ND-19-0672, Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.5.00.06 (Index Number 831)

Vogtie, Units 3 and 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.5.00.06 (Index Number 831)

ML19169A122
Person / Time
Site:	Vogtle
Issue date:	06/18/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-0672
Download: ML19169A122 (13)

Text

Michael J. Yox 7825 River Road hk.Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei JUN 1 8 2019 Docket Nos.: 52-025 52-026 ND-19-0672 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 3.5.00.06 [Index Number 8311 Ladles and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 12, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.5.00.06 [Index Number 831]

has not been completed greater than 225-days prior to Initial fuel load. The Enclosure describes the plan for completing this ITAAC. 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.

Mi Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.5.00.06 [Index Number 831]

MJY/PGUsfr

U.S. Nuclear Regulatory Commission ND-19-0672 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. R.G. West(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. J. B. Klecha Mr. G. Chick Mr. M. J. Vox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman 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. P. O'Bryan Mr. T. Fredette Mr. C. Weber Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0672 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani(w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan Mr. J. L. Coward Other Mr. J. E. Hesler, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0672 Enclosure Page 1 of 10 Southern Nuclear Operating Company ND-19-0672 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.5.00.06 [Index Number 831]

U.S. Nuclear Regulatory Commission ND-19-0672 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.

I nspections/Tests/Analvses 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 Completion Description Inspections are performed to verify the retrievability of the Vogtle Electric Generating Plant (VEGP) Unit 3 and 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-19-0672 Enclosure Page 3 of 10 Safety-related disolavs identified in Table 3.5-1 can be retrieved in the MGR.

The inspection is performed in accordance with the Unit 3 and Unit 4 component test package work orders(References 1 and 2)for radiation monitor component indication verifications, and visually confirms that when each of the safety-related displays identified in Attachment A is summoned at the MGR Protection and Safety Monitoring System (PMS)Visual Display Units (VDUs), the summoned safety-related display appears on the PMS VDU.

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

The inspection confirms that the safety-related displays of the parameters identified in GOL Appendix G Table 3.5-1 can be retrieved in the MGR.

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

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

Walkdown inspections of the as-built radiation monitoring equipment are conducted after completion of construction to confirm that the process radiation monitors listed in Attachment B exist in the locations indicated in Attachment B. Procedure XXX (Reference 3) is used to conduct the inspections, which involve 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 is 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 results of the inspections are documented in Reference 3.

The inspections confirm that the process radiation monitors listed in GOL Appendix G Table 3.5-2 exist and are present in the component locations listed in GOL Appendix G Table 3.5-7.

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

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

Walkdown inspections of the as-built radiation monitoring equipment are conducted after completion of construction to confirm that the effluent radiation monitors listed in Attachment G exist in the locations indicated in Attachment G. Procedure XXX (Reference 3) is used to conduct the inspections, which involve 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 is 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 results of the inspections are documented in Reference 3.

The inspections confirm that the effluent radiation monitors listed in GOL Appendix G Table 3.5-3 exist and are present in the component locations listed in GOL Appendix G Table 3.5-7.

U.S. Nuclear Regulatory Commission ND-19-0672 Enclosure Page 4 of 10 Each of the Fairborne radiationi monitors listed in Table 3.5-4 exists.

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

Walkdown inspections of the as-built radiation monitoring equipment are conducted after completion of construction to confirm that the airborne radiation monitors listed in Attachment D exist in the locations indicated in Attachment D. Procedure XXX (Reference 3) is used to conduct the inspections, which involve 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 is 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 results of the inspections are documented in Reference 3.

The inspections confirm that the airborne radiation monitors listed in COL Appendix 0 Table 3.5-4 exist and are present in the component locations listed in COL Appendix C Table 3.5-7.

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

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

Walkdown inspections of the as-built radiation monitoring equipment are conducted after completion of construction to confirm that the area radiation monitors listed in Attachment E exist in the locations indicated in Attachment E. Procedure XXX (Reference 3) is used to conduct the inspections, which involve 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 is 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 results of the inspections are documented in Reference 3.

The inspections confirm that the area radiation monitors listed in COL Appendix 0 Table 3.5-5 exist and are present in the component locations listed in COL Appendix C Table 3.5-7.

Together,these inspections, tests, and reports(References 1, 2, and 3) 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.

U.S. Nuclear Regulatory Commission ND-19-0672 Enclosure Page 5 of 10 References 1, 2, and 3 are available for NRG inspection as part of the ITAAC 3.5.00.06 Completion Package (References 4 and 5).

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 reievant ITAAC findings associated with this ITAAC.

References favaiiabie for NRG inspection)

1. SNC922080,"RMS PMS Indication Verifications- ITAAC: SV3-3.5.00.06 Item 4"

2. SNCYYYYYY,"RMS PMS Indication Verifications- ITAAC: SV4-3.5.00.06 Item 4"

3. Procedure XXX,"ITAAC 3.5.00.06(831) Inspection of As-Built Radiation Monitoring Equipment"

4. 3.5.00.06-U3-CP-Rev0, ITAAC Completion Package

5. 3.5.00.06-U4-CP-Rev0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0672 Enclosure Page 6 of 10 Attachment A MGR 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 MGR Radiation Monitoring Package VBS-JS01A Yes MGR Radiation Monitoring Package VBS-JS01B Yes Note:

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

Excerpt from GOL Appendix G Table 3.5-1

U.S. Nuclear Regulatory Commission ND-19-0672 Enclosure Page 7 of 10 Attachment B Process Radiation Monitors Component Equipment List* Equipment No.*

Location*

Steam Generator Slowdown SDS-RE010 Turbine Suilding Steam Generator Slowdown SDS-RE011 Turbine Suilding Component Cooling Water CCS-RE001 Turbine Suilding Main Steam Line<^> SGS-RY026 Auxiliary Suilding Main Steam Line<^' SGS-RY027 Auxiliary Suilding Service Water Slowdown SWS-RE008 Turbine Suilding Primary Sampling System Liquid Sample PSS-RE050 Auxiliary Suilding Primary Sampling System Gaseous Sample PSS-RE052 Auxiliary Suilding Containment Air Filtration Exhaust VFS-RE001 Annex Suilding Gaseous Radwaste Discharge WGS-RE017 Auxiliary Suilding 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-19-0672 Enclosure Page 8 of 10 Attachment 0 Effluent Radiation Monitors Component Equipment List* Equipment No.*

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^^' 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-19-0672 Enclosure Page 9 of 10 Attachment D Airborne Radiation Monitors Component Equipment List* Equipment No.*

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 VHS-RE001 Annex Building Radiation Monitor 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-19-0672 Enclosure Page 10 of 10 Attachment E Area Radiation Monitors Component Equipment List* Equipment No.*

Location*

Primary Sampling Room RMS-RE008 Auxiliary Building Containment Area - Upper Personnel Hatch RMS-RE009 Auxiliary Building Operating Deck 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 RMS-RE013 Auxiliary Building Building Loading Bay)

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 RMS-RE021 Auxiliary Building Maintenance Level Excerpt from COL Appendix C Table 3.5-5 and Table 3.5-7