ND-19-0119, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule
| ML19039A264 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| 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) | |
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: 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. 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. 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. 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 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 Sworn to and sutjscribed before me this Notary Public:
My commission expires:
day of.
>i\\x,.<<*
^
Auo""
13/'
^2019 CPS 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
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 of
^ day of County Notary Public:
My Commission Expires:
W\\o
[MJUX2019 in, X
- t *
- 4,
V/f.-O
./A 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 Redacted COL Operational Programs and Other License Conditions Implementation Schedule (This Enclosure consists of 6 pages, Including this cover page) 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 FSAR Reference Program Name implementation Date 02.D.nil N/A Unit 3 Initial Fuel Load
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02.0.(11)
N/A Unit 4 Initial Fuel Load
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02.0.(11)
Table 13.4-201 Item 1 Unit 3 Inservice Inspection
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02.0.(11)
Table 13.4-201 Item 1 Unit 4 Inservice Inspection
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02.0.(11)
Table 13.4-201 Item 2 Inservice Testing
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02.0.(10)(a) and 02.0.(11)
Table 13.4-201 Item 3 Environmental Qualification
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02.0.(11)
Table 13.4-201 Item 4 Unit 3 Preservice Inspection
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02.0.(11)
Table 13.4-201 Item 4 Unit 4 Preservice Inspection
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02.0.(10)(b) and 02.0.(11)
Table 13.4-201 Item 5 Reactor Vessel Material Surveillance 02.0.(10)(c) and 02.0.(11)
Table 13.4-201 Item 6 Preservice Testing
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02.0.(10)(d) and 02.0.(11)
Table 13.4-201 Item 7 Containment Leakage Rate Testing
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02.0.(10)(e)1. and 02.0.(11)
Table 13.4-201 Item 8 Fire Protection - Oesignated Storage Areas (per RG 1.189)
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02.0.(10)(e)2. and 02.0.(11)
Table 13.4-201 Item 8 Fire Protection - New Fuel Areas (per RG 1.189)
^
J 02.0.(10)(e)3. and 02.0.(11)
Table 13.4-201 Item 8 Fire Protection - All other features
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02.0.(10)(f) and 02.0.(11)
Table 13.4-201 Item 9 Radiological Effluent Technical Specifications/Standard Radiological Effluent Controls
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02.0.(10)(a) and 02.0.(11)
Table 13.4-201 Item 9 Offsite Dose Calculation Manual
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Page 2 of 6 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 FSAR Reference Program Name Implementation Date 02.D.(10)fh) and02.D.nU Table 13.4-201 Item 9 Radiological Environmental Monitoring
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02.D.(10)m and 02.D.ni1 Table 13.4-201 Item 9 Process Control
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02.0.(101(111. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Initial Receipt of Byproduct, Source, or Special Nuclear Materials
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02.0.(101(112. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Receipt of Fuel Onsite
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02.0.(101(113. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Initial Fuel Load
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02.0.(101(114. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Shipment of Radioactive Waste
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02.0.(111 Table 13.4-201 Item 11 Non-Licensed Plant Staff Training (non-radioactivel
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02.0.(111 Table 13.4-201 Item 11 Non-Licensed Plant Staff Training (portions applicable to radioactive materiall 02.0.(1 OKkl and 02.0.(111 Table 13.4-201 Item 12 Reactor Operator Training
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02.0.(111 Table 13.4-201 Item 13 Reactor Operator Requalification
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02.0.(111 Table 13.4-201 Item 14 Unit 3 Emergency Planning: Full Participation Exercise
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02.0.(111 Table 13.4-201 Item 14 Unit 3 Emergency Planning: Onsite Exercise
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02.0.(111 Table 13.4-201 Item 14 Unit 4 Emergency Planning: Full Participation Exercise
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02.0.(111 Table 13.4-201 Item 14 Unit 4 Emergency Planning: Onsite Exercise
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02.0.(111 Table 13.4-201 Item 14 Emergency Planning: Detailed Implementing Procedures for Emergency Plan
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02.0.(1 OKol and 02.0.(111 Table 13.4-201 Item 15 Physical Protection Program (for special nuclear material before Protected Area is operationall
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Page 3 of 6 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 FSAR Reference Program Name Implementation Date 02.D.(1U Table 13.4-201 Item 15 Physical Security Program
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02.D.ni)
Table 13.4-201 Item 15 Safeguards Contingency Program
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02.D.(111 Table 13.4-201 Item 15 Security Training and Qualification Program
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02.D.(111 Table 13.4-201 Item 16 Quality Assurance
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02.D.ni1 Table 13.4-201 Item 17 Maintenance Rule
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02.D.noim and02.D.ni1 Table 13.4-201 Item 18 MO V Testing
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02.D.(10)(m)1.and 02.D.(111 Table 13.4-201 Item 19 Initial Test Program - Component
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02.D.(101(m12. and 02.D.ni1 Table 13.4-201 Item 19 Initial Test Program - Pre-Qperational
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02.D.n0Km13. and 02.D.f111 Table 13.4-201 Item 19 Initial Test Program - Startup
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02.D.ni)
Table 13.4-201 Item 20 FFD for Construction Workers and First-Line Supervisors 02.D.(111 Table 13.4-201 Item 20 FFD for Construction Management and Oversight Personnel 02.D.(11)
Table 13.4-201 Item 20 FFD for Security Personnel (WECTEC) 02.D.(111 Table 13.4-201 Item 20 FFD for Security Personnel (SNC)
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02.D.(11)
Table 13.4-201 Item 20 FFD for FFD personnel
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02.D.ni1 Table 13.4-201 Item 20 FFD for TSC and EOF personnel
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02.D.(111 Table 13.4-201 Item 20 FFD for Operations
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02.D.ni)
Table 13.4-201 Item 21 Cyber Security
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Page 4 of 6 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 FSAR Reference Program Name Implementation Date 02.0.(1 OUn) and 02.0.(111 Table 13.4-201 Item 22 Special Nuclear Material Control and Accounting
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02.0.(121(f11.
Section 3.8.4.8 Construction inspection procedures lor steei concrete composite construction activities lor seismic Category 1 nuclear island structural modules lor minimum required reinforcement, steel plate thickness, and concrete thickness.
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02.0.(121(f11.
Section 3.8.4.8 Construction inspection procedures for steel concrete composite construction activities for seismic Category 1 shield building moduies for minimum required reinforcement, steel plate thickness, and concrete thickness.
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02.0.(121(f12.
N/A Spent Fuel Rack Metamic Coupon Monitoring-Program
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02.0.(121(f13.
N/A Flow Accelerated Corrosion Program (including construction phase)
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02.0.(121(114.
Section 10.2.3.6 Turbine Maintenance and Inspection Program
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02.0.(121(115.
N/A Availability ol documented instrumentation uncertainties to calculate a power calorimetric uncertainty
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02.0.(121(116.
N/A Availability ol administrative controls to implement maintenance and contingency activities related to the power calorimetric uncertainty instrumentation
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02.0.(121(117.
N/A Site-specilic severe accident management guidelines
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02.0.(121(118.
N/A The operational and programmatic elements ol the mitigative strategies for responding to circumstances associated with the loss ol large areas ol the plant due to explosions or lire
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02.0.(121(119.
Section 14.2.3 ITP administrative manual procedures
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Page 5 of 6 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 FSAR Reference Program Name implementation Date 02.D.(12Uf)9.
Section 14.2.3 Preoperational testing procedures See Enclosure 4 02.D.(12)(f)9.
Section 14.2.3 Startup testing procedures
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Page 6 of 6
Southern Nuclear Operating Company ND-19-0119 l
Redacted Preoperatlonal Test Procedure Completion Schedule (This Enclosure consists of 9 pages, inciuding this cover page) 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
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3-WRS-ITPP-501 Radioactive Waste Drain System
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3-VWS-ITPP-SOl Central Chilled vli/ater System l
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3-VWS-ITPP-S02 Central Chilled Water System Precore Hot Functional
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3-DDS-ITPP-SOl Data Display and Processing System
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3-DDS-ITPP-S02 Integrated DCIS Performance
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3-IDS-ITPP-SOl Class IE DC and UPS System
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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
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3-PLS-ITPP-S06 Control Rod Drive Mechanism Motor-Generator
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3-PLS-ITPP-S07 Control Rod Drive Mechanism Precore Hot Functional
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3-PLS-ITPP-S20 Digital Rod Position Indication
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3-RXS-ITPP-SOl Pre-and Post-Precore Hot Functional Inspection of Reactor Vessel Internals
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3-RXS-ITPP-S02 Reactor Vessel Internals Vibration
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3-RXS-ITPP-S03 Integrated Head Package (IHP)
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3-SWS-ITPP-SOl Service Water System
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3-SWS-ITPP-S02 Service Water System Precore Hot Functional
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Page 2 of 9 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
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3-PMS-ITPP-502 PMS Time Response
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3-PMS-ITPP-503 PMS Qualified Data Processing System l
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3-PMS-ITPP-504 PMS RT Actuation
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3-PMS-ITPP-505 PMS Nuclear Instrumentation System
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3-PMS-ITPP-521 '
PMS Logic
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1 3-PMS-ITPP-522 PMS Squib Valve Controller Performance
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3-PMS-ITPP-523 PMS Containment Pressure High-2
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3-PMS-ITPP-524 PMS Cold Actuations 3-PMS-ITPP-526 PMS MCR Isolation and Passive Containment Cooling System Actuation
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3-WGS-ITPP-501 Gaseous Radwaste System+D686
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3-SFS-ITPP-S02 Spent Fuel Pool Cooling System Flow Path
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3-SFS-ITPP-503 Spent Fuel Pool Cooling Loss of Large Area
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3-WSS-ITPP-501 Solid Radwaste System
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3-ECS-ITPP-501 6.9 kV Switchgear
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3-ECS-ITPP-504 Ancillary Diesel Generator
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3-SDS-ITPP-501 Sanitary Drainage System
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3-CVS-ITPP-501 Chemical and Volume Control System
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Page 3 of 9 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
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3-PSS-ITPP-502 Primary Sampling System Precore Hot Functional
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3-PXS-ITPP-502 PXS ACC Mapping Line ResistancelTest
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3-PXS-ITPP-503 Passive Core Cooling System Flow Testing with the RV Head Installed
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3-PXS-ITPP-504 Passive Core Cooling System Precore Hot Functional Test
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1 3-PXS-ITPP-505 Passive Core Cooling System Automatic Depressurlzatlon Precore Hot Functional
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3-RNS-ITPP-501 Normal Residual Heat Removal System
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3-RNS-ITPP-502 Normal Residual Heat Removal System Precore Hot Functional
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3-WLS-ITPP-501 Liquid Radwaste System
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3-PXS-ITPP-506 PXS CMT Mapping and Line Resistance Test
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3-PXS-ITPP-507 PXS IRWST Resistance Test
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3-MHS-ITPP-501 Nuclear Island Mechanical Handling System
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3-SGS-ITPP-502 Steam Generator System
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3-SGS-ITPP-504 Steam Generator Hydrostatic
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3-SMS-ITPP-501 Special Monitoring System
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3-SMS-ITPP-502 Special Monitoring System Precore Hot Functional
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3-DAS-ITPP-501 Diverse Actuation System
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3-TVS-ITPP-501 Closed Circuit Television System
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Page 4 of 9 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
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3-IIS-ITPP-501 Incore instrumentation System
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3-MSS-ITPP-501 Main Steam System l
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3-MSS-ITPP-502 Main Steam System Precore Hot Functional
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3-DWS-ITPP-501 Demineralized Water Transfer and Storage System
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3-CNS-ITPP-501 ILRT Containment System Leak Rate Test Type A 3-CNS-ITPP-502 ILRT Containment System Leak Test Type B
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3-CNS-ITPP-503 ILRT Containment System Leak Test Type C
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3-RCS-ITPP-503 RCS Primary Hydrostatic
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3-RCS-ITPP-504 Pressurizer Pressure Level and Spray Precore Hot Functional
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3-RCS-ITPP-505 RCS Precore Hot Functional Instrumentation Calibration
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3-RCS-ITPP-506 Reactor Coolant Pump and Reactor Coolant Flow Precore Hot Functional
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3-CDS-ITPP-501 Condensate System
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3-RWS-ITPP-501 Raw Water System
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3-VLS-ITPP-501 VLS Preoperational Test
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1 3-VYS-ITPP-501 Hot Water Heating System
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3-VAS-ITPP-502 Radiologically Controlled Area Ventilation System Precore Hot Functional
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3-VAS-ITPP-501 Radiologically Controlled Area Ventilation System
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Page 5 of 9 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
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3-WWS-ITPP-501 Waste Water System
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3-LOS-ITPP-501 Main Turbine and Generator Lube Oil System l
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3-SSS-ITPP-501 Secondary Sampling System
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3-SSS-ITPP-502 Secondary Sampling System Precore Hot Functional
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3-VXS-ITPP-501 Annex/Auxiliary Building Nonradioactive Ventilation System
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3-VES-ITPP-501 Main Control Room Emergency Habitability System
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3-CCS-ITPP-501 Component Cooling Water System
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3-CCS-ITPP-502 Component Cooling Water System Precore Hot Functional
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3-ZOS-ITPP-501 Onsite Standby Power System
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3-ZOS-ITPP-503 Onsite Standby Power System Load Sequencing
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3-PWS-ITPP-501 Potable Water System
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3-ASS-ITPP-501 Auxiliary Steam Supply System
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3-TOS-ITPP-501 Main Turbine Control and Diagnostics System 3-CFS-ITPP-501 Turbine Island Chemical Feed System
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3-HDS-ITPP-501 Heater Drain System
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3-VTS-ITPP-501 Turbine Building Ventilation System
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3-BDS-ITPP-501 Steam Generator Blowdown System
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Page 6 of 9 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
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3-VCS-ITPP-501 Containment Recirculation Cooling System
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3-VCS-ITPP-502 Containment Recirculation Cooling System Precore Hot Funcjtional
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3-VHS-ITPP-501 Health Physics and Hot Machine Shop HVAC System
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3-GSS-ITPP-501 Gland Steam System
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' 3-RMS-ITPP-501 Radiation Monitoring System
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3-RMS-ITPP-502 Portable Personnel Monitors and Radiation Survey Instruments
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3-VFS-ITPP-501 Containment Air Filtration System
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3-CWS-ITPP-501 Circulating Water System
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3-FWS-ITPP-501 Main and Startup Feedwater System
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3-FWS-ITPP-502 Main and Startup Feedwater System Hot Functional
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3-FHS-ITPP-521 Fuel Handling System
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3-FHS-ITPP-522 Fuel Handling Equipment Indexing
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3-FHS-ITPP-523 Fuel Assembly Drag
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3-CES-ITPP-501 Condenser Tube Cleaning System
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3-MTS-ITPP-501 Main Turbine System
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3-MTS-ITPP-502 Main Turbine System Precore Hot Functional
[
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3-VBS-ITPP-501 Nuclear Island Nonradioactive Ventilation System
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Page 7 of 9 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
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3-HCS-ITPP-501 Generator Hydrogen and C02 Systems
[
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3-HSS-ITPP-501 Hydrogen Seall Oil System l
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3-TCS-ITPP-501 Turbine Building Closed Cooling Water System
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3-TCS-ITPP-503 Stator Cooling Water
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3-FPS-lfpP-501 Fire Protection System
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3-FPS-ITPP-502 Fire Brigade Support Equipment
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3-ZAS-ITPP-501 Main Generation System 3-CMS-ITPP-501 Condenser Air Removal System
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3-VZS-ITPP-501 Diesel Generator Building Heating and Ventilation System
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3-EFS-ITPP-501 Plant Communications System
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3-GEN-ITPP-507 Thermal Expansion
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3-GEN-ITPP-509 Reactor Coolant System Vibration and Dynamic Effects
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3-GEN-ITPP-510 Normal Residual Heat Removal System Vibration and Dynamic Effects
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3-GEN-ITPP-511 Passive Core Cooling System Dynamic Effects
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3-GEN-ITPP-512 Chemical and Volume Control System Dynamic Effects
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3-GEN-ITPP-515 Feedwater, Steam Generator and Steam Generator Blowdown Systems Dynamic Effect
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3-GEN-ITPP-517 Precore Hot Functional Test Sequence
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Page 8 of 9 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-GEN-ITPP-518 Precore Hot Functional Testing Chemistry
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3-GEN-ITPP-521 HVAC Final Air Balancing
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3-SJS-ITPP-501 Seismic Monitoring System l
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3-VRS-ITPP-501 Radwaste Building HVAC System
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3-ELS-ITPP-501 Plant Lighting System
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3-PCS-ITPP-501 '
Passive Containment Cooling System PCCAWST
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3-PCS-ITPP-502 Passive Containment Cooling System PCCWST
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Page 9 of 9
Southern Nuclear Opierating Company ND-19-0119 Enblosure 6 Confidential Commercial Information Notice (This Enclosure consists of 2 pages, including this cover page)
Page 1 of 2 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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