ND-23-0603, ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831)

ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831)

ML23196A008
Person / Time
Site:	Vogtle
Issue date:	07/15/2023
From:	Coleman J Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
ITAAC 3.5.00.06, ND-23-0603
Download: ML23196A008 (1)

Text

Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel July 15, 2023 Docket No.:

52-026 ND-23-0603 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 Item 3.5.00.06 [Index Number 831]

Ladies and Gentlemen:

In accordance with10 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 3.5.00.06 [Index Number 831].

This ITAAC verified that the safety-related displays identified in Combined License (COL), Appendix C, Table 3.5-1 can be retrieved in the Main Control Room (MCR) and that each of the process, effluent, airborne, and area radiation monitors listed in Tables 3.5-2 through 3.5-5 exist in the locations identified in Table 3.5-7. 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 Item 3.5.00.06 [Index Number 831]

JMC/CSS/sfr

U.S. Nuclear Regulatory Commission ND-23-0603 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-23-0603 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-23-0603 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC Item 3.5.00.06 [Index Number 831]

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 2 of 10 ITAAC Statement Design Commitment

4. Safety-related displays identified in Table 3.5-1 can be retrieved in the MCR.

5. The process radiation monitors listed in Table 3.5-2 are provided.

6. The effluent radiation monitors listed in Table 3.5-3 are provided.

7. The airborne radiation monitors listed in Table 3.5-4 are provided.

8. The area radiation monitors listed in Table 3.5-5 are provided.

Inspections/Tests/Analyses Inspection will be performed for retrievability of the displays in the MCR.

Inspection for the existence of the monitors will be performed.

Inspection for the existence of the monitors will be performed.

Inspection for the existence of the monitors will be performed.

Inspection for the existence of the monitors will be performed.

Acceptance Criteria Safety-related displays identified in Table 3.5-1 can be retrieved in the MCR.

Each of the monitors listed in Table 3.5-2 exists.

Each of the monitors listed in Table 3.5-3 exists.

Each of the monitors listed in Table 3.5-4 exists.

Each of the monitors listed in Table 3.5-5 exists.

ITAAC Determination Basis Inspections were performed to verify the retrievability of the Vogtle Electric Generating Plant (VEGP) Unit 4 Radiation Monitoring safety-related displays in the main control room (MCR), as identified in Combined License (COL) Appendix C Table 3.5-1 (Attachment A), and that the process radiation monitors, effluent radiation monitors, airborne radiation monitors, and area radiation monitors listed in Tables 3.5-2 (Attachment B) through 3.5-5 (Attachment E) exist and are in the locations identified in Table 3.5-7 (Attachment B through Attachment E).

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 3 of 10 Safety-related displays identified in Table 3.5-1 can be retrieved in the MCR.

The inspection was performed as documented in SV4-RMS-ITR-801831 (Reference 1), for radiation monitor component indication verifications, and visually confirmed that when each of the safety-related displays identified in Attachment A was summoned at the MCR Protection and Safety Monitoring System (PMS) Visual Display Units (VDUs), the summoned safety-related display appeared on the PMS VDU.

Attachment A Note (1) states that each MCR Radiation Monitoring Package (VBS-JS01A and VBS-JS01B) includes particulate, iodine, and gaseous radiation monitors, so these displays were inspected individually.

The inspection confirmed that the safety-related displays of the parameters identified in COL Appendix C Table 3.5-1 can be retrieved in the MCR.

Each of the [process radiation] monitors listed in Table 3.5-2 exists.

An inspection of the as-built radiation monitoring equipment was performed to verify that the process radiation monitors listed in Attachment B are provided (installed).

Walkdown inspections of the as-built radiation monitoring equipment were conducted after completion of construction to confirm that the process radiation monitors listed in Attachment B exist in the locations indicated in Attachment B. Inspections were performed, as documented in Reference 2, which involved visual observations of the process radiation monitors and verification that the monitors are installed in their specified locations. The make and model and other nameplate data of the monitors were also inspected and compared to that specified in design documents to verify that the installed radiation monitors have the appropriate nominal detection ranges to provide indication of unusual radiological events.

The inspections confirmed that the process radiation monitors listed in COL Appendix C Table 3.5-2 exist and are present in the component locations listed in COL Appendix C Table 3.5-7.

Each of the [effluent radiation] monitors listed in Table 3.5-3 exists.

An inspection of the as-built radiation monitoring equipment was performed to verify that the effluent radiation monitors listed in ITAAC Attachment C are provided (installed).

Walkdown inspections of the as-built radiation monitoring equipment were conducted after completion of construction to confirm that the effluent radiation monitors listed in Attachment C exist in the locations indicated in Attachment C. Inspections were performed, as documented in Reference 2, which involved visual observations of the effluent radiation monitors and verification that the monitors are installed in their specified locations. The make and model and other nameplate data of the monitors were also inspected and compared to that specified in design documents to verify that the installed radiation monitors have the appropriate nominal detection ranges to provide indication of unusual radiological events.

The inspections confirmed that the effluent radiation monitors listed in COL Appendix C Table 3.5-3 exist and are present in the component locations listed in COL Appendix C Table 3.5-7.

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 4 of 10 Each of the [airborne radiation] monitors listed in Table 3.5-4 exists.

An inspection of the as-built radiation monitoring equipment was performed to verify that the airborne radiation monitors listed in Attachment D are provided (installed).

Walkdown inspections of the as-built radiation monitoring equipment were conducted after completion of construction to confirm that the airborne radiation monitors listed in Attachment D exist in the locations indicated in Attachment D. Inspections were performed, as documented in Reference 2, which involved visual observations of the airborne radiation monitors and verification that the monitors are installed in their specified locations. The make and model and other nameplate data of the monitors were also inspected and compared to that specified in design documents to verify that the installed radiation monitors have the appropriate nominal detection ranges to provide indication of unusual radiological events.

The inspections confirmed that the airborne radiation monitors listed in COL Appendix C Table 3.5-4 exist and are present in the component locations listed in COL Appendix C Table 3.5-7.

Each of the [area radiation] monitors listed in Table 3.5-5 exists.

An inspection of the as-built radiation monitoring equipment was performed to verify that the area radiation monitors listed Attachment E are provided (installed).

Walkdown inspections of the as-built radiation monitoring equipment were conducted after completion of construction to confirm that the area radiation monitors listed in Attachment E exist in the locations indicated in Attachment E. Inspections were performed, as documented in Reference 2, which involved visual observations of the area radiation monitors and verification that the monitors are installed in their specified locations. The make and model and other nameplate data of the monitors were also inspected and compared to that specified in design documents to verify that the installed radiation monitors have the appropriate nominal detection ranges to provide indication of unusual radiological events.

The inspections confirmed that the area radiation monitors listed in COL Appendix C Table 3.5-5 exist and are present in the component locations listed in COL Appendix C Table 3.5-7.

Together, these inspections (References 1 and 2) confirm that the ITAAC Acceptance Criteria requirements are met:

Safety-related displays identified in Table 3.5-1 can be retrieved in the MCR.

Each of the [process radiation] monitors listed in Table 3.5-2 exists.

Each of the [effluent radiation] monitors listed in Table 3.5-3 exists.

Each of the [airborne radiation] monitors listed in Table 3.5-4 exists.

Each of the [area radiation] monitors listed in Table 3.5-5 exists.

References 1 and 2 are available for NRC inspection as part of the ITAAC 3.5.00.06 Completion Package (Reference 3).

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 5 of 10 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 with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 3.5.00.06 Completion Package (Reference 3) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 3.5.00.06 was performed for VEGP Unit 4 and that the prescribed 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.

References (available for NRC inspection)

1. SV4-RMS-ITR-801831, Rev. 0, Unit 4 Recorded Results of Radiation Monitoring System MCR Safety-related Displays: ITAAC 3.5.00.06 Item 4

2. SV4-RMS-ITR-800831, Rev. 0, Unit 4 Recorded Results of RMS Effluent Monitors: ITAAC 3.5.00.06 Items 5-8

3. 3.5.00.06-U4-CP-Rev0, ITAAC Completion Package

4. NEI 08-01, Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 6 of 10 Attachment A MCR Radiation Monitor Displays Equipment Name*

Tag No.*

Safety-Related Display*

Containment High Range Monitor PXS-RE160 Yes Containment High Range Monitor PXS-RE161 Yes Containment High Range Monitor PXS-RE162 Yes Containment High Range Monitor PXS-RE163 Yes MCR Radiation Monitoring Package A(1)

VBS-JS01A Yes MCR Radiation Monitoring Package B(1)

VBS-JS01B Yes Note:

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

• Excerpt from COL Appendix C Table 3.5-1

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 7 of 10 Attachment B Process Radiation Monitors Equipment List*

Equipment No.*

Component Location*

Steam Generator Blowdown BDS-RE010 Turbine Building Steam Generator Blowdown BDS-RE011 Turbine Building Component Cooling Water CCS-RE001 Turbine Building Main Steam Line(1)

SGS-RY026 Auxiliary Building Main Steam Line(1)

SGS-RY027 Auxiliary Building Service Water Blowdown SWS-RE008 Turbine Building Primary Sampling System Liquid Sample PSS-RE050 Auxiliary Building Primary Sampling System Gaseous Sample PSS-RE052 Auxiliary Building Containment Air Filtration Exhaust VFS-RE001 Annex Building Gaseous Radwaste Discharge WGS-RE017 Auxiliary Building Note:

1. Each main steam line monitor includes a noble gas detector and primary-to-secondary side leak detector.

• Excerpt from COL Appendix C Table 3.5-2 and Table 3.5-7

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 8 of 10 Attachment C Effluent Radiation Monitors Equipment List*

Equipment No.*

Component Location*

Plant Vent (Normal Range Particulate)

VFS-RE101 Auxiliary Building Plant Vent (Normal Range Iodine)

VFS-RE102 Auxiliary Building Plant Vent (Normal Range Radiogas)

VFS-RE103 Auxiliary Building Plant Vent (Mid Range Radiogas)

VFS-RE104A Auxiliary Building Plant Vent (High Range Radiogas)

VFS-RE104B Auxiliary Building Turbine Island Vent(1)

TDS-RE001 Turbine Building Liquid Radwaste Discharge WLS-RE229 Radwaste Building Wastewater Discharge WWS-RE021 Turbine Building Note:

1. The turbine island vent includes a low and a high range detector.

• Excerpt from COL Appendix C Table 3.5-3 and Table 3.5-7

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 9 of 10 Attachment D Airborne Radiation Monitors Equipment List*

Equipment No.*

Component Location*

Fuel Handling Area Exhaust Radiation Monitor VAS-RE001 Auxiliary Building Auxiliary Building Exhaust Radiation Monitor VAS-RE002 Auxiliary Building Auxiliary Building Exhaust Radiation Monitor VAS-RE003 Auxiliary Building Annex Building Exhaust Radiation Monitor VAS-RE008 Annex Building Health Physics and Hot Machine Shop Exhaust Radiation Monitor VHS-RE001 Annex Building Radwaste Building Exhaust Radiation Monitor VRS-RE023 Radwaste Building

• Excerpt from COL Appendix C Table 3.5-4 and Table 3.5-7

U.S. Nuclear Regulatory Commission ND-23-0603 Enclosure Page 10 of 10 Attachment E Area Radiation Monitors Equipment List*

Equipment No.*

Component Location*

Primary Sampling Room RMS-RE008 Auxiliary Building Containment Area - Upper Personnel Hatch Operating Deck RMS-RE009 Auxiliary Building Main Control Room RMS-RE010 Auxiliary Building Chemistry Laboratory RMS-RE011 Auxiliary Building Fuel Handling Area 1 RMS-RE012 Auxiliary Building Rail Car Bay/Filter Storage Area (Auxiliary Building Loading Bay)

RMS-RE013 Auxiliary Building Liquid and Gaseous Radwaste Area RMS-RY014 Radwaste Building Control Support Area RMS-RE016 Annex Building Radwaste Building Mobile Systems Facility RMS-RE017 Radwaste Building Hot Machine Shop RMS-RE018 Annex Building Annex Staging and Storage Area RMS-RE019 Annex Building Fuel Handling Area 2 RMS-RE020 Auxiliary Building Containment Area - Lower Personnel Hatch Maintenance Level RMS-RE021 Auxiliary Building

• Excerpt from COL Appendix C Table 3.5-5 and Table 3.5-7