ND-23-0447, ITAAC Closure Notification on Completion of ITAAC 2.6.03.04i (Index Number 609)

ITAAC Closure Notification on Completion of ITAAC 2.6.03.04i (Index Number 609)

ML23168A001
Person / Time
Site:	Vogtle
Issue date:	06/17/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-23-0447, ITAAC 2.6.03.04i
Download: ML23168A001 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel June 17, 2023 Docket No.:

52-026 ND-23-0447 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 2.6.03.04i [Index Number 609]

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 2.6.03.04i [Index Number 609].

This ITAAC confirms that the Class 1E DC and Uninterruptible Power Supply System (IDS) supplies an operating voltage at the terminals of the specified Class 1E motor operated valves that is greater than or equal to the minimum design voltage. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (NEI) 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52," which was endorsed by the NRC in Regulatory Guide 1.215.

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

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

Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.6.03.04i [Index Number 609]

JMC/TJC/sfr

U.S. Nuclear Regulatory Commission ND-23-0447 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

U.S. Nuclear Regulatory Commission ND-23-0447 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-23-0447 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.6.03.04i [Index Number 609]

U.S. Nuclear Regulatory Commission ND-23-0447 Enclosure Page 2 of 6 ITAAC Statement Design Commitment 4.i) The IDS supplies an operating voltage at the terminals of the Class 1E motor operated valves identified in subsections 2.1.2, 2.2.1, 2.2.2, 2.2.3, 2.2.4, 2.3.2, 2.3.6, and 2.7.1 that is greater than or equal to the minimum design voltage.

Inspections/Tests/Analyses Testing will be performed by measuring the voltage during motor starting at both the IDS battery and motor-operated valve motor terminals while each motor-operated valve is stroked. Analyses will be performed to verify that the voltage at the motor operated valve motor terminals is greater than or equal to the minimum design voltage of each motor operated valve with an IDS battery terminal voltage of 210 Vdc.

Acceptance Criteria A report exists and concludes that IDS can provide a voltage greater than or equal to each valve's minimum design voltage to the motor terminals of each motor operated valve when power is supplied under design conditions from IDS batteries with battery terminal voltage at 210 Vdc while each motor operated valve is stroked.

ITAAC Determination Basis Testing was performed by measuring the voltage during motor starting at both the Class 1E DC and Uninterruptible Power Supply system (IDS) battery and motor-operated valve (MOV) motor terminals while each MOV is stroked. Analyses were performed to verify that the voltage at the MOV motor terminals is greater than or equal to the minimum design voltage of each MOV with an IDS battery terminal voltage of 210 volts direct current (Vdc).

Analyses were performed in accordance with SV4-IDS-E0C-004 (Reference 1) to determine the voltage drop on each power circuit at a battery voltage of 210 Vdc and the resulting voltage at the MOV terminals during normal operating conditions, and accident conditions. Reference 1 is the basis of analyses performed in accordance with SV4-IDS-E0C-018 (Reference 2). The analyses determined the expected voltage at the MOV terminals and defined the method for the determination of the minimum acceptance voltage for each MOV during preoperational testing.

Each MOV identified in Combined License (COL) Appendix C, Subsections 2.1.2, 2.2.1,2.2.2, 2.2.3, 2.2.4, 2.3.2, 2.3.6, and 2.7.1 (Attachment A) was stroked individually as documented in SV4-IDS-E0R-007 (Reference 3). The voltage at the battery terminals and at the MOV terminals was recorded during MOV operation using installed maintenance and test equipment. The recorded voltage at the MOV terminals was analyzed in accordance with the method described in Reference 2, to compare proportional values when the tested battery voltage is higher or lower than the nominal voltage assumed in the analysis of Reference 2, to determine the minimum acceptance voltage for each MOV. A resulting proportional voltage that is greater than or equal to the minimum design voltage of each MOV confirms the tested voltage is bounded by the analysis in Reference 2.

U.S. Nuclear Regulatory Commission ND-23-0447 Enclosure Page 3 of 6 The analyses and preoperational test results (References 1 through 3) confirmed that IDS can provide a voltage greater than or equal to each MOV's minimum design voltage to the terminals of each MOV, as specified in Reference 2, when power is supplied under design conditions from IDS batteries with battery terminal voltage at 210 Vdc while each MOV is stroked.

References 1 through 3 are available for NRC inspection as part of Unit 4 ITAAC Completion Package (Reference 4).

ITAAC Finding Review In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found there were no relevant findings associated with this ITAAC. The review is documented in the ITAAC 2.6.03.04i Completion Package (Reference

4) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.6.03.04i was performed for VEGP Unit 4 and the prescribed acceptance criteria was met.

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

References (available for NRC inspection)

1. SV4-IDS-E0C-004, Rev 6, "IDS Power Cable Sizing and Voltage Drop Analysis"

2. SV4-IDS-E0C-018, Rev 1, "MOV Acceptance Voltage During Safety Related DC MOV Field Testing"

3. SV4-IDS-E0R-Vogtle Unit 4 IDS System ITAAC 2.6.03.04i MOV Voltage Test Analyses Report

4. 2.6.03.04i-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-23-0447 Enclosure Page 4 of 6 Attachment A Table 2.1.2-1*

Equipment Name*

Tag No.*

First-stage ADS Motor-operated Valve (MOV)

RCS-PL-V001A First-stage ADS MOV RCS-PL-V001B Second-stage ADS MOV RCS-PL-V002A Second-stage ADS MOV RCS-PL-V002B Third-stage ADS MOV RCS-PL-V003A Third-stage ADS MOV RCS-PL-V003B First-stage ADS Isolation MOV RCS-PL-V011A First-stage ADS Isolation MOV RCS-PL-V011B Second-stage ADS Isolation MOV RCS-PL-V012A Second-stage ADS Isolation MOV RCS-PL-V012B Third-stage ADS Isolation MOV RCS-PL-V013A Third-stage ADS Isolation MOV RCS-PL-V013B Fourth-stage ADS MOV RCS-PL-V014A Fourth-stage ADS MOV RCS-PL-V014B Fourth-stage ADS MOV RCS-PL-V014C Fourth-stage ADS MOV RCS-PL-V014D Table 2.2.1-1*

Equipment Name*

Tag No.*

Component Cooling Water System (CCS) Containment Isolation Motor-operated Valve (MOV) Inlet Line Outside Reactor Containment (ORC)

CCS-PL-V200 CCS Containment Isolation MOV Outlet Line IRC CCS-PL-V207 CCS Containment Isolation MOV Outlet Line ORC CCS-PL-V208 SFS Discharge Line Containment Isolation MOV ORC SFS-PL-V038 SFS Suction Line Containment Isolation MOV IRC SFS-PL-V034 SFS Suction Line Containment Isolation MOV ORC SFS-PL-V035 Vacuum Relief Containment Isolation A MOV ORC VFS-PL-V800A Vacuum Relief Containment Isolation B MOV ORC VFS-PL-V800B Table 2.2.2-1*

Component Name*

Tag No.*

PCCWST Isolation Valve MOV PCS-PL-V001C PCCWST Isolation Block MOV PCS-PL-V002A PCCWST Isolation Block MOV PCS-PL-V002B PCCWST Isolation Block MOV PCS-PL-V002C

• Excerpts from COL Tables 2.1.2-1, 2.2.1-1, and 2.2.2-1.

U.S. Nuclear Regulatory Commission ND-23-0447 Enclosure Page 5 of 6 Attachment A (Cont.)

Table 2.2.3-1*

Equipment Name*

Tag No.*

CMT A Inlet Isolation Motor-operated Valve PXS-PL-V002A CMT B Inlet Isolation Motor-operated Valve PXS-PL-V002B PRHR HX Inlet Isolation Motor-operated Valve PXS-PL-V101 Containment Recirculation A Isolation Motor-operated Valve PXS-PL-V117A Containment Recirculation B Isolation Motor-operated Valve PXS-PL-V117B Table 2.2.4-1*

Equipment Name*

Tag No.*

Power-operated Relief Valve Block Motor-operated Valve Steam Generator 01 SGS-PL-V027A Power-operated Relief Valve Block Motor-operated Valve Steam Generator 02 SGS-PL-V027B Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067A Startup Feedwater Isolation Motor-operated Valve SGS-PL-V067B Table 2.3.2-1*

Equipment Name*

Tag No.*

RCS Purification Motor-operated Isolation Valve CVS-PL-V001 RCS Purification Motor-operated Isolation Valve CVS-PL-V002 RCS Purification Motor-operated Isolation Valve CVS-PL-V003 CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V090 CVS Makeup Line Containment Isolation Motor-operated Valve CVS-PL-V091 Table 2.3.6-1*

Equipment Name*

Tag No.*

RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023

• Excerpts from COL Tables 2.2.3-1, 2.2.4-1, 2.3.2-1, and 2.3.6-1.

U.S. Nuclear Regulatory Commission ND-23-0447 Enclosure Page 6 of 6 Attachment A (Cont.)

Table 2.7.1-1*

Equipment Name*

Tag No.*

MCR Supply Air Isolation Valve VBS-PL-V186 MCR Supply Air Isolation Valve VBS-PL-V187 MCR Return Air Isolation Valve VBS-PL-V188 MCR Return Air Isolation Valve VBS-PL-V189 MCR Exhaust Air Isolation Valve VBS-PL-V190 MCR Exhaust Air Isolation Valve VBS-PL-V191 MCR SDS (Vent) Isolation Valve SDS-PL-V001 MCR SDS (Vent) Isolation Valve SDS-PL-V002

• Excerpt from COL Table 2.7.1-1.