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

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{{#Wiki_filter:A Southern Nuclear                                                               Southern Nuclear Operating Company, inc.
{{#Wiki_filter: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:
I u n IXI L.  
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.
^^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:
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 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))
Line 26: Line 31:
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
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:
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.
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.
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 2 contains the public, redacted version of SNC's COL Operational Programs and Other License Conditions Implementation Schedule.
Enclosure 5 contains the non-pubiic, non-redaCted version of SNC's Preoperationai Test Procedure Completion Schedule. contains a Confidential Commercial Information Notice.
j Enclosure 3 contains the non-public, non-redacted version of SNC's COL Operationai Programs and Other License Conditions Implementation Schedule.
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.
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.
This letter contains no regulatory commitments.
If you have any questions, please contact Michael Yox at(706)848-6459.
If you have any questions, please contact Michael Yox at (706) 848-6459.
(Oath and Affirmation are provided on the following page.)
(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.
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
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:
                                                          >i\x ,.<<*
My commission expires:
Sworn to and sutjscribed before me this          day of.                ^^2019
day of.
                                                                        'CPS Notary Public:
>i\\x,.<<*
^
Auo""
13/'
13/'
                                                      '        Auo""
^2019 CPS Enclosures
My commission expires:
Enclosures
: 1. Affidavit for Withholding
: 1. Affidavit for Withholding
: 2. Redacted COL Operational Programs and Other License Conditions Implementation Schedule
: 2. Redacted COL Operational Programs and Other License Conditions Implementation Schedule
Line 57: Line 58:
U.S. Nuclear Regulatory Commission ND-19-0119 Page 4 of 5 cc:
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)
Southern Nuclear Operating Company / Georgia Power Company Mr. 8. E. Kuczynski (w/o enclosures)
Mr. D. G. Best(w/o enclosures)
Mr. D. G. Best (w/o enclosures)
Mr. M. D. Meier (w/o enclosures)
Mr. M. D. Meier (w/o enclosures)
Mr. D. H. Jones (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. J. B. Klecha Mr. G. Chick Mr. D. L. McKinney (w/o enclosures)
Mr. T. W.Yelverton (w/o enclosures)
Mr. T. W.
Mr. B. H. Whitley       '
Yelverton (w/o enclosures)
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)
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
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)
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)
Ms. A. Whaley (w/o enclosures 3&5)
Municipal Electric Authority of Georoia Mr. J. E. Fuller (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)
Mr. S. M. Jackson (w/o enclosures 3&5)
Dalton Utilities               l Mr. T. Bundros(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)
Westinohouse Electric Company. LLC Mr. L. Oriani (w/o enclosures)
T. Rubenstein (w/o enclosures)
T. Rubenstein (w/o enclosures)
Mr. M. Corletti           '
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)
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)
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)
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)
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)
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. 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. 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)
Mr. S. Franzone, Florida Power & Light (w/o enclosures 3&5)


Southern Nuclear Operating Company ND-19-0119 I
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 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:
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
Joseph B. Klecha SWORN to and SUBSCRIBED before me this 0 day of
* t ** 4, V/f.-O Notary Public:                                  ./A My Commission Expires:
^ day of County Notary Public:
STATES THE AFFIANT:
My Commission Expires:
: 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.
W\\o
: 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.
[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
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).
: 3.
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:
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. SNC has heid the information in confidence.
I
ii. This information is of a type customariiy held in confidence by SNC.
: 4.
iii. This information is being transmitted to the NRC in confidence.
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:
iv. This information is not avaiiable in public sources.
: i.
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.
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.
FURTHER AFFIANT SAITH NOT.
Page 3 of 3
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)
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
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                   [             ]
02.0.(11)
N/A 02.0.(11)
N/A Unit 4 Initial Fuel Load
Unit 3 Inservice Inspection                  L            ]
[
Table 13.4-201 Item 1 02.0.(11)
]
Unit 4 Inservice Inspection                  [              ]
02.0.(11)
Table 13.4-201 Item 1 02.0.(11)
Table 13.4-201 Item 1 Unit 3 Inservice Inspection
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              [              ]
L
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        [              ]
02.0.(11)
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 1 Unit 4 Inservice Inspection
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-             [             ]
02.0.(11)
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 2 Inservice Testing
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             [             ]
02.0.(10)(a) and 02.0.(11)
Table 13.4-201 Item 14 02.0.(111             Unit 4 Emergency Planning: Full Participation          [             ]
Table 13.4-201 Item 3 Environmental Qualification
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              [             ]
02.0.(11)
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 4 Unit 3 Preservice Inspection
Table 13.4-201 Item 15 operationall Page 3 of6
[
]
02.0.(11)
Table 13.4-201 Item 4 Unit 4 Preservice Inspection
[
]
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
[
]
02.0.(10)(d) and 02.0.(11)
Table 13.4-201 Item 7 Containment Leakage Rate Testing
[
]
02.0.(10)(e)1. and 02.0.(11)
Table 13.4-201 Item 8 Fire Protection - Oesignated Storage Areas (per RG 1.189)
[
]
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
[
]
02.0.(10)(f) and 02.0.(11)
Table 13.4-201 Item 9 Radiological Effluent Technical Specifications/Standard Radiological Effluent Controls
[
]
02.0.(10)(a) and 02.0.(11)
Table 13.4-201 Item 9 Offsite Dose Calculation Manual
[
]
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
[
]
02.D.(10)m and 02.D.ni1 Table 13.4-201 Item 9 Process Control
[
]
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
[
]
02.0.(101(112. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Receipt of Fuel Onsite
_ [  
]
02.0.(101(113. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Initial Fuel Load
[
]
02.0.(101(114. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Shipment of Radioactive Waste
[
]
02.0.(111 Table 13.4-201 Item 11 Non-Licensed Plant Staff Training (non-radioactivel
[
]
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
[
]
02.0.(111 Table 13.4-201 Item 13 Reactor Operator Requalification
[
]
02.0.(111 Table 13.4-201 Item 14 Unit 3 Emergency Planning: Full Participation Exercise
[
]
02.0.(111 Table 13.4-201 Item 14 Unit 3 Emergency Planning: Onsite Exercise
[
]
02.0.(111 Table 13.4-201 Item 14 Unit 4 Emergency Planning: Full Participation Exercise
[
]
02.0.(111 Table 13.4-201 Item 14 Unit 4 Emergency Planning: Onsite Exercise
_ [  
]
02.0.(111 Table 13.4-201 Item 14 Emergency Planning: Detailed Implementing Procedures for Emergency Plan
[
]
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
[
]
02.D.ni)
Table 13.4-201 Item 15 Safeguards Contingency Program
[
]
02.D.(111 Table 13.4-201 Item 15 Security Training and Qualification Program
[
]
02.D.(111 Table 13.4-201 Item 16 Quality Assurance
[
]
02.D.ni1 Table 13.4-201 Item 17 Maintenance Rule
[
]
02.D.noim and02.D.ni1 Table 13.4-201 Item 18 MO V Testing
_ [  
]
02.D.(10)(m)1.and 02.D.(111 Table 13.4-201 Item 19 Initial Test Program - Component
[
]
02.D.(101(m12. and 02.D.ni1 Table 13.4-201 Item 19 Initial Test Program - Pre-Qperational
[
]
02.D.n0Km13. and 02.D.f111 Table 13.4-201 Item 19 Initial Test Program - Startup
[
]
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)
[
]
02.D.(11)
Table 13.4-201 Item 20 FFD for FFD personnel
[
]
02.D.ni1 Table 13.4-201 Item 20 FFD for TSC and EOF personnel
[
]
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


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                                                                      [              ]
Vogtle Electric Generating Plant -
Physical Security Program Table 13.4-201 Item 15 02.D.ni)                                                                       [              ]
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
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                                                                      [              ]
02.0.(121(f11.
Maintenance Rule Table 13.4-201 Item 17 02.D.noim and02.D.ni1 MOV Testing                    _ [                ]
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.
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                                                              [              ]
02.0.(121(f11.
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)
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.
FFD for Security Personnel(WECTEC)
[
Table 13.4-201 Item 20 02.D.(111                                                                      [              ]
]
FFD for Security Personnel(SNC)
02.0.(121(f12.
Table 13.4-201 Item 20 02.D.(11)                                                                      [              ]
N/A Spent Fuel Rack Metamic Coupon Monitoring-Program
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)                                                                        [              ]
02.0.(121(f13.
Cyber Security Table 13.4-201 Item 21 Page 4 of6
N/A Flow Accelerated Corrosion Program (including construction phase)
 
[
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           [              ]
02.0.(121(114.
concrete composite construction activities lor 02.0.(121(f11.
Section 10.2.3.6 Turbine Maintenance and Inspection Program
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.
02.0.(121(115.
uncertainties to calculate a power calorimetric N/A uncertainty Availability ol administrative controls to          [.            ]
N/A Availability ol documented instrumentation uncertainties to calculate a power calorimetric uncertainty
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.
02.0.(121(116.
circumstances associated with the loss ol N/A large areas ol the plant due to explosions or lire 02.0.(121(119.                                                                   [              ]
N/A Availability ol administrative controls to implement maintenance and contingency activities related to the power calorimetric uncertainty instrumentation
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.                                                                   [                ]
02.0.(121(117.
Startup testing procedures Section 14.2.3 Page 6 of6
N/A Site-specilic severe accident management guidelines
 
[
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)
]
 
02.0.(121(118.
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                                              [          ]
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
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                            [          ]
02.0.(121(119.
3-DDS-ITPP-SOl                                                                [          ]
Section 14.2.3 ITP administrative manual procedures
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                                                                [          ]
Page 5 of 6 to ND-19-0119 Vogtle Electric Generating Plant -
Plant Gas System 3-PLS-ITPP-S06                                                                [          ]
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.
Control Rod Drive Mechanism Motor-Generator 3-PLS-ITPP-S07                                                                [          ]
Section 14.2.3 Preoperational testing procedures See Enclosure 4 02.D.(12)(f)9.
Control Rod Drive Mechanism Precore Hot Functional 3-PLS-ITPP-S20                                                                [          ]
Section 14.2.3 Startup testing procedures
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                                                                [          ]
Page 6 of 6
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                                                                [           ]
Southern Nuclear Operating Company ND-19-0119 l
Condensate Polishing System 3-WWS-ITPP-501                                                               [           ]
Redacted Preoperatlonal Test Procedure Completion Schedule (This Enclosure consists of 9 pages, inciuding this cover page) to ND-19-0119 Vogtle Electric Generating Plant -
Waste Water System 3-LOS-ITPP-501                                                                [         ]
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
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                                                                [         ']
3-WRS-ITPP-501 Radioactive Waste Drain System
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                                                                [         ]
3-VWS-ITPP-SOl Central Chilled vli/ater System l
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                                                                [         ]
3-VWS-ITPP-S02 Central Chilled Water System Precore Hot Functional
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                                                                [          ]
3-DDS-ITPP-SOl Data Display and Processing System
Heater Drain System 3-VTS-ITPP-501                                                               [         ]
[
Turbine Building Ventilation System 3-BDS-ITPP-501                                                                [         ]
]
Steam Generator Blowdown System Page 6 of9
3-DDS-ITPP-S02 Integrated DCIS Performance
 
[
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                                                                [         ]
3-IDS-ITPP-SOl Class IE DC and UPS System
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                                                                [         ]
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
Gland Steam System
[
' 3-RMS-ITPP-501                                                               [         ]
]
Radiation Monitoring System 3-RMS-ITPP-502                                                                [         ]
3-PLS-ITPP-S06 Control Rod Drive Mechanism Motor-Generator
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                                                               [         ]
3-PLS-ITPP-S07 Control Rod Drive Mechanism Precore Hot Functional
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                                                                [         ]
3-PLS-ITPP-S20 Digital Rod Position Indication
Fuel Handling Equipment Indexing 3-FHS-ITPP-523                                                                [          ]
[
Fuel Assembly Drag 3-CES-ITPP-501                                                                [          ]
]
Condenser Tube Cleaning System 3-MTS-ITPP-501                                                                [          ]
3-RXS-ITPP-SOl Pre-and Post-Precore Hot Functional Inspection of Reactor Vessel Internals
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
3-RXS-ITPP-S02 Reactor Vessel Internals Vibration
 
[
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                                                               [           ]
3-RXS-ITPP-S03 Integrated Head Package (IHP)
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                                                                [         ]
3-SWS-ITPP-SOl Service Water System
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                                                                [         ]
3-SWS-ITPP-S02 Service Water System Precore Hot Functional
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                                                                [          ]
Page 2 of 9 to ND-19-0119 Vogtle Electric Generating Plant -
Thermal Expansion 3-GEN-ITPP-509                                                                [         ]
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
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                                                                [         ]
3-PMS-ITPP-502 PMS Time Response
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
3-PMS-ITPP-503 PMS Qualified Data Processing System l
 
[
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                                                                [         ]
3-PMS-ITPP-504 PMS RT Actuation
HVAC Final Air Balancing 3-SJS-ITPP-501                                                                [         ]
[
Seismic Monitoring System                                              l 3-VRS-ITPP-501                                                                 [         ]
]
Radwaste Building HVAC System 3-ELS-ITPP-501                                                                 [         ]
3-PMS-ITPP-505 PMS Nuclear Instrumentation System
Plant Lighting System 3-PCS-ITPP-501 '                                                              [         ]
[
Passive Containment Cooling System PCCAWST 3-PCS-ITPP-502                                                                 [         ]
]
Passive Containment Cooling System PCCWST Page 9 of9
3-PMS-ITPP-521 '
PMS Logic
[
1 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 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
[
]
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 Passive Core Cooling System Precore Hot Functional Test
[
1 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 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
[
]
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 VLS Preoperational Test
[
1 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 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
[
]
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 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
[
]
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 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
[
]
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 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
[
]
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 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)
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
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.
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
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).
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).
f Page 2 of 2}}
f Page 2 of 2}}

Latest revision as of 06:09, 5 January 2025

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)
v • d • e


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

[

]

02.0.(11)

N/A Unit 4 Initial Fuel Load

[

]

02.0.(11)

Table 13.4-201 Item 1 Unit 3 Inservice Inspection

L

]

02.0.(11)

Table 13.4-201 Item 1 Unit 4 Inservice Inspection

[

]

02.0.(11)

Table 13.4-201 Item 2 Inservice Testing

[

]

02.0.(10)(a) and 02.0.(11)

Table 13.4-201 Item 3 Environmental Qualification

[

]

02.0.(11)

Table 13.4-201 Item 4 Unit 3 Preservice Inspection

[

]

02.0.(11)

Table 13.4-201 Item 4 Unit 4 Preservice Inspection

[

]

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

[

]

02.0.(10)(d) and 02.0.(11)

Table 13.4-201 Item 7 Containment Leakage Rate Testing

[

]

02.0.(10)(e)1. and 02.0.(11)

Table 13.4-201 Item 8 Fire Protection - Oesignated Storage Areas (per RG 1.189)

[

]

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

[

]

02.0.(10)(f) and 02.0.(11)

Table 13.4-201 Item 9 Radiological Effluent Technical Specifications/Standard Radiological Effluent Controls

[

]

02.0.(10)(a) and 02.0.(11)

Table 13.4-201 Item 9 Offsite Dose Calculation Manual

[

]

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

[

]

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

[

]

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

[

]

02.0.(101(112. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Receipt of Fuel Onsite

_ [

]

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

[

]

02.0.(101(114. and 02.0.(111 Table 13.4-201 Item 10 Radiation Protection Program: Prior to Shipment of Radioactive Waste

[

]

02.0.(111 Table 13.4-201 Item 11 Non-Licensed Plant Staff Training (non-radioactivel

[

]

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

[

]

02.0.(111 Table 13.4-201 Item 13 Reactor Operator Requalification

[

]

02.0.(111 Table 13.4-201 Item 14 Unit 3 Emergency Planning: Full Participation Exercise

[

]

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

[

]

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

_ [

]

02.0.(111 Table 13.4-201 Item 14 Emergency Planning: Detailed Implementing Procedures for Emergency Plan

[

]

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

[

]

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

[

]

02.D.ni)

Table 13.4-201 Item 15 Safeguards Contingency Program

[

]

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

[

]

02.D.(111 Table 13.4-201 Item 16 Quality Assurance

[

]

02.D.ni1 Table 13.4-201 Item 17 Maintenance Rule

[

]

02.D.noim and02.D.ni1 Table 13.4-201 Item 18 MO V Testing

_ [

]

02.D.(10)(m)1.and 02.D.(111 Table 13.4-201 Item 19 Initial Test Program - Component

[

]

02.D.(101(m12. and 02.D.ni1 Table 13.4-201 Item 19 Initial Test Program - Pre-Qperational

[

]

02.D.n0Km13. and 02.D.f111 Table 13.4-201 Item 19 Initial Test Program - Startup

[

]

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)

[

]

02.D.(11)

Table 13.4-201 Item 20 FFD for FFD personnel

[

]

02.D.ni1 Table 13.4-201 Item 20 FFD for TSC and EOF personnel

[

]

02.D.(111 Table 13.4-201 Item 20 FFD for Operations

[

]

02.D.ni)

Table 13.4-201 Item 21 Cyber Security

[

]

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

[

]

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.

[

]

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.

[

]

02.0.(121(f12.

N/A Spent Fuel Rack Metamic Coupon Monitoring-Program

[

]

02.0.(121(f13.

N/A Flow Accelerated Corrosion Program (including construction phase)

[

]

02.0.(121(114.

Section 10.2.3.6 Turbine Maintenance and Inspection Program

[

]

02.0.(121(115.

N/A Availability ol documented instrumentation uncertainties to calculate a power calorimetric uncertainty

[

]

02.0.(121(116.

N/A Availability ol administrative controls to implement maintenance and contingency activities related to the power calorimetric uncertainty instrumentation

[.

]

02.0.(121(117.

N/A Site-specilic severe accident management guidelines

[

]

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

[

]

02.0.(121(119.

Section 14.2.3 ITP administrative manual procedures

[

]

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

[

]

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

[

]

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 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

[

]

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 '

PMS Logic

[

1 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 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

[

]

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 Passive Core Cooling System Precore Hot Functional Test

[

1 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 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

[

]

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 VLS Preoperational Test

[

1 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 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

[

]

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 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

[

]

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 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

[

]

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 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

[

]

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

[

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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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