ND-22-0824, ITAAC Closure Notification on Completion of ITAAC 3.5.00.01.i (Index Number 823)

ITAAC Closure Notification on Completion of ITAAC 3.5.00.01.i (Index Number 823)

ML23151A730
Person / Time
Site:	Vogtle
Issue date:	05/31/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ND-22-0824, ITAAC 3.5.00.01.i
Download: ML23151A730 (1)

Text

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

May 31, 2023

Docket No.: 52-026

ND-22-0824 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 3.5.00.01.i [Index Number 823]

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 3.5.00.01.i [Index Number 823] to demonstrate that the Radiation Monitoring System (RMS) equipment identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 3.5-1 is designed and constructed in accordance with applicable requirements.

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 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 3.5.00.01.i [Index Number 823]

JMC/JRB/sfr

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cc: Regional Administrator, Region II 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-22-0824 Enclosure

Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 3.5.00.01.i [Index Number 823]

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ITAAC Statement

Design Commitment

1. The seismic Category I equipment identified in Table 3.5-1 can withstand seismic design basis loads without loss of safety function.

2. The Class 1E equipment identified in Table 3.5-1 as being qualified for a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

Inspections, Tests, Analyses

i) Inspection will be performed to verify that the seismic Category I equipment identified in Table 3.5-1 is located on the Nuclear Island.

ii) Type tests, analyses, or a combination of type tests and analyses of seismic Category I equipment will be performed.

iii) Inspection will be performed for the existence of a report verifying that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

i) Type tests, analyses, or a combination of type tests and analyses will be performed on Class 1E equipment located in a harsh environment.

ii) Inspection will be performed of the as-built Class 1E equipment and the associated wiring, cables, and terminations located in a harsh environment.

Acceptance Criteria

i) The seismic Category I equipment identified in Table 3.5-1 is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

i) A report exists and concludes that Class 1E equipment identified in Table 3.5-1 as being located in a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 3.5-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

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ITAAC Determination Basis

This ITAAC requires that inspections, tests, and analyses be performed and documented to ensure the Radiation Monitoring System (RMS) equipment identified as seismic Category I or Class 1E in the Combined License (COL) Appendix C, Table 3.5-1 (the Table) is designed and constructed in accordance with applicable requirements.

i) The seismic Category I equipment identified in Table 3.5-1 is located on the Nuclear Island.

To assure that seismic Category I equipment can withstand seismic design basis loads without loss of safety function, all the equipment in the Table is designed to be located on the seismic Category I Nuclear Island. In accordance with Equipment Qualification (EQ) ITAAC As-built Walkdown Guideline and the EQ ITAAC As-built Installation Documentation Guideline (References 1 and 2), an inspection was conducted of the RMS to confirm the satisfactory installation of the seismically qualified equipment. The inspection includes verification of equipment make/model/serial number and verification of equipment location (Building, Elevation, Room). The EQ As-Built Reconciliation Report (EQRR) (Reference 3) identified in Attachment A documents the results of the inspection and concludes that the seismic Category I equipment is located on the Nuclear Island.

ii) A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

Seismic Category I equipment in the Table requires type tests and/or analyses to demonstrate structural integrity and operability. Safety-related (Class 1E) electrical equipment in the Table is seismically qualified by type testing combined with analysis in accordance with Institute of Electrical and Electronics Engineers (IEEE) Standard 344 -1987 (Reference 4). This equipment includes safety-related (Class 1E) field sensors. The specific qualification method (i.e., type testing, analysis, or combination) used for each piece of equipment in the Table is identified in Attachment A. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the Updated Final Safety Analysis Report (UFSAR) Appendix 3D (Reference 5). The EQ Reports (Reference 6) identified in Attachment A contain applicable test reports and associated documentation and conclude th at the seismic Category I equipment can withstand seismic design basis loads without loss of safety function.

iii) A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions.

An inspection (References 1 and 2) was conducted to confirm the satisfactory installation of the seismically qualified equipment in the Table. The inspection verifies the equipment make/model/serial number, as-designed equipment mounting orientation, ancho rage and clearances, and electrical and other interfaces. The documentation of installed configuration of seismically qualified equipment includes photographs and/or sketches/drawings of equipment/mounting/interfaces.

As part of the seismic qualification program, consideration was given to the definition of the clearances needed around the equipment mounted in the plant to permit the equipment to move during a postulated seismic event without causing impact between adjacent pieces of safety -

related equipment. When required, seismic testing by measuring the maximum dynamic relative displacement of the top and bottom of the equipment was performed. EQ Reports (Reference 6)

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identify the equipment mounting employed for qualification and establish interface requirements for assuring that subsequent in-plant installation does not degrade the established qualification.

Interface requirements are defined based on the test configuration and other design requirements.

Attachment A identifies the EQRR (Reference 3) completed to verify that the as-built seismic Category I equipment listed in the Table, including anchorage, are seismically bounded by the tested or analyzed conditions, IEEE Standard 344-1987 (Reference 4) and NRC Regulatory Guide (RG) 1.100 (Reference 7).

i) A report exists and concludes that Class 1E equipment identified in Table 3.5-1 as being located in a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

The harsh environment Class 1E equipment in the Table is qualified by type testing and/or analyses. Class 1E electrical equipment type testing is performed in accordance with IEEE Standard 323-1974 (Reference 8) and RG 1.89 (Reference 9) to meet the requirements of 10 CFR 50.49. Type testing of safety-related equipment meets the requirements of 10 CFR Part 50, Appendix A, General Design Criterion 4. Attachment A identifies the EQ p rogram and specific qualification method for each piece of safety-related Class 1E electrical equipment located in a harsh environment. Additional information about the methods used to qualify AP1000 safety-related equipment is provided in the UFSAR Append ix 3D (Reference 5). EQ Reports (Reference 6) identified in Attachment A contain applicable test reports and associated documentation and conclude that the equipment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function.

ii) A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 3.5-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

An inspection (References 1 and 2) was conducted of the RMS to confirm the satisfactory installation of the Class 1E equipment in the Table. The inspection verified the equipment location, make/model/serial number, as -designed equipment mounting, wiring, cables, and terminations, and confirms that the environmental conditions for the zone (Attachment A) in which the equipment is mounted are bounded by the tested and/or analyzed conditions. It also documents the installed configuration with photographs or sketches/drawings of equipment mounting and connections. The EQRR (Reference 3) identified in Attachment A documents this inspection and concludes that the as-built harsh environment Class 1E equipment and the associated wiring, cables, and terminations are bounded by the qualified configuration and IEEE Standard 323-1974 (Reference 8).

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Together, these reports (References 3 and 6) provide evidence that the ITAAC Acceptance Criteria requirements are met:

• The seismic Category I equipment identified in Table 3.5-1 is located on the Nuclear Island;

• A report exists and concludes that the seismic Category I equipment can withstand seismic design basis loads without loss of safety function;

• A report exists and concludes that the as-built equipment including anchorage is seismically bounded by the tested or analyzed conditions;

• A report exists and concludes that Class 1E equipment identified in Table 3.5-1 as being located in a harsh environment can withstand the environmental conditions that would exist before, during, and following a design basis accident without loss of safety function for the time required to perform the safety function; and

• A report exists and concludes that the as-built Class 1E equipment and the associated wiring, cables, and terminations identified in Table 3.5-1 as being qualified for a harsh environment are bounded by type tests, analyses, or a combination of type tests and analyses.

References 3 and 6 are available for NRC inspection as part of the Unit 4 ITAAC 3.5.00.01.i Completion Package (Reference 10).

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 finding review, which included now-consolidated ITAAC Indexes 824, 825, 826, and 827, found no relevant ITAAC findings associated with this ITAAC.

The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.5.00.01.i (Reference 10) and is available for NRC review.

ITAAC Completion Statement

Based on the above information, SNC hereby notifies the NRC that ITAAC 3.5.00.01.i was performed for VEGP Unit 4 and that the prescribed acceptance criteria are met.

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

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References (available for NRC inspection)

1. ND-RA-001-014, EQ ITAAC As-built Walkdown Guideline, Version 3.1

2. ND-RA-001-016, EQ ITAAC As-built Installation Documentation Guideline, Version 1.0

3. EQ As-Built Reconciliation Report (EQRR) as identified in Attachment A for Unit 4

4. IEEE Standard 344-1987, IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations

5. Vogtle 3&4 Updated Final Safety Analysis Report Appendix 3D, Methodology for Qualifying AP1000 Safety-Related Electrical and Mechanical Equipment

6. Equipment Qualification (EQ) Reports as identified in Attachment A

7. Regulatory Guide 1.100, Rev. 2, "Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants"

8. IEEE Standard 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations

9. Regulatory Guide 1.89, Rev 1, Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants

10. 3.5.00.01.i-U4-CP-Rev0, ITAAC Completion Package

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Attachment A

System: Radiation Monitoring System (RMS)

Seismic Class 1E/ Qual. Envir. Envir Qual Type of Equipment Name+ Tag No.+ For Harsh EQ Reports As-Built EQRR Cat. I+ Envir.+ Zone1 Program2 Qual.

Containment High Range Type SV4-RMS-VBR-001 / 3.5.00.01.i-U4-EQRR-Monitor PXS-RE160 Yes Yes/Yes 1 E

• S Testing & SV4-RMS-VBR-002 PCD001 Analysis

Containment High Range Type SV4-RMS-VBR-001 / 3.5.00.01.i-U4-EQRR-Monitor PXS-RE161 Yes Yes/Yes 1 E

• S Testing & SV4-RMS-VBR-002 PCD001 Analysis

Containment High Range Type SV4-RMS-VBR-001 / 3.5.00.01.i-U4-EQRR-Monitor PXS-RE162 Yes Yes/Yes 1 E

• S Testing & SV4-RMS-VBR-002 PCD001 Analysis

Containment High Range Type SV4-RMS-VBR-001 / 3.5.00.01.i-U4-EQRR-Monitor PXS-RE163 Yes Yes/Yes 1 E

• S Testing & SV4-RMS-VBR-002 PCD001 Analysis

MCR Radiation Type SV4-RMS-VBR-001 / 3.5.00.01.i-U4-EQRR-Monitoring Package A 4 VBS-JS01A Yes Yes/No NA NA Testing & SV4-RMS-VBR-002 PCD001 Analysis

MCR Radiation Type SV4-RMS-VBR-003 / 3.5.00.01.i-U4-EQRR-4 VBS-JS01B Yes Yes/No NA NA Testing &

Monitoring Package B Analysis SV4-RMS-VBR-004 PCD001

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Seismic Class 1E/ Qual. Envir. Envir Qual Type of Equipment Name+ Tag No.+ Cat. I+ For Harsh Zone1 Program2 Qual. EQ Reports As-Built EQRR Envir.+

Containment Atmosphere Type SV4-RMS-VBR-003 / 3.5.00.01.i-U4-EQRR-Monitor (Gaseous) PSS-RE026 Yes No/No NA NA Testing & SV4-RMS-VBR-004 PCD001 Analysis

Containment Atmosphere Type Monitor (particulate, for PSS-RE027 Yes No/No NA NA Testing & SV4-RMS-VBR-003 / 3.5.00.01.i-U4-EQRR-RCS pressure boundary Analysis SV4-RMS-VBR-004 PCD001 leakage detection)

Notes:

+ Excerpt from COL Appendix C Table 3.5-1

1. See Table 3D.5-1 of UFSAR

2. E = Electrical Equipment Program S = Qualified for submergence or operation with spray

• = Harsh Environment

4. Each MCR Radiation Monitoring Package includes particulate, iodine and gaseous radiation monitors.