes (Position)

CMT A Level Sensor PXS-011A Yes CMT A Level Sensor PXS-011B Yes CMT A Level Sensor PXS-011C Yes CMT A Level Sensor PXS-011D Yes CMT B Level Sensor PXS-012A Yes CMT B Level Sensor PXS-012B Yes CMT B Level Sensor PXS-012C Yes CMT B Level Sensor PXS-012D Yes CMT A Level Sensor PXS-013A Yes

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 8 of 12 Attachment A (con't)

Table 2.2.3-1

^Equipment Name *Tag No. *Safety-Related Display CMT A Level Sensor PXS-013B Yes CMT A Level Sensor PXS-013C Yes CMT A Level Sensor PXS-013D Yes CMT B Level Sensor PXS-014A Yes CMT B Level Sensor PXS-014B Yes CMT B Level Sensor PXS-014C Yes CMT B Level Sensor PXS-014D Yes IRWST Wide Range Level Sensor PXS-046 Yes IRWST Wide Range Level Sensor PXS-047 Yes IRWST Wide Range Level Sensor PXS-048 Yes PRHR HX Flow Sensor PXS-049A Yes PRHR HX Flow Sensor PXS-049B Yes Containment Flood-up Level Sensor PXS-050 Yes Containment Flood-up Level Sensor PXS-051 Yes Containment Flood-up Level Sensor PXS-052 Yes IRWST Lower Narrow Range Level Sensor PXS-066 Yes IRWST Lower Narrow Range Level Sensor PXS-067 Yes IRWST Lower Narrow Range Level Sensor PXS-068 Yes IRWST Lower Narrow Range Level Sensor PXS-069 Yes Attachment B

'Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

• Equipment Name *Tag No. *Remotely *Act[ve Operated Function Valve CMT A Discharge Isolation Valve PXS-PL-V014A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V014B YES Transfer Open CMT A Discharge Isolation Valve PXS-PL-V015A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V015B YES Transfer Open Nitrogen Supply Containment PXS-PL-V042 YES Transfer Closed Isolation Valve PRHR HX Control Valve PXS-PL-V108A YES Transfer Open PRHR HX Control Valve PXS-PL-V108B YES Transfer Open IRWST Gutter Isolation Valve PXS-PL-V130A YES Transfer Closed IRWST Gutter Isolation Valve PXS-PL-V130B YES Transfer Closed

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 9 of 12 Attachment 0

'Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1 "Equipment Name "Tag No. "Control "Active RMS Function CMT A Discharge Isoiation Valve PXS-PL-V014A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V014B YES Transfer Open CMT A Discharge Isolation Valve PXS-PL-V015A YES Transfer Open CMT B Discharge Isolation Valve PXS-PL-V015B YES Transfer Open Nitrogen Supply Containment PXS-PL-V042 YES Transfer Closed Isolation Valve PRHR HX Control Valve PXS-PL-V108A YES Transfer Open PRHR HX Control Valve PXS-PL-V108B YES Transfer Open IRWST Gutter Isolation Valve PXS-PL-V130A YES Transfer Closed IRWST Gutter Isolation Valve PXS-PL-V130B YES Transfer Closed Attachment D

'Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1 Unit "Equipment "Tag No. "Remotely "Control Opening Name Operated RMS Time Valve 3 CMT A Discharge PXS-PL- Yes Yes XX sec Isolation Valve V014A 3 CMT B Discharge PXS-PL- Yes Yes XX sec Isolation Valve V014B 3 CMT A Discharge PXS-PL- Yes Yes XX sec Isolation Valve V015A 3 CMT B Discharge PXS-PL- Yes Yes XX sec Isolation Valve V015B 3 PRHR HX Control PXS-PL- Yes Yes XX sec Valve V108A 3 PRHR HX Control PXS-PL- Yes Yes XX sec Valve V108B 4 CMT A Discharge PXS-PL- Yes Yes XX sec Isolation Valve V014A 4 CMT B Discharge PXS-PL- Yes Yes XX sec Isolation Valve V014B 4 CMT A Discharge PXS-PL- Yes Yes XX sec Isolation Valve V015A

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 10 of 12 Attachment D (con't)

Table 2.2.3-1 Unit ^Equipment *Tag No. *Remotely *Control Opening Name Operated RMS Time Valve 4 CMT B Discharge PXS-PL- Yes Yes XX sec Isolation Valve V015B 4 PRHR HX Control PXS-PL- Yes Yes XX sec Valve V108A 4 PRHR HX Control PXS-PL- Yes Yes XX sec Valve V108B Attachment E

'Excerpt from COL Appendix C Table 2.2.3-1 Table 2.2.3-1

^Equipment Name *Tag No. *Remotely *Loss of Operated Motive Valve Power Position CMT A Inlet Isolation Motor-operated PXS-PL-V002A Yes As Is Valve CMT B Inlet Isolation Motor-operated PXS-PL-V002B Yes As Is Valve CMT A Discharge Isolation Valve PXS-PL-V014A Yes Open CMT B Discharge Isolation Valve PXS-PL-V014B Yes Open CMT A Discharge Isolation Valve PXS-PL-V015A Yes Open CMT B Discharge Isolation Valve PXS-PL-V015B Yes Open Accumulator A Discharge PXS-PL-V027A Yes As Is Isolation Valve Accumulator B Discharge PXS-PL-V027B Yes As Is Isolation Valve Nitrogen Supply Containment Isolation PXS-PL-V042 Yes Closed Valve PRHR HX Inlet Isolation Motor- PXS-PL-V101 Yes As Is operated Valve PRHR HX Control Valve PXS-PL-V108A Yes Open PRHR HX Control Valve PXS-PL-V108B Yes Open Containment Recirculation A Isolation PXS-PL-V117A Yes As Is Motor-operated Valve Containment Recirculation B Isolation PXS-PL-V117B Yes As Is Motor-operated Valve Containment Recirculation A Squib PXS-PL-V118A Yes As Is Valve

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 11 of 12 Attachment E (con't)

Table 2.2.3-1

^Equipment Name *Tag No. *Remotely *Loss of Operated Motive Valve Power Position Containment Recirculation B Squib PXS-PL-V118B Yes As Is Valve Containment Recirculation A Squib PXS-PL-V120A Yes As Is Valve Containment Recirculation B Squib PXS-PL-V120B Yes As Is Valve IRWST Injection A Squib Valve PXS-PL-V123A Yes As Is IRWST Injection A Squib Valve PXS-PL-V123B Yes As Is IRWST Injection A Squib Valve PXS-PL-V125A Yes As Is IRWST Injection A Squib Valve PXS-PL-V125B Yes As Is IRWST Gutter Isolation Valve PXS-PL-V130A Yes Closed IRWST Gutter Isolation Valve PXS-PL-V130B Yes Closed Attachment F

'Excerpt from COL Appendix C Table 2.2.3-3 Table 2.2.3-3

• Equipment *Tag No. *Dlsplav CMT A Discharge Isolation Valve (Position) PXS-PL-V014A Yes(Position)

CMT B Discharge Isolation Valve (Position) PXS-PL-V014B Yes(Position)

CMT A Discharge Isolation Valve (Position) PXS-PL-V015A Yes(Position)

CMT B Discharge Isolation Valve (Position) PXS-PL-V015B Yes(Position)

Accumulator A Nitrogen Vent Valve (Position) PXS-PL-V021A Yes(Position)

Accumulator B Nitrogen Vent Valve (Position) PXS-PL-V021B Yes(Position)

Accumulator A Discharge Isolation Valve (Position) PXS-PL-V027A Yes(Position)

Accumulator B Discharge Isolation Valve (Position) PXS-PL-V027B Yes(Position)

PRHR HX Control Valve (Position) PXS-PL-V108A Yes(Position)

PRHR HX Control Valve (Position) PXS-PL-V108B Yes(Position)

Containment Recirculation A Isolation PXS-PL-V117A Yes(Position)

Motor-operated Valve (Position)

Containment Recirculation B Isolation PXS-PL-V117B Yes(Position)

Motor-operated Valve (Position)

Containment Recirculation A Squib PXS-PL-V118A Yes(Position)

Valve (Position)

Containment Recirculation B Squib PXS-PL-V118B Yes (Position)

Valve (Position)

U.S. Nuclear Regulatory Commission ND-19-1054 Enclosure Page 12 of 12 Attachment F (con't)

Table 2.2.3-3

• Equipment *Tag No. ^Display Containment Recirculation A Squib PXS-PL-V120A Yes (Position)

Valve (Position)

Containment Recirculation B Squib PXS-PL-V120B Yes (Position)

Valve (Position)

IRWST Line A Isolation Valve (Position) PXS-PL-V121A Yes (Posiltion)

IRWST Line B Isolation Valve (Position) PXS-PL-V121B Yes (Posiltion)

IRWST Injection A Squib Valve (Position) PXS-PL-V123A Yes (Posiltion)

IRWST Injection A Squib Valve (Position) PXS-PL-V123B Yes (Posiltion)

IRWST Injection A Squib Valve (Position) PXS-PL-V125A Yes (Posiltion)

IRWST Injection A Squib Valve (Position) PXS-PL-V125B Yes (Posiltion)

IRWST Gutter Isolation Valve (Position) PXS-PL-V130A Yes (Posiltion)

IRWST Gutter Isolation Valve (Position) PXS-PL-V130B Yes (Posiltion)

Accumulator A Level Sensor PXS-JE-L021 Yes Accumulator B Level Sensor PXS-JE-L022 Yes Accumulator A Level Sensor PXS-JE-L023 Yes Accumulator B Level Sensor PXS-JE-L024 Yes PRHR HX Inlet Temperature Sensor PXS-JE-L064 Yes IRWST Surface Temperature Sensor PXS-JE-L041 Yes IRWST Surface Temperature Sensor PXS-JE-L042 Yes IRWST Bottom Temperature Sensor PXS-JE-L043 Yes IRWST Bottom Temperature Sensor PXS-JE-L044 Yes