ND-19-0119, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule

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Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule
ML19039A264
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 02/08/2019
From: Klecha J
Southern Nuclear Operating Co
To: Frederick Brown
Document Control Desk, Office of New Reactors
Shared Package
ML19039A261 List:
References
ND-19-0119
Download: ML19039A264 (25)
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Text

A Southern Nuclear Southern Nuclear Operating Company, inc.

I u n IXI L. ^^25 River Road Joseph B. Klecha Waynesboro, GA 30830 Vice President, Site Operations /oe 848 ease tei Plant Vogtle 3&4 jbklecha@southernco.com February 8, 2019 I Docket Nos.: 52-025 ND-19-0119 52-026 U. 8. Nuclear Regulatory Commission ATTN: Documerjt Control Desk Washington, D. 0. 20555-0001 Mr. Fred Brown Director, Office of New Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 VoQtle Electric Generating Plant - Units 3 and 4 Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule Ladies and Gentlemen:

The U.S. Nuclear Regulatory Commission (NRC)issued Combined Licenses (COLs) NPF-91 and NPF-92 to Southern Nuclear Operating Company(SNC) pursuant to Title 10 of the Code of Federal Regulations {^0 CFR) Section 52.97, "Issuance of combined licenses," on February 10, 2012.

Two license conditions require SNC to submit, no later than twelve months after issuance of the COL, the following:

  • A schedule for implementation of the operational programs listed in the Final Safety Analysis Report Table 13.4-201, including the associated estimated date for initial loading of fuel (COL section 2.D.(11))
  • A schedule for implementation of the license conditions listed in COL section 2.D.(12)(f)1-9 In accordance with the license conditions, the schedule shall be updated every six months until twelve months before scheduled fuel loading, and every month thereafter until each license condition has been fully implemented. contains the updated schedule. This information is current as of February 5, 2019.

As is typical with a construction project, the schedule information is dynamic in nature.

SNC's COL Operational Programs and Other License Conditions Implementation Schedule contains confidential commercial information. Pursuant to 10 CFR 2.390, SNC requests that the

U.S. Nuclear Regulatory Commission ND-19-0119 Page 2 of 5 specified information be withheld from public disclosure. In support of this request for withholding, SNC has attached to this letter the following documents:

Enclosure 1 contains an Affidavit for withholding executed by SNC and prepared in accordance with 10 CFR 2.390, which specifies the confidential commercial information sought to be withheld and the basis on which the information may be withheld.

Enclosure 2 contains the public, redacted version of SNC's COL Operational Programs and Other License Conditions Implementation Schedule.

j Enclosure 3 contains the non-public, non-redacted version of SNC's COL Operationai Programs and Other License Conditions Implementation Schedule.

Enclosure 4 contains the public, redacted version of SNC's Preoperationai Test Procedure Completion Schedule.

' Enclosure 5 contains the non-pubiic, non-redaCted version of SNC's Preoperationai Test Procedure Completion Schedule.

Enclosure 6 contains a Confidential Commercial Information Notice.

SNC requests that Enclosure 3, COL Operational Programs and Other License Conditions Implementation Schedule, and Enclosure 5, Preoperationai Test Procedure Completion Schedule, be withheld from public disclosure under 10 CFR 2.390. The redacted versions in Enclosure 2 and Enclosure 4 are suitable for public disclosure.

This letter contains no regulatory commitments.

If you have any questions, please contact Michael Yox at(706)848-6459.

(Oath and Affirmation are provided on the following page.)

U.S. Nuclear Regulatory Commission ND-19-0119 Page 3 of 5 Mr. Joseph B. Klecha states that: he is the Vice President, Site Operations of Vogtie 3 & 4 of Southern Nuclear Operating Company; he is authorized to execute this oath on behalf of Southern Nuclear Operating Company; and to the best of his knowledge and belief, the facts set forth in this letter are true.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY Sincerely Joseph B. Klecha Vice President, Site Operations of Vogtie 3 & 4 JBK/LRG/SFR

>i\x ,.<<*

Sworn to and sutjscribed before me this day of. ^^2019

'CPS Notary Public:

13/'

' Auo""

My commission expires:

Enclosures

1. Affidavit for Withholding
2. Redacted COL Operational Programs and Other License Conditions Implementation Schedule
3. Non-Redacted COL Operational Programs and Other License Conditions Implementation Schedule {Withhold from Public Disclosure}
4. Redacted Preoperational Test Procedure Completion Schedule
5. Non-Redacted Preoperational Test Procedure Completion Schedule

{Withhold from Public Disclosure}

6. Confidential Commercial Information Notice

U.S. Nuclear Regulatory Commission ND-19-0119 Page 4 of 5 cc:

Southern Nuclear Operating Company / Georgia Power Company Mr. 8. E. Kuczynski (w/o enclosures)

Mr. D. G. Best(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. D. L. McKinney (w/o enclosures)

Mr. T. W.Yelverton (w/o enclosures)

Mr. B. H. Whitley '

Ms. C. A. Gayheart Mr. C. R. Pierce Ms. A. G. Aughtman Mr. D. L. Fulton Mr. M. J. Vox I Mr. 0. T. Defnall Mr. J. Tupik Mr. W. A. Sparkman Ms. A. C. Chamberlain Mr. 8. Leighty Mr. E. Riffle Ms. K. Roberts Document Services RTYPE: VND.LI.LOO File AR.01.02.06 Nuclear Reaulatorv Commission Mr. W.Jones (w/o enclosures)

Ms. J. Dixon-Herrity Mr. C. Patel Ms. J. M. Heisserer Mr. B. Kemker Mr. G. Khouri Ms. 8. Temple Mr. F. Brown Mr. C. J. Even Mr. A. Lerch Mr. 8. Walker State of Georgia Mr. R. Dunn

U.S. Nuclear Regulatory Commission ND-19-0119 Page 5 of 5 Qqlethorpe Power Corporation Mr. M. W. Price (w/o enclosures 3&5)

Ms. A. Whaley (w/o enclosures 3&5)

Municipal Electric Authority of Georoia Mr. J. E. Fuller (w/o enclosures 3&5)

Mr. S. M. Jackson (w/o enclosures 3&5)

Dalton Utilities l Mr. T. Bundros(w/o enclosures 3&5)

Westinohouse Electric Company. LLC Mr. L. Oriani (w/o enclosures)

T. Rubenstein (w/o enclosures)

Mr. M. Corletti '

Mr. M. L. Clyde Mr. D. Hawkins Mr. J. Coward Other Mr. S. W. Kline, Bechtel Power Corporation (w/o enclosures 3&5)

Ms. L. A. Matis, Tetra Tech NUS, Inc.(w/o enclosures 3&5)

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.(w/o enclosures 3&5)

Mr. S. Roetger, Georgia Public Service Commission (w/o enclosures 3&5)

Ms. 8. W. Kernizan, Georgia Public Service Commission (w/o enclosures 3&5)

Mr. K. C. Greene, Troutman Sanders(w/o enclosures 3&5)

Mr. S. Blanton, Balch Bingham NDDocumentinBox@duke-energy.com, Duke Energy (w/o enclosures 3&5)

Mr. S. Franzone, Florida Power & Light (w/o enclosures 3&5)

Southern Nuclear Operating Company ND-19-0119 I

Enclosure 1 Affidavit for Withholding Prepared in Accordance with 10 CFR 2.390 for Southern Nuclear Operating Company (This Enclosure consists of 3 pages, including this cover page)

AFFIDAVIT Before me, the undersigned authority, personally appeared Joseph 8. Klecha who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Southern Nuclear Operating Company, and that the statements of fact set forth in this Affidavit are true amicorrect to the best of his knowledge, information, and belief:

Joseph B. Klecha SWORN to and SUBSCRIBED before me this ^ 0 day day ofof W\o[MJUX2019 in, County X

  • t ** 4, V/f.-O Notary Public: ./A My Commission Expires:

STATES THE AFFIANT:

1. My name is Joseph B. Klecha, and I am over the age of 18. My office is located in Burke County, Georgia. I am employed by Southern Nuclear Operating Company ("SNC") as the Vice President, Site Operations of Vogtle 3&4. I am authorized to make this affidavit on behalf of SNC.
2. I have personal knowledge of the criteria and procedures used by SNC to designate information as trade secrets, privileged or as confidential commercial or financial information.

Page 2 of 3

3. In accordance with 10 C.F.R. 2.390, I am making this Affidavit to support SNC's request for withhoiding, contained in the letter accompanying this Affidavit. The specific information to be withheld is contained on pages 1 - 6 of Enclosure 3 (COL Operational Programs and Other License Conditions Implementation Schedule) and pages 1 - 9 of (Preoperational Test Procedure Completion Schedule).

I 4. The information is sought to be withheld lunder 10 C.F.R. 2.390(a)(4), as it is confidential commercial information. In support of this request for withholding and pursuant to 10 C.F.R. 2.390(b)(4), I state the foiiowing:

i. SNC has heid the information in confidence.

ii. This information is of a type customariiy held in confidence by SNC.

iii. This information is being transmitted to the NRC in confidence.

iv. This information is not avaiiable in public sources.

V. The public disciosure of the information sought to be withheid is likeiy to cause substantial harm to SNC's competitive position. The information sought to be withheid contains aspects of SNC's deveiopment plans, the release of which wiil iikely cause harm by allowing other entities to gain a competitive advantage through prior knowiedge of SNC's construction and procurement pians.

FURTHER AFFIANT SAITH NOT.

Page 3 of 3

Southern Nuclear Operating Companyl ND-19-0119 Enclosure 2 Redacted COL Operational Programs and Other License Conditions Implementation Schedule (This Enclosure consists of 6 pages, Including this cover page)

Enclosure 2 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Combined License(COL)Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Program Name implementation Date FSAR Reference 02.D.nil Unit 3 Initial Fuel Load [ ]

N/A 02.0.(11)

Unit 4 Initial Fuel Load [ ]

N/A 02.0.(11)

Unit 3 Inservice Inspection L ]

Table 13.4-201 Item 1 02.0.(11)

Unit 4 Inservice Inspection [ ]

Table 13.4-201 Item 1 02.0.(11)

Inservice Testing [ ]

Table 13.4-201 Item 2 02.0.(10)(a) and 02.0.(11)

Environmental Qualification [ ]

Table 13.4-201 Item 3 02.0.(11)

Unit 3 Preservice Inspection [ ]

Table 13.4-201 Item 4 02.0.(11)

Unit 4 Preservice Inspection [ ]

Table 13.4-201 Item 4 02.0.(10)(b) and 02.0.(11)

Reactor Vessel Material Surveillance Table 13.4-201 Item 5 02.0.(10)(c) and 02.0.(11)

Preservice Testing [ ]

Table 13.4-201 Item 6 02.0.(10)(d) and 02.0.(11)

Containment Leakage Rate Testing [ ]

Table 13.4-201 Item 7 02.0.(10)(e)1. and 02.0.(11) Fire Protection - Oesignated Storage Areas [ ]

Table 13.4-201 Item 8 (per RG 1.189) 02.0.(10)(e)2. and 02.0.(11) Fire Protection - New Fuel Areas (per RG

^ J Table 13.4-201 Item 8 1.189) 02.0.(10)(e)3. and 02.0.(11)

Fire Protection - All other features [ ]

Table 13.4-201 Item 8 02.0.(10)(f) and 02.0.(11)

Radiological Effluent Technical [ ]

Table 13.4-201 Item 9 Specifications/Standard Radiological Effluent Controls 02.0.(10)(a) and 02.0.(11)

Offsite Dose Calculation Manual [ ]

Table 13.4-201 Item 9 Page 2 of6

Enclosure 2 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Combined License ICOL)Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Program Name Implementation Date FSAR Reference 02.D.(10)fh) and02.D.nU Radiological Environmental Monitoring [ ]

Table 13.4-201 Item 9 02.D.(10)m and 02.D.ni1 Process Control [ ]

Table 13.4-201 Item 9 02.0.(101(111. and 02.0.(111 Radiation Protection Program: Prior to Initial [ ]

Table 13.4-201 Item 10 Receipt of Byproduct, Source, or Special Nuclear Materials 02.0.(101(112. and 02.0.(111 Radiation Protection Program: Prior to Receipt _ [ ]

Table 13.4-201 Item 10 of Fuel Onsite 02.0.(101(113. and 02.0.(111 Radiation Protection Program: Prior to Initial [ ]

Table 13.4-201 Item 10 Fuel Load 02.0.(101(114. and 02.0.(111 Radiation Protection Program: Prior to [ ]

Table 13.4-201 Item 10 Shipment of Radioactive Waste 02.0.(111 Non-Licensed Plant Staff Training (non- [ ]

Table 13.4-201 Item 11 radioactivel 02.0.(111 Non-Licensed Plant Staff Training (portions Table 13.4-201 Item 11 applicable to radioactive materiall 02.0.(1 OKkl and 02.0.(111 Reactor Operator Training [ ]

Table 13.4-201 Item 12 02.0.(111 Reactor Operator Requalification [ ]

Table 13.4-201 Item 13 02.0.(111 Unit 3 Emergency Planning: Full Participation [ ]

Table 13.4-201 Item 14 Exercise 02.0.(111 Unit 3 Emergency Planning: Onsite Exercise [ ]

Table 13.4-201 Item 14 02.0.(111 Unit 4 Emergency Planning: Full Participation [ ]

Table 13.4-201 Item 14 Exercise 02.0.(111 Unit 4 Emergency Planning: Onsite Exercise

_ [ ]

Table 13.4-201 Item 14 02.0.(111 Emergency Planning: Detailed Implementing [ ]

Table 13.4-201 Item 14 Procedures for Emergency Plan Physical Protection Program (for special 02.0.(1 OKol and 02.0.(111 nuclear material before Protected Area is [ ]

Table 13.4-201 Item 15 operationall Page 3 of6

Enclosure 2 to ND-19-0119 Yogtie Electric Generating Plant- Units 3 and 4 Combined License tCOLl Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Program Name Implementation Date FSAR Reference 02.D.(1U [ ]

Physical Security Program Table 13.4-201 Item 15 02.D.ni) [ ]

Safeguards Contingency Program Table 13.4-201 Item 15 02.D.(111 [ ]

Security Training and Qualification Program Table 13.4-201 Item 15 02.D.(111 [ ]

Quality Assurance Table 13.4-201 Item 16 02.D.ni1 [ ]

Maintenance Rule Table 13.4-201 Item 17 02.D.noim and02.D.ni1 MOV Testing _ [ ]

Table 13.4-201 Item 18 02.D.(10)(m)1.and 02.D.(111 [ ]

Initial Test Program - Component Table 13.4-201 Item 19 02.D.(101(m12. and 02.D.ni1 [ ]

Initial Test Program - Pre-Qperational Table 13.4-201 Item 19 02.D.n0Km13. and 02.D.f111 [ ]

Initial Test Program - Startup Table 13.4-201 Item 19 02.D.ni) FFD for Construction Workers and First-Line Table 13.4-201 Item 20 Supervisors 02.D.(111 FFD for Construction Management and Table 13.4-201 Item 20 Oversight Personnel 02.D.(11)

FFD for Security Personnel(WECTEC)

Table 13.4-201 Item 20 02.D.(111 [ ]

FFD for Security Personnel(SNC)

Table 13.4-201 Item 20 02.D.(11) [ ]

FFD for FFD personnel Table 13.4-201 Item 20 02.D.ni1 [ ]

FFD for TSC and EOF personnel Table 13.4-201 Item 20 02.D.(111 [ ]

FFD for Operations Table 13.4-201 Item 20 02.D.ni) [ ]

Cyber Security Table 13.4-201 Item 21 Page 4 of6

Enclosure 2 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Combined License tCOLl Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Program Name Implementation Date FSAR Reference 02.0.(1 OUn) and 02.0.(111 Special Nuclear Material Control and [ ]

Table 13.4-201 Item 22 Accounting Construction inspection procedures lor steei [ ]

concrete composite construction activities lor 02.0.(121(f11.

seismic Category 1 nuclear island structural Section 3.8.4.8 modules lor minimum required reinforcement, steel plate thickness, and concrete thickness.

Construction inspection procedures for steel [ ]

concrete composite construction activities for 02.0.(121(f11.

seismic Category 1 shield building moduies for Section 3.8.4.8 minimum required reinforcement, steel plate thickness, and concrete thickness.

02.0.(121(f12. Spent Fuel Rack Metamic Coupon Monitoring- [ ]

N/A Program 02.0.(121(f13. Flow Accelerated Corrosion Program [ ]

N/A (including construction phase) 02.0.(121(114.

Turbine Maintenance and Inspection Program [ ]

Section 10.2.3.6 Availability ol documented instrumentation [ ]

02.0.(121(115.

uncertainties to calculate a power calorimetric N/A uncertainty Availability ol administrative controls to [. ]

02.0.(121(116. implement maintenance and contingency N/A activities related to the power calorimetric uncertainty instrumentation 02.0.(121(117. Site-specilic severe accident management [ ]

N/A guidelines The operational and programmatic elements [ ]

ol the mitigative strategies for responding to 02.0.(121(118.

circumstances associated with the loss ol N/A large areas ol the plant due to explosions or lire 02.0.(121(119. [ ]

ITP administrative manual procedures Section 14.2.3 Page 5 of6

Enclosure 2 to ND-19-0119 Vogtle Electric Generating Plant- Units 3^and 4 Combined License fCOU Operational Programs and Other License Conditions Implementation Schedule Redacted Version COL Reference Program Name implementation Date FSAR Reference 02.D.(12Uf)9. See Enclosure 4 Preoperational testing procedures Section 14.2.3 02.D.(12)(f)9. [ ]

Startup testing procedures Section 14.2.3 Page 6 of6

Southern Nuclear Operating Company ND-19-0119 Enclosure 4 l Redacted Preoperatlonal Test Procedure Completion Schedule (This Enclosure consists of 9 pages, inciuding this cover page)

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-PWS-ITPP-502 Building 315 Potable Water System [ ]

3-WRS-ITPP-501 Radioactive Waste Drain System [ ]

3-VWS-ITPP-SOl Central Chilled vli/ater System l [ ]

3-VWS-ITPP-S02 Central Chilled Water System Precore Hot Functional [ ]

3-DDS-ITPP-SOl [ ]

Data Display and Processing System 3-DDS-ITPP-S02 [ ]

Integrated DCIS Performance 3-IDS-ITPP-SOl [ ]

Class IE DC and UPS System 3-IDS-ITPP-S03 Class IE DC and UPS System Low Voltage 3-DDS-ITPP-S20 Remote Shutdown Workstation 3-PGS-ITPP-SOl [ ]

Plant Gas System 3-PLS-ITPP-S06 [ ]

Control Rod Drive Mechanism Motor-Generator 3-PLS-ITPP-S07 [ ]

Control Rod Drive Mechanism Precore Hot Functional 3-PLS-ITPP-S20 [ ]

Digital Rod Position Indication 3-RXS-ITPP-SOl [ ]

Pre- and Post- Precore Hot Functional Inspection of Reactor Vessel Internals 3-RXS-ITPP-S02 [ ]

Reactor Vessel Internals Vibration 3-RXS-ITPP-S03 [ ]

Integrated Head Package (IHP) 3-SWS-ITPP-SOl [ ]

Service Water System 3-SWS-ITPP-S02 [ ]

Service Water System Precore Hot Functional Page 2 of9

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-EDS-ITPP-501 [ ]

Non-Class IE DC and UPS System 3-PMS-ITPP-502 [ ]

PMS Time Response 3-PMS-ITPP-503 PMS [ ]

Qualified Data Processing System l 3-PMS-ITPP-504 [ ]

PMS RT Actuation 3-PMS-ITPP-505 [ ]

PMS Nuclear Instrumentation System 3-PMS-ITPP-521 ' [ 1 PMS Logic 3-PMS-ITPP-522 [ ]

PMS Squib Valve Controller Performance 3-PMS-ITPP-523 [ ]

PMS Containment Pressure High-2 3-PMS-ITPP-524 PMS Cold Actuations 3-PMS-ITPP-526 [ ]

PMS MCR Isolation and Passive Containment Cooling System Actuation 3-WGS-ITPP-501 [ ]

Gaseous Radwaste System+D686 3-SFS-ITPP-S02 [ ]

Spent Fuel Pool Cooling System Flow Path 3-SFS-ITPP-503 [ ]

Spent Fuel Pool Cooling Loss of Large Area 3-WSS-ITPP-501 [ ]

Solid Radwaste System 3-ECS-ITPP-501 [ ]

6.9 kV Switchgear 3-ECS-ITPP-504 [ ]

Ancillary Diesel Generator 3-SDS-ITPP-501 [ ]

Sanitary Drainage System 3-CVS-ITPP-501 [ ]

Chemical and Volume Control System Page 3 of9

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-CVS-ITPP-502 [ ]

Chemical and Volume Control System Precore Hot Functional 3-PSS-ITPP-502 [ ]

Primary Sampling System Precore Hot Functional 3-PXS-ITPP-502 [ ]

PXS ACC Mapping Line ResistancelTest 3-PXS-ITPP-503 [ ]

Passive Core Cooling System Flow Testing with the RV Head Installed 3-PXS-ITPP-504 [ 1 Passive Core Cooling System Precore Hot Functional Test 3-PXS-ITPP-505 ' [ ]

Passive Core Cooling System Automatic Depressurlzatlon Precore Hot Functional 3-RNS-ITPP-501 [ ]

Normal Residual Heat Removal System 3-RNS-ITPP-502 [ ]

Normal Residual Heat Removal System Precore Hot Functional 3-WLS-ITPP-501 [ ]

Liquid Radwaste System 3-PXS-ITPP-506 [ ]

PXS CMT Mapping and Line Resistance Test 3-PXS-ITPP-507 [ ]

PXS IRWST Resistance Test 3-MHS-ITPP-501 [ ]

Nuclear Island Mechanical Handling System 3-SGS-ITPP-502 [ ]

Steam Generator System 3-SGS-ITPP-504 Steam Generator Hydrostatic [ ]

3-SMS-ITPP-501 [ ]

Special Monitoring System 3-SMS-ITPP-502 [ ]

Special Monitoring System Precore Hot Functional 3-DAS-ITPP-501 [ ]

Diverse Actuation System 3-TVS-ITPP-501 ( ]

Closed Circuit Television System Page 4 of9

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-CAS-ITPP-501 [ ]

Compressed and Instrument Air System 3-IIS-ITPP-501 [ ]

Incore instrumentation System 3-MSS-ITPP-501 [ ]

Main Steam System l 3-MSS-ITPP-502 [ ]

Main Steam System Precore Hot Functional 3-DWS-ITPP-501 [ ]

Demineralized Water Transfer and Storage System 3-CNS-ITPP-501 '

ILRT Containment System Leak Rate Test Type A 3-CNS-ITPP-502 [ ]

ILRT Containment System Leak Test Type B 3-CNS-ITPP-503 [ ]

ILRT Containment System Leak Test Type C 3-RCS-ITPP-503 [ ]

RCS Primary Hydrostatic 3-RCS-ITPP-504 [ ]

Pressurizer Pressure Level and Spray Precore Hot Functional 3-RCS-ITPP-505 [ ]

RCS Precore Hot Functional Instrumentation Calibration 3-RCS-ITPP-506 [ ]

Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional 3-CDS-ITPP-501 [ ]

Condensate System 3-RWS-ITPP-501 [ ]

Raw Water System 3-VLS-ITPP-501 [ 1 VLS Preoperational Test 3-VYS-ITPP-501 [ ]

Hot Water Heating System 3-VAS-ITPP-502 [ ]

Radiologically Controlled Area Ventilation System Precore Hot Functional 3-VAS-ITPP-501 [ ]

Radiologically Controlled Area Ventilation System Page 5 of9

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-CPS-ITPP-501 [ ]

Condensate Polishing System 3-WWS-ITPP-501 [ ]

Waste Water System 3-LOS-ITPP-501 [ ]

Main Turbine and Generator Lube Oil System l 3-SSS-ITPP-501 [ ]

Secondary Sampling System 3-SSS-ITPP-502 [ ]

Secondary Sampling System Precore Hot Functional 3-VXS-ITPP-501 [ ']

Annex/Auxiliary Building Nonradioactive Ventilation System 3-VES-ITPP-501 [ ]

Main Control Room Emergency Habitability System 3-CCS-ITPP-501 [ ]

Component Cooling Water System 3-CCS-ITPP-502 [ ]

Component Cooling Water System Precore Hot Functional 3-ZOS-ITPP-501 [ ]

Onsite Standby Power System 3-ZOS-ITPP-503 [ ]

Onsite Standby Power System Load Sequencing 3-PWS-ITPP-501 [ ]

Potable Water System 3-ASS-ITPP-501 [ ]

Auxiliary Steam Supply System 3-TOS-ITPP-501 Main Turbine Control and Diagnostics System 3-CFS-ITPP-501 [ ]

Turbine Island Chemical Feed System 3-HDS-ITPP-501 [ ]

Heater Drain System 3-VTS-ITPP-501 [ ]

Turbine Building Ventilation System 3-BDS-ITPP-501 [ ]

Steam Generator Blowdown System Page 6 of9

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-BDS-ITPP-502 [ ]

Steam Generator Blowdown System Precore Hot Functional 3-VCS-ITPP-501 [ ]

Containment Recirculation Cooling System 3-VCS-ITPP-502 [ ]

Containment Recirculation Cooling System Precore Hot Funcjtional 3-VHS-ITPP-501 [ ]

Health Physics and Hot Machine Shop HVAC System 3-GSS-ITPP-501 [ ]

Gland Steam System

' 3-RMS-ITPP-501 [ ]

Radiation Monitoring System 3-RMS-ITPP-502 [ ]

Portable Personnel Monitors and Radiation Survey Instruments 3-VFS-ITPP-501 [ ]

Containment Air Filtration System 3-CWS-ITPP-501 [ ]

Circulating Water System 3-FWS-ITPP-501 [ ]

Main and Startup Feedwater System 3-FWS-ITPP-502 [ ]

Main and Startup Feedwater System Hot Functional 3-FHS-ITPP-521 [ ]

Fuel Handling System 3-FHS-ITPP-522 [ ]

Fuel Handling Equipment Indexing 3-FHS-ITPP-523 [ ]

Fuel Assembly Drag 3-CES-ITPP-501 [ ]

Condenser Tube Cleaning System 3-MTS-ITPP-501 [ ]

Main Turbine System 3-MTS-ITPP-502 [ ]

Main Turbine System Precore Hot Functional 3-VBS-ITPP-501 [ ]

Nuclear Island Nonradioactive Ventilation System Page 7 of9

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-VBS-ITPP-502 [ ]

Nuclear Island Nonradioactive Ventilation System Precore Hot Functional 3-HCS-ITPP-501 [ ]

Generator Hydrogen and C02 Systems 3-HSS-ITPP-501 [ ]

Hydrogen Seall Oil System l 3-TCS-ITPP-501 [ ]

Turbine Building Closed Cooling Water System 3-TCS-ITPP-503 [ ]

Stator Cooling Water 3-FPS-lfpP-501 [ ]

Fire Protection System 3-FPS-ITPP-502 [ ]

Fire Brigade Support Equipment 3-ZAS-ITPP-501 Main Generation System 3-CMS-ITPP-501 [ ]

Condenser Air Removal System 3-VZS-ITPP-501 ( ]

Diesel Generator Building Heating and Ventilation System 3-EFS-ITPP-501 [ ]

Plant Communications System 3-GEN-ITPP-507 [ ]

Thermal Expansion 3-GEN-ITPP-509 [ ]

Reactor Coolant System Vibration and Dynamic Effects 3-GEN-ITPP-510 [ ]

Normal Residual Heat Removal System Vibration and Dynamic Effects 3-GEN-ITPP-511 [ ]

Passive Core Cooling System Dynamic Effects 3-GEN-ITPP-512 [ ]

Chemical and Volume Control System Dynamic Effects 3-GEN-ITPP-515 [ ]

Feedwater, Steam Generator and Steam Generator Blowdown Systems Dynamic Effect 3-GEN-ITPP-517 [ ]

Precore Hot Functional Test Sequence Page 8 of9

Enclosure 4 to ND-19-0119 Vogtle Electric Generating Plant- Units 3and 4 Preoperational Test Procedure Completion Schedule Redacted Version Procedure Number/Name Completion Date 3-GEN-ITPP-518 [ ]

Precore Hot Functional Testing Chemistry 3-GEN-ITPP-521 [ ]

HVAC Final Air Balancing 3-SJS-ITPP-501 [ ]

Seismic Monitoring System l 3-VRS-ITPP-501 [ ]

Radwaste Building HVAC System 3-ELS-ITPP-501 [ ]

Plant Lighting System 3-PCS-ITPP-501 ' [ ]

Passive Containment Cooling System PCCAWST 3-PCS-ITPP-502 [ ]

Passive Containment Cooling System PCCWST Page 9 of9

Southern Nuclear Opierating Company ND-19-0119 Enblosure 6 Confidential Commercial Information Notice (This Enclosure consists of 2 pages, including this cover page)

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Enclosure 6 to ND-19-0119 Vogtle Electric Generating Plant- Units 3 and 4 Confidential Commercial Information Notice CONFIDENTIAL COMMERCIAL INFORMATION NOTICE Transmitted herewith are confidential commercial information and/or non-confidential commercial information versions of documents furnished to the NRG in connection with SNO's COL Operational Programs and Other License Conditions Implementation Schedule.

I I In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of confidential commercial information so submitted to the I i' NRC, the information which is confidential commercial information in the non-public version is contained within brackets, and where the confidential commercial information has been deleted In the public version, only the brackets remain (the information that was contained within the brackets in the public version having been deleted). The justification for claiming the information so designated as confidential commercial information is indicated in Enclosure 1, Affidavit for Withholding, accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).

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