ND-23-0238, ITAAC Closure Notification on Completion of ITAAC 2.3.06.11a (Index Number 382)

ITAAC Closure Notification on Completion of ITAAC 2.3.06.11a (Index Number 382)

ML23125A295
Person / Time
Site:	Vogtle
Issue date:	05/05/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0238, ITAAC 2.3.06.11a
Download: ML23125A295 (1)

Text

Jamie M. Coleman 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6926 tel

May 5, 2023

Docket No.: 52-026

ND-23-0238 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.3.06.11a [Index Number 382]

Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)

Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.06.11a [Index Number 382], to verify that the valves/pumps identified in Combined License (COL) Appendix C Tables 2.3.6-1 and 2.3.6-3 respond per the Acceptance Criteria specified per ITAAC 2.3.06.11a.

The closure process for this ITAAC is based on the guidance described in NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52, which is endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted,

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.06.11a [Index Number 382]

JMC/KIK/sfr

U.S. Nuclear Regulatory Commission ND-23-0238 Page 2 of 2

cc: Regional Administrator, Region ll Director, Office of Nuclear Reactor Regulation (NRR)

Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4

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Southern Nuclear Operating Company ND-23-0238 Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.3.06.11a [Index Number 382]

U.S. Nuclear Regulatory Commission ND-23-0238 Enclosure Page 2 of 12

ITAAC Statement

Design Commitment

10. Safety-related displays identified in Table 2.3.6-1 can be retrieved in the MCR.

11.a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.3.6-1 to perform active functions.

11.b) The valves identified in Table 2.3.6-1 as having PMS control perform active safety functions after receiving a signal from the PMS.

12.b) After loss of motive power, the remotely oper ated valves identified in Table 2.3.6-1 assume the indicated loss of motive power position.

13. Controls exist in the MCR to cause the pump s identified in Table 2.3.6-3 to perform the control function.

14. Displays of the RNS parameters identified in Table 2.3.6-3 can be retrieved in the MCR.

Inspections/Tests/Analyses

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

Stroke testing will be performed on the remotely operated valves identified in Table 2.3.6-1 using the controls in the MCR.

Testing will be performed using real or simulated signals into the PMS.

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

Testing will be performed to actuate the pumps identified in Table 2.3.6-3 using controls in the MCR.

Inspection will be performed for retrievability in the MCR of the displays identified in Table 2.3.6-3.

Acceptance Criteria

Safety-related displays identified in Table 2.3.6-1 can be retrieved in the MCR.

Controls in the MCR operate to cause those remote ly operated valves identified in Table 2.3.6-1 to perform active functions.

The valves identified in Table 2.3.6-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS.

Upon loss of motive power, each remotely operated valve identified in Table 2.3.6-1 assumes the indicated loss of motive power position.

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Controls in the MCR cause pumps identified in Table 2.3.6-3 to perform the control function.

Displays of the RNS parameters identified in Table 2.3.6-3 are retrieved in the MCR.

ITAAC Determination Basis

Testing or inspections were performed to verify that the Normal Residual Heat Removal System (RNS) provides the following functions:

x Inspections performed demonstrate the safety-related displays identified in Combined License (COL) Appendix C Table 2.3.6-1 (Attachment A) can be retrieved in the Main Control Room (MCR).

x Testing performed demonstrates that controls in the MCR operate to cause those remotely operated valves identified in Table 2.3.6-1 (Attachment B) to perform active functions.

x Testing performed demonstrates that the valves identified in table 2.3.6-1 (Attachment C) as having Protection and Monitoring System (PMS) control perform the active function identified in the table after receiving a signal from the PMS.

x Testing performed demonstrates that after a loss of motive power, the remotely operated valves identified in Table 2.3.6-1 (Attachment D) assumes the indicated loss of motive power position.

x Testing performed demonstrates that controls in the MCR cause pumps identified in Table 2.3.6-3 (Attachment E) to perform the control function.

x Inspections performed demonstrate the displays of the RNS parameters identified in Table 2.3.6-3 (Attachment F) are retrieved in the MCR.

Safety-related displays identified in Table 2.3.6-1 can be retrieved in the MCR.

An inspection was performed to verify the safety -related displays identified in Attachment A can be retrieved in the MCR. Inspections were performed as described in the SV4-RNS-ITR-800382 Technical Report (Reference 11) which visually confirmed 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 valve position appears on the PMS VDU.

Controls in the MCR operate to cause those remote ly operated valves identified in Table 2.3.6-1 to perform active functions.

Testing was performed in accordance with Unit 4 component test work package 1191320 (Reference 1) to verify that controls in the M CR operate to cause those remotely operated valves identified in Attachment B to perform active fu nctions. Testing was conducted at an operator workstation, and Division A through D PMS VDUs in Unit 4 MCR to verify the valves identified in Attachment B as being remotely operated and having active functions are stroked open and closed from the MCR. The valve positions were verified locally and in the MCR. This confirmed that controls in Unit 4 MCR operate to cause the remotely operated valves to perform active safety functions.

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The completed Unit 4 testing results (Reference 1), as documented in SV4-RNS-ITR-802382 (Reference 11), confirmed that controls in the MCR operate to cause those remotely operated valves identified in Table 2.3.6-1 to perform active functions.

The valves identified in Table 2.3.6-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS.

Testing was performed in accordance with Unit 4 component test packages and procedures (References 2 through 10) to verify that the valv es identified in Attachment C as having PMS control perform the active function identified in the Attachment after receiving a signal from the PMS.

Unit 4 component test packages and procedures (References 2 through 10) established initial conditions with each valve verified locally and in the MCR to be in the Open position. An actuation signal was generated by PMS using the PMS Maintenance and Test Panel (MTP) to generate a signal to Close the valves in Attachment C. Each valve was verified locally and in the MCR to be Closed.

The completed Unit 4 testing results (References 2 through 10), as documented in SV4-RNS-ITR-801382 (Reference 12), confirmed that the valves identified in Table 2.3.6-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS.

Upon loss of motive power, each remotely operated valve identified in Table 2.3.6-1 assumes the indicated loss of motive power position.

Testing was performed in accordance with Unit 4 component test work package 1191320 (Reference 1) to verify that upon loss of motive power, each remotely operated valve identified in Attachment D assumes the indicated loss of motive power position.

Reference 1 was used to establish the RNS-PL-V024 Motor Operated Valve (MOV) identified in Table 2.3.6-1 in the pretest position of open. Motive power was removed from the valve by opening the associated breaker, an attempt was made to reposition the valve, and a verification was performed to ensure the valve stayed in the As-Is (Open) position. Actual valve position was verified locally and in the MCR. Motive power was restored and the valve was repositioned to closed. Motive power was again removed from the valve by opening the associated breaker, an attempt was made to reposition the valve, and a verification was performed to ensure the valve stayed in the As-Is (Closed) position. Actual valve position was verified locally and in the MCR.

References 1 and 2 were used to establish RNS-PL-V022, RNS-PL-V011, RNS-PL-V001A, RNS-PL-V001B, RNS-PL-V002A, RNS-PL-V002B, RNS-PL-V022, RNS-PL-V023 and RNS-PL-V055 Motor Operated Valves (MOVs) identified in Table 2.1.2-1 in their pretest position of closed. Each MOV was stroked Open by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the Open position was reached.

This loss of power caused by the valve control circuit demonstrated the MOV failed As -Is (Open) when motive power was removed. Actual valve position was verified locally. Each MOV was also stroked Closed by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the Closed position was reached. This loss of power U.S. Nuclear Regulatory Commission ND-23-0238 Enclosure Page 5 of 12

caused by the valve control circuit demonstrated that each MOV failed As-Is (Closed) when motive power was removed. Actual valve position was verified locally.

Reference 1 verified the Air Operated Valves (AOVs) go to the loss of motive power position. For RNS-PL-V057A and -V057B (RNS Pump Miniflow Air-Operated Isolation Valves) testing, the valves were Closed and verified Closed locally and in the MCR. Power was removed from the solenoid valves supplying air to the valve actuators which removed motive power to the valves.

RNS-PL-V057A and -V057B were verified to be Open locally and in the MCR. For RNS PL-V061 (RNS Return from Chemical and Volume Control System (CVS) Containment Isolation Valve) testing, the valve was Opened and verified Open locally and in the MCR. Power was removed from the solenoid valve supplying air to the valve actuator which removed motive power to the valve. RNS-PL-V061 was verified to Close locally and in the MCR.

The completed Unit 4 testing results (References 1and 2), as documented in SV4-RNS-ITR-802382 (Reference 13), confirmed that upon loss of motive power, each remotely operated valve identified in Table 2.3.6-1 assumed the indicated loss of motive power position.

Controls in the MCR cause pumps identified in Table 2.3.6-3 to perform the control function.

Testing was performed in accordance with Unit 4 component test work package 1191320 (Reference 1) to verify that controls in the MCR cause pumps identified in Attachment E to perform the control function.

Reference 1 established the initial conditions with both RNS pumps stopped. The pumps were started using Plant Control System (PLS) controls in the MCR. Both RNS pumps were verified to have started locally and in the MCR.

The completed Unit 4 component test results (Reference 1), as documented in SV4-RNS-ITR-804382 (Reference 14) confirmed that controls in the MCR cause pumps identified in Table 2.3.6-3 to perform the control function.

Displays of the RNS parameters identified in Table 2.3.6-3 are retrieved in the MCR.

An inspection was performed to verify displays of the RNS parameters identified in Attachment F are retrieved in the MCR.

Inspection was performed at an MCR operator workstation and visually confirmed that when each of the displays of parameters identified in Attachment F is summoned at an MCR workstation, the summoned plant parameter appears on a display monitor at the MCR workstation. The results as documented in SV4-RNS-ITR-800382 (Reference 11), confirmed that displays of the RNS parameters identified in Table 2.3.6-3 were retrieved in the MCR.

References 1 through 14 are available for NRC inspection as part of ITAAC 2.3.06.11a Unit 4 Completion Package (Reference 15).

ITAAC Finding Review

In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated U.S. Nuclear Regulatory Commission ND-23-0238 Enclosure Page 6 of 12

with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.06.11a (Reference 15) and is available for NRC review.

ITAAC Completion Statement

Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.06.11a was performed for VEGP Unit 4 and that the pr escribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

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References (available for NRC inspection)

1. SV4-RNS-T0W-1191320, Rev. 0, Perform ITAAC 2.3.06.11a Items 10, 11.a, 12.b, 13 and 14 RNS

2. SV4-RNS-T0W-1191390, PLANT INTERFACE TESTING OF MODULE SV4-PLS-JD-DPU019 REFERENCE VALVE SV4-RNS-PL-V055

3. SV4-RNS-T0W-1285540, Rev. 0, Perform PMS Component Test for SV4-RNS-PL-V001A

4. SV4-RNS-T0W-1285541, Rev. 0, Perform PMS Component Test SV4-RNS-PL-V001B

5. SV4-RNS-T0W-1245225, Rev. 0, Perform Plant PMS / PLS Interface Test for SV4-RNS-PL-V002A

6. SV4-RNS-T0W-1245226, Rev. 0, Perform Plant PMS / PLS Interface Test for SV4-RNS-PL-V002B

7. SV4-RNS-T0W-1245469, Rev. 0, Perform PLS / PMS Component Interface Test SV4-RNS-PL-V011

8. SV4-RNS-T0W-1245471, Rev. 0, Perform Plant PMS / PLS Interface Test for SV4-RNS-PL-V022

9. SV4-RNS-T0W-1245483, Rev. 0, Perform Plant PMS / PLS Interface Test for SV4-RNS-PL-V023

10. SV4-RNS-T0W-1247406, Rev. 0, Perform ITAAC PMS CIM SV4-RNS-PL-V061 Component Test

11. SV4-RNS-ITR-800382, Rev 0, Unit 4 Testing Results of: ITAAC 2.3.06.11.a (Items 10 and 14)

12. SV4-RNS-ITR-801382, Rev 0, Unit 4 Testing Results of: ITAAC 2.3.06.11.a (Item 11.b)

13. SV4-RNS-ITR-802382, Rev 0, Unit 4 Inspection Results of: ITAAC 2.3.06.11a (Items 11.a & 12.b)

14. SV4-RNS-ITR-804382, Rev 0, Unit 4 Inspection Results of: ITAAC 2.3.06.11a (Item 13)

15. 2.3.06.11a-U4-CP-Rev0, ITAAC Completion Package

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Attachment A

• Excerpt from COL Appendix C Table 2.3.6-1

Table 2.3.6-1

• Equipment Name *Tag No. *Safety-Related Display

RCS Inner Hot Leg Suction Motor-operated V001A Yes Isolation Valve RNS-PL-(Valve Position)

RCS Inner Hot Leg Suction Motor-operated B Yes Isolation Valve RNS-PL-V001(Valve Position)

RCS Outer Hot Leg Suction Motor-operated A Yes Isolation Valve RNS-PL-V002(Valve Position)

RCS Outer Hot Leg Suction Motor-operated 2B Yes Isolation Valve RNS-PL-V00(Valve Position)

RNS Discharge Motor-operated Containment Yes Isolation Valve RNS-PL-V011(Valve Position)

RNS Suction Header Motor-operated Yes Containment Isolation Valve RNS-PL-V022(Valve Position)

RNS Suction from IRWST Motor-operated Yes Isolation Valve RNS-PL-V023(Valve Position)

RNS Return from Chemical and Volume Control Yes System (CVS) Containment Isolation Valve RNS-PL-V061 (Valve Position)

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Attachment B

• Excerpt from COL Appendix C Table 2.3.6-1

Table 2.3.6-1

• Remotely *Active

• Equipment Name *Tag No. Operated Function Valve

RCS Inner Hot Leg Suction Transfer Motor-operated Isolation Valve RNS-PL-V001A Yes Closed

RCS Inner Hot Leg Suction Transfer Motor-operated Isolation Valve RNS-PL-V001B Yes Closed

RCS Outer Hot Leg Suction Transfer Motor-operated Isolation Valve RNS-PL-V002A Yes Closed

RCS Outer Hot Leg Suction Transfer Motor-operated Isolation Valve RNS-PL-V002B Yes Closed

RNS Discharge Motor-operated Transfer Containment Isolation Valve RNS-PL-V011 Yes Closed

RNS Suction Header Motor-operated Transfer Containment Isolation Valve RNS-PL-V022 Yes Closed

RNS Suction from IRWST Transfer Motor-operated Isolation Valve RNS-PL-V023 Yes Closed

RNS Return from Chemical and Transfer Volume Control System (CVS) RNS-PL-V061 Yes Closed Containment Isolation Valve U.S. Nuclear Regulatory Commission ND-23-0238 Enclosure Page 10 of 12

Attachment C

• Excerpt from COL Appendix C Table 2.3.6-1

Table 2.3.6-1

• Equipment Name *Tag No. *Control PMS *Active Function

RCS Inner Hot Leg Suction RNS-PL-V001A Yes Transfer Motor-operated Isolation Valve Closed

RCS Inner Hot Leg Suction RNS-PL-V001B Yes Transfer Motor-operated Isolation Valve Closed

RCS Outer Hot Leg Suction RNS-PL-V002A Yes Transfer Motor-operated Isolation Valve Closed

RCS Outer Hot Leg Suction RNS-PL-V002B Yes Transfer Motor-operated Isolation Valve Closed

RNS Discharge Motor-operated V011 Yes Transfer Containment Isolation Valve RNS-PL-Closed

RNS Suction Header Motor-operated Containment RNS-PL-V022 Yes TransferClosed Isolation Valve

RNS Suction from IRWST RNS-PL-V023 Yes Transfer Motor-operated Isolation Valve Closed

RNS Return from Chemical and Volume Control System (CVS) RNS-PL-V061 Yes TransferClosed Containment Isolation Valve U.S. Nuclear Regulatory Commission ND-23-0238 Enclosure Page 11 of 12

Attachment D

• Excerpt from COL Appendix C Table 2.3.6-1

Table 2.3.6-1

• Loss of

• Equipment Name *Tag No. Motive Power Position

RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A As Is

RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B As Is

RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A As Is

RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B As Is

RNS Discharge Motor-operated Containment Isolation As Is Valve RNS-PL-V011

RNS Suction Header Motor-operated Containment As Is Isolation Valve RNS-PL-V022

RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 As Is

RNS Discharge to IRWST Motor-operated Isolation Valve RNS-PL-V024 As Is

RNS Suction from Cask Loading Pit Motor-operated As Is Isolation Valve RNS-PL-V055

RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057A Open

RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057B Open

RNS Return from Chemical and Volume Control System Closed (CVS) Containment Isolation Valve RNS-PL-V061

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Attachment E

• Excerpt from COL Appendix C Table 2.3.6-3

Table 2.3.6-3

• Equipment Name *Tag No. *Control Function RNS Pump 1A (Motor) RNS-MP-01A Start RNS Pump 1B (Motor) RNS-MP-01B Start

Attachment F

• Excerpt from COL Appendix C Table 2.3.6-3

Table 2.3.6-3

• Equipment Name *Tag No. *Display RNS Pump 1A (Motor) RNS-MP-01A Yes (Run Status)

RNS Pump 1B (Motor) RNS-MP-01B Yes (Run Status)

RNS Flow Sensor RNS-01A Yes RNS Flow Sensor RNS-01B Yes

RNS Suction from Cask Loading Pit Isolation Valve Yes (Position Indicator) RNS-PL-V055

RNS Pump Miniflow Isolation Valve Yes (Position Indicator) RNS-PL-V057A RNS Pump Miniflow Isolation Valve RNS-PL-V057B Yes (Position Indicator)