ML21316A055
| ML21316A055 | |
| Person / Time | |
|---|---|
| Site: | Vogtle, Farley  |
| Issue date: | 01/05/2022 |
| From: | John Lamb Plant Licensing Branch II |
| To: | Gayheart C Southern Nuclear Operating Co |
| Lamb, J. | |
| References | |
| EPID L-2021-LLA-0163, TSTF-577 | |
| Download: ML21316A055 (39) | |
Text
January 5, 2022
Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company 3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING REVISION TO TECHNICAL SPECIFICATIONS TO ADOPT TSTF-577, REVISED FREQUENCIES FOR STEAM GENERATOR TUBE INSPECTIONS (EPID L-2021-LLA-0163)
Dear Ms. Gayheart:
The U.S. Nuclear Regulatory Commission (t he Commission) has issued the enclosed Amendment No. 238 to Renewed Facility Operating License No. NPF-2 and Amendment No. 235 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, respective ly; and Amendment No. 211 to Renewed Facility Operating License NPF-68 and Amendment No. 194 to Renewed Facility Operating License NPF-81 for the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2, respectively. The amendments consist of changes to the License and Technical Specifications (TSs) in response to your application dated September 17, 2021, as supplemented October 21, 2021.
The amendments would revise the TSs to adopt Technical Specifications Task Force (TSTF)
Traveler TSTF-577, Revision 1, Revised Freque ncies for Steam Generator Tube Inspections.
Copies of the related Safety Evaluations are also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
C. Gayheart
If you have questions, you can contact me at 301-415-3100 or John.Lamb@nrc.gov.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-348, 50-364, 50-424, and 50-425
Enclosures:
- 1. Amendment No. 238 to NPF-2
- 4. Amendment No. 194 to NPF-81
- 5. Safety Evaluation for Farley
- 6. Safety Evaluation for Vogtle
cc w/encls: Listserv
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
ALABAMA POWER COMPANY
DOCKET NO. 50-348
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1
AMENDMENT TO RENEWED FACILITY OPERATING LICENSE
Amendment No. 238 Renewed License No. NPF-2
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern Nuclear Operating Company, Inc.
(Southern Nuclear), dated September 17, 2021, as supplemented on October 21, 2021, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-2 is hereby amended to read as follows:
(2) Technical Specifications
The Technical Specifications contained in Appendix A, as revised through Amendment No. 238, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Technical Specifications
Date of Issuance: January 5, 2022 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
ALABAMA POWER COMPANY
DOCKET NO. 50-364
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2
AMENDMENT TO RENEWED FACILITY OPERATING LICENSE
Amendment No. 235 Renewed License No. NPF-8
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern Nuclear Operating Company, Inc.
(Southern Nuclear), dated September 17, 2021, as supplemented on October 21, 2021, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wi ll be conducted in compliance with the Commissions regulations;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 2
- 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-8 is hereby amended to read as follows:
(2) Technical Specifications
The Technical Specifications contained in Appendix A, as revised through Amendment No. 235, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Operating License and Technical Specifications
Date of Issuance: January 5, 2022
ATTACHMENT
TO LICENSE AMENDMENT NO. 238
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1
RENEWED FACILITY OPERATING LICENSE NO. NPF-2
DOCKET NO. 50-348
AND
TO LICENSE AMENDMENT NO. 235
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2
RENEWED FACILITY OPERATING LICENSE NO. NPF-8
DOCKET NO. 50-364
Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages
License License License No. NPF-2, page 4 License No. NPF-2, page 4 License No. NPF-8, page 3 License No. NPF-8, page 3
TSs TSs
5.5-5 5.5-5 5.5-7 5.5-7 5.5-8 5.5-8 5.6-6 5.6-6
5.6-7
(2) Technical Specifications
The Technical Specifications contained in Appendix A, as revised through Amendment No. 238, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
(3) Additional Conditions
The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the Issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.
- a. Southern Nuclear shall not operate the reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation.
- b. Deleted per Amendment 13
- c. Deleted per Amendment 2
- d. Deleted per Amendment 2
- e. Deleted per Amendment 152
Deleted per Amendment 2
- f. Deleted per Amendment 158
- g. Southern Nuclear shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall include:
- 1) Identification of a sampling schedule for the critical parameters and control points for these parameters;
- 2) Identification of the procedures used to quantify parameters that are critical to control points;
- 3) Identification of process sampling points;
- 4) A procedure for the recording and management of data;
- 5) Procedures defining corrective actions for off control point chemistry conditions; and
Farley - Unit 1 Renewed License No. NPF-2 Amendment No. 238 (2) Alabama Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, Licensing of Production and Utilization Facilities, to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with the procedures and limitations set forth in this renewed license.
(3) Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
(4) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
(5) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproducts, source or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or associated with radioactive apparatus or components; and
(6) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporate below:
(1) Maximum Power Level
Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 2821 megawatts thermal.
(2) Technical Specifications
The Technical Specifications contained in Appendix A, as revised through Amendment No. 235, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
(3) Delete per Amendment 144
(4) Delete Per Amendment 149
(5) Delete per Amend 144
Farley - Unit 2 Renewed License No. NPF-8 Amendment No. 235 3URJUDPVDQG0DQXDOV
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SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY
OGLETHORPE POWER CORPORATION
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
CITY OF DALTON, GEORGIA
DOCKET NO. 50-424
VOGTLE ELECTRIC GENERATING PLANT, UNIT 1
AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE
Amendment No. 211 Renewed License No. NPF-68
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Renewed Facility Operating License No. NPF-68 filed by the Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated September 17, 2021, as supplemented on October 21, 2021, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 3
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-68 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A, as revised through Amendment No. 211, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of it s date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-68 and the Technical Specifications
Date of Issuance: January 5, 2022
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY
OGLETHORPE POWER CORPORATION
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
CITY OF DALTON, GEORGIA
DOCKET NO. 50-425
VOGTLE ELECTRIC GENERATING PLANT, UNIT 2
AMENDMENT TO RENEWED FACI LITY OPERATING LICENSE
Amendment No. 194 Renewed License No. NPF-81
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Renewed Facility Operating License No. NPF-81 filed by the Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated September 17, 2021, as supplemented on October 21, 2021, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I;
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I;
D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
Enclosure 4
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-81 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A, as revised through Amendment No. 194, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Michael T. Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-81 and the Technical Specifications
Date of Issuance: January 5, 2022
ATTACHMENT
TO LICENSE AMENDMENT NO. 211
VOGTLE ELECTRIC GENERATING PLANT, UNIT 1
RENEWED FACILITY OPERATING LICENSE NO. NPF-68
DOCKET NO. 50-424
AND
TO LICENSE AMENDMENT NO. 194
VOGTLE ELECTRIC GENERATING PLANT, UNIT 2
RENEWED FACILITY OPERATING LICENSE NO. NPF-81
DOCKET NO. 50-425
Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages
License License
License No. NPF-68, page 4 License No. NPF-68, page 4 License No. NPF-81, page 3 License No. NPF-81, page 3
TSs TSs
5.5-7 5.5-7 5.5-8 5.5-8 5.5-9 5.5-9 5.5-10 5.5-10 5.5-11 -------
5.6-6 5.6-6
5.6-7
(1) Maximum Power Level
Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A, as revised through Amendment No. 211, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Southern Nuclear Operating Company shall be capable of establishing containment hydrogen monitoring within 90 minutes of initiating safety injection following a loss of coolant accident.
(4) Deleted
(5) Deleted
(6) Deleted
(7) Deleted
(8) Deleted
(9) Deleted
(10) Mitigation Strategy License Condition
The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:
(a) Fire fighting response strategy with the following elements:
- 1. Pre-defined coordinated fire response strategy and guidance
- 2. Assessment of mutual aid fire fighting assets
- 3. Designated staging areas for equipment and materials
- 4. Command and control
- 5. Training and response personnel
(b) Operations to mitigate fuel damage considering the following:
- 1. Protection and use of personnel assets
- 2. Communications
- 3. Minimizing fire spread
- 4. Procedures for Implementing integrated fire response strategy
- 5. Identification of readily-available pre-staged equipment
- 6. Training on integrated fire response strategy
Renewed Operating License NPF-68 Amendment No. 211
(2) Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, pursuant to the Act and 10 CFR Part 50, to possess but not operate the facility at the designated location in Burke County, Georgia, in accordance with the procedures and limitations set forth in this license;
(3) Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended;
(4) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
(5) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components;
(6) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as my be produced by the operation of the facility authorized herein.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.
(1) Maximum Power Level
Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3625.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan
The Technical Specifications contained in Appendix A, as revised through Amendment No. 194 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be performed immediately upon implementation of Amendment No. 74. The SRs listed below shall be
Renewed Operating License NPF-81 Amendment No. 194 3URJUDPVDQG0DQXDOV
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
RELATED TO
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2
AMENDMENT NO. 238 TO RENEWED FACILITY OPERATING LICENSE NPF-2
AMENDMENT NO. 235 TO RENEWED FACILITY OPERATING LICENSE NPF-8
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NOS. 50-348, AND 50-364
1.0 INTRODUCTION
By application dated September 17, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21263A223), as supplemented by letter dated October 21, 2021 (ADAMS Accession No. ML21298A244, Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) for the Joseph M.
Farley Nuclear Plant (Farley), Units 1 and 2.
In its application, SNC requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the Farley Steam Generator (SG)
Program and Steam Generator (SG) Tube Inspection Report technical specifications (TSs) based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections (TSTF-577) (ADAMS Accession No. ML21060B434), and the associated NRC staff safety evaluation (SE) of TSTF-577 (ADAMS Accession No. ML21098A188).
The tubes within an SG function as an integral part of the reactor coolant pressure boundary and, in addition, isolate fission products in the primary coolant from the secondary coolant and the environment. SG tube integrity means that the tubes are capable of performing this safety function in accordance with the plant design and licensing basis.
The current Farley, Units 1 and 2, SG TS requirements are based on TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (ADAMS Accession No. ML110610350). The Farley, Units 1 and 2, SG tubes are made from Thermally Treated Alloy 690 (Alloy 690TT).
The supplemental letter dated October 21, 2021, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no signific ant hazards consideration determination as published in the Federal Register on November 2, 2021 (86 FR 60485).
Enclosure 5
1.1 Proposed TS Changes to Adopt TSTF-577
In accordance with NRC staff-approved TSTF-577, the licensee proposed changes that would revise Farley TS 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator (SG) Tube Inspection Report. Specifically, the licensee proposed the following changes to adopt TSTF-577:
TS 5.5.9, Steam Generator (SG) Program:
x The introductory paragraph to TS 5.5.9 would be revised by replacing steam generator with SG in a couple instances.
x TS 5.5.9.d.2 would be revised by deleting the requirement to base inspection frequency on the more restrictive metric between either the effective full power months (EFPM) or refueling outage and to use just the EFPM metric.
x TS 5.5.9.d.2 would be revised by deleting the requirement to inspect 100 percent of the tubes during each period in paragraphs d.2.a, d.2.b, d.2.c, and d.2.d (144, 120, 96, and 72 EFPM, respectively) and by adding the re quirement to inspect 100 percent of the tubes in each SG at least every 96 EFPM.
x TS 5.5.9.d.2 would be revised by deleting the allowance to extend the inspection period by up to 3 EFPM and by deleting the discussion of prorating inspections.
x TS 5.5.9.d.3 would be revised by replacing shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections) with shall be at the next refueling outage.
TS 5.6.10, Steam Generator (SG) Tube Inspection Report:
x Existing reporting requirement b. would be renumbered as c. and be revised by editorial and punctuation changes.
x New reporting requirement b. would be added to require the nondestructive examination (NDE) techniques utilized for tubes with increased degradation susceptibility to be reported.
x Existing reporting requirement c. would be renumbered as c.1. and be revised by editorial and punctuation changes.
x Existing reporting requirement d. would be renumbered as c.2. and be revised to note that the location, orientation (if linear), measured size (if available), and voltage response do not need to be reported for tube wear indications at support structures that are less than 20 percent through-wall. However, the total number of tube wear indications at support structures that are less than 20 percent through-wall would be reported.
x New reporting requirement d. would be added to require an analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection relative to the applicable performance criteria, including the an alysis, methodology, inputs, and results.
x Existing reporting requirement e. would be renumbered as c.4 and be revised by editorial and punctuation changes.
x Existing reporting requirement f. would be renumbered as e. and be revised by editorial and punctuation changes.
x New reporting requirement f. would be added to require the results of any SG secondary side inspections to be reported.
x Existing reporting requirement g. would be renumbered as c.3. and be revised to add the requirements to report a description of the condition monitoring assessment, the margin to the tube integrity performance criteria, and a comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment. In addition, the requirement to report the results of tube pulls and in-situ testing would be deleted.
1.2 Additional Proposed TS Changes
In addition to the changes proposed consistent with the traveler discussed in Section 1.1, SNC proposed the following variations.
1.2.1 Editorial Variations
The licensee identified one variation for Farley, Units 1 and 2. SNC noted that Farley TS 5.6.10 references the title of TS 5.5.9, Steam Generator (SG) Program, without placing the title within quotation marks. For consistency with TSTF-577 and the Standard Technical Specifications, a change is proposed to place the title within quotation marks.
2.0 REGULATORY EVALUATION
The regulations in Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.36(c)(5),
Administrative controls, state that [a]dministr ative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. Each licensee shall submit any reports to the Commission pursuant to approved technical specifications as specified in
[10 CFR] 50.4. Technical Specification Section 5.0, Administrative Controls, requires that a SG Program be established and implemented to ensure that SG tube integrity is maintained.
Programs established by the licensee, including the SG Program, are listed in the administrative controls section of the TS to operate the facility in a safe manner.
The NRC staffs guidance for the review of TSs is in NUREG-0800, Standard Review Plan
[SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition, Chapter 16.0, Technical Specifications, Revision 3, dated March 2010 (ADAMS Accession No. ML100351425).
As described therein, as part of the regulatory standardization effort, the NRC staff has prepared Standard Technical Specifications (STSs ) for each of the LWR nuclear designs.
Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-1431, 1 as modified by NRC-approved travelers.
TSTF-577 revised the STSs related to SG tube inspections and SG tube inspection reporting requirements. The NRC approved TSTF-577, under the CLIIP on April 14, 2021 (ADAMS Package Accession No. ML21099A086).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-577
The NRC staff compared the licensees proposed TS changes in Section 1.1 of this SE against the changes approved in TSTF-577. In accordance with SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-577 are applicable because Farley is a Pressurized-Water Reactor (PWR) design plant, and the NRC staff approved the TSTF-577 changes for PWR designs. The NRC staff finds that the licensees proposed changes to the Farley, Units 1 and 2, TSs in Section 1.1 of this SE are consistent with those found acceptable in the NRC staff review of TSTF-577.
In the SE of TSTF-577, the NRC staff concluded that the TSTF-577 changes to STS 5.5.9, Steam Generator (SG) Program, and STS 5.6.7, Steam Generator Tube Inspection Report, were acceptable because, as discussed in Section 3.0 of that SE, they continued to ensure SG tube integrity and, therefore, protected the public health and safety. In particular, the structural integrity performance criterion and accident-induced l eakage performance criterion (explained in STS 5.5.9.b, Items 1 and 2, respectively) will continue to be met with the proposed revised SG inspection intervals (maximum allowable time be tween SG inspections) and inspection periods (maximum allowable time between 100 percent of SG tubes inspections). Additionally, the proposed changes to the reporting requirements will provide more detailed and consistent information to the NRC. Therefore, the NRC staff found that the proposed changes to the SG program and inspection reporting requirements were acceptable because they continued to meet the requirements of 10 CFR 50.36(c)(5) by pr oviding administrative controls necessary to assure operation of the facility in a safe manner. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the Farley, Units 1 and 2, TSs in Section 1.1 of this SE, which incorporate the changes made in TSTF-577, continue to meet the requirements of 10 CFR 50.36(c)(5).
3.2 Additional Proposed TS Changes
3.2.1 Editorial
SNC identified one variation. The licensee noted that Farley, Units 1 and 2, TS 5.6.10 references the title of TS 5.5.9, Steam Generator (SG) Program, without placing the title within quotation marks. The NRC staff finds that placing the title within quotation marks is acceptable because it is administrative in nature, consistent with the STS, and does not substantively alter TS requirements. The NRC staff also noted that Farley uses different numbering than the STS
1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Westinghouse Plants, NUREG-1431, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ADAMS Accession Nos. ML21259A155 and ML21259A159, respectively).
on which TSTF-577 was based. Specifically, Farley uses TS 5.6.10 for Steam Generator (SG)
Tube Inspection Report and the TSTF-577 uses TS 5.6.7. The NRC staff finds that the different TS numbering is acceptable because it does not substantively alter TS requirements.
3.3 TS Change Consistency
The NRC staff reviewed the proposed TS changes fo r technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Alabama State officials were notified on November 18, 2021, of the proposed issuance of the amendments. On November 19, 2021, the State official indicated the State of Alabama has no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment relates, in part, to changes in recordkeeping, reporting, or administrative procedures or requirements. The amendment also relates, in part, to changing requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no signif icant increase in individual or cumulative occupational radiation exposure. The Commissi on has previously issued a proposed finding that the amendment involves no significant hazards consideration (86 FR 60485 dated November 2, 2021), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for catego rical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Charley Peabody, Jr., NRR/DSS
Date: January 5, 2022
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
RELATED TO
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2
AMENDMENT NO. 211 TO RENEWED FACILITY OPERATING LICENSE NPF-68
AMENDMENT NO. 194 TO RENEWED FACILITY OPERATING LICENSE NPF-81
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NOS. 50-424, AND 50-425
1.0 INTRODUCTION
By application dated September 17, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21263A223), as supplemented by letter dated October 21, 2021 (ADAMS Accession No. ML21298A244, Southern Nuclear Operating Company (SNC, the licensee) submitted a licen se amendment request (LAR) for the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2.
In its application, SNC requested that the U.S. Nuclear Regulatory Commission (NRC, the Commission) process the proposed amendment under the Consolidated Line Item Improvement Process (CLIIP). The proposed changes would revise the Vogtle Steam Generator (SG)
Program and the Steam Generator Tube Inspection Report technical specifications (TSs )based on Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube In spections (TSTF-577) (ADAMS Accession No. ML21060B434), and the associated NRC staff safety evaluation (SE) of TSTF-577 (ADAMS Accession No. ML21098A188).
The tubes within an SG function as an integral part of the reactor coolant pressure boundary and, in addition, isolate fission products in the primary coolant from the secondary coolant and the environment. SG tube integrity means that the tubes are capable of performing this safety function in accordance with the plant design and licensing basis.
The current Vogtle, Units 1 and 2, SG TS requirements are based on TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (ADAMS Accession No. ML110610350). The Vogtle, Units 1 and 2, SG tubes are made from Thermally Treated Alloy 600 (Alloy 600TT).
Enclosure 6
The supplemental letter dated October 21, 2021, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staffs original proposed no signif icant hazards consideration determination as published in the Federal Register on November 2, 2021 (86 FR 60485).
1.1 Proposed TS Changes to Adopt TSTF-577
In accordance with NRC staff-approved TSTF-577, the licensee proposed changes that would revise Vogtle, Units 1 and 2, TS 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report. Specifically, the licensee proposed the following changes to adopt TSTF-577:
TS 5.5.9, Steam Generator (SG) Program:
x TS 5.5.9 introductory paragraph and paragraph b.1 would be revised by replacing steam generator with SG in a few instances.
x TS 5.5.9.d would be revised by adding a phrase regarding portions of the tube that are exempt from inspection by alternate repair criteria that replaces information that specifies distance from the top of the tubesheet.
x TS 5.5.9.d.2 would be revised by changing the requirement to inspect 100 percent of the tubes at periods of 120, 96, and 72 effective full power months (EFPM) to 54 EFPM.
A 72 EFPM inspection period would be permitted if none of the SG tubes have ever experienced cracking (not including regions exempt from inspection by alternate repair criteria) and the SG inspection was performed with enhanced probes. A description of the enhanced probe inspection would be added.
x TS 5.5.9.d.2 would be revised by deleting the requirement to base inspection frequency on the more restrictive metric between either the EFPM or refueling outage and to use just the EFPM metric.
x TS 5.5.9.d.2 would be revised by deleting the allowance to extend the inspection period by 3 months and by deleting the discussion of prorating inspections.
x TS 5.5.9.d.3 would be revised by replacing shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent inspections) with shall be at the next refueling outage.
x TS 5.5.9.d.3 would be revised by adding a phrase regarding portions of the tube that are exempt from inspection by alternate repair criteria that replaces the phrase, not excluded above. An additional phrase would be added that permits deferring SG inspections after cracking indications are found if the 100 percent inspection of all SGs was performed with enhanced probes.
TS 5.6.10, Steam Generator Tube Inspection Report:
x Existing reporting requirement b. would be renumbered as c. and be revised by editorial and punctuation changes.
x New reporting requirement b. would be added to require the nondestructive examination (NDE) techniques utilized for tubes with increased degradation susceptibility to be reported.
x Existing reporting requirement c. would be renumbered as c.1. and be revised by editorial and punctuation changes.
x Existing reporting requirement d. would be renumbered as c.2. and be revised to note that the location, orientation (if linear), measured size (if available), and voltage response do not need to be reported for tube wear indications at support structures that are less than 20 percent through-wall. However, the total number of tube wear indications at support structures that are less than 20 percent through-wall would be reported.
x New reporting requirement d. would be added to require an analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection relative to the applicable performance criteria, including the an alysis, methodology, inputs, and results.
x Existing reporting requirement e. would be renumbered as c.4. and be revised by editorial and punctuation changes.
x Existing reporting requirement f. would be renumbered as e. and be revised by editorial and punctuation changes.
x New reporting requirement f. would be added to require the results of any SG secondary side inspections to be reported.
x Existing reporting requirement g. would be renumbered as c.3. and be revised to add the requirements to report a description of the condition monitoring assessment, the margin to the tube integrity performance criteria, and a comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment. In addition, the requirement to report the results of tube pulls and in-situ testing would be deleted.
x Existing reporting requirements h., i., and j. would be renumbered to g., h., and i.,
respectively and be revised by editorial and punctuation changes.
1.2 Additional Proposed TS Changes
In addition to the changes proposed consistent with the traveler discussed in Section 1.1, the licensee proposed the following variations.
1.2.1 Editorial Variations
The licensee noted that Vogtle, Units 1 and 2, TS 5.6.10 references the title of TS 5.5.9, Steam Generator (SG) Program, without placing the title within quotation marks. For consistency with TSTF-577 and the Standard Technical Specifications, a change is proposed to place the title within quotation marks.
1.2.2 Other Variations
SNC noted that the Vogtle, Units 1 and 2, SG Program TSs currently contain a provision for an alternate tube plugging criteria. The description of the alternate tube plugging criteria in the proposed change is equivalent to the description in the current TSs.
2.0 REGULATORY EVALUATION
The regulations in Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.36(c)(5),
Administrative controls, state that [a]dministr ative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. Each licensee shall submit any reports to the Commission pursuant to approved technical specifications as specified in
[10 CFR] 50.4. Technical Specification Section 5.0, Administrative Controls, requires that a SG Program be established and implemented to ensur e that SG tube integrity is maintained.
Programs established by the licensee, including the SG Program, are listed in the administrative controls section of the TS to operate the facility in a safe manner.
The NRC staffs guidance for the review of TSs is in NUREG-0800, Standard Review Plan
[SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition, Chapter 16.0, Technical Specifications, Revision 3, dated March 2010 (ADAMS Accession No. ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared Standard Technical Specifications (STSs) for each of the LWR nuclear designs. Accordingly, the NRC staffs review includes consideration of whether the proposed changes are consistent with NUREG-1431, 2 as modified by NRC-approved travelers.
TSTF-577 revised the STSs related to SG tube inspections and SG tube inspection reporting requirements. The NRC approved TSTF-577, under the CLIIP on April 14, 2021 (ADAMS Package Accession No. ML21099A086).
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-577
The NRC staff compared the licensees proposed TS changes in Section 1.1 of this SE against the changes approved in TSTF-577. In accordance with SRP Chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-577 are applicable, because Vogtle, Units 1 and 2, are a pressurized-water reactor (PWR) design plant and the NRC staff approved the TSTF-577 changes for PWR designs. The NRC sta ff finds that SNCs proposed changes to the Vogtle. Units 1 and 2, TSs in Section 1.1 of this SE are consistent with those found acceptable in the NRC staff review of TSTF-577.
In the SE of TSTF-577, the NRC staff concluded that the TSTF-577 changes to STS 5.5.9, Steam Generator (SG) Program, and STS 5.6.7, Steam Generator Tube Inspection Report, were acceptable because, as discussed in Section 3.0 of that SE, they continued to ensure SG
2 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, Westinghouse Plants, NUREG-1431, Volume 1, Specifications, and Volume 2, Bases, Revision 5, September 2021 (ADAMS Accession Nos. ML21259A155 and ML21259A159, respectively).
tube integrity and, therefore, protected the public health and safety. In particular, the structural integrity performance criterion and accident-induced l eakage performance criterion (explained in STS 5.5.9.b, items 1 and 2, respectively) will continue to be met with the proposed revised SG inspection intervals (maximum allowable time bet ween SG inspections) and inspection periods (maximum allowable time between 100 percent of SG tubes inspections). Additionally, the proposed changes to the reporting requirements will provide more detailed and consistent information to the NRC. Therefore, the NRC staff found that the proposed changes to the SG program and inspection reporting requirements were acceptable because they continued to meet the requirements of 10 CFR 50.36(c)(5) by providing administrative controls necessary to assure operation of the facility in a safe manner. For these same reasons, the NRC staff concludes that the corresponding proposed changes to the Vogtle, Units 1 and 2, TSs in Section 1.1 of this SE, which incorporate the changes made in TSTF-577, continue to meet the requirements of 10 CFR 50.36(c)(5).
3.2 Additional Proposed TS Changes
3.2.1 Editorial
The licensee noted that Vogtle, Units 1 and 2, TS 5.6.10 references the title of TS 5.5.9, Steam Generator (SG) Program, without placing the title within quotation marks. The NRC staff finds that placing the title within quotation marks is ac ceptable because it is administrative in nature, consistent with the STS, and does not substantiv ely alter TS requirements. The NRC staff also noted that Vogtle uses different numbering than the STS on which TSTF-577 was based.
Specifically, Vogtle uses TS 5.6.10 for Steam Generator Tube Inspection Report, and the TSTF-577 uses TS 5.6.7. The NRC staff finds that the different TS numbering is acceptable because it does not substantively alter TS requirements.
3.2.2 Other Variations
The licensee noted that the Vogtle, Units 1 and 2, SG Program TSs currently contain a provision for an alternate tube plugging criteria. The description of the alternate tube plugging criteria in the proposed change is equivalent to the description in the current TSs.
The current Vogtle, Units 1 and 2, TS that addresses alternate tube plugging criteria (i.e., TS 5.5.9.c.) reflects NRC-approved changes contained in Amendment No. 167 and Amendment No. 149 for the Vogtle, Units 1 and 2, respectively (ADAMS Accession No. ML12216A056). As part of the request to adopt TSTF-577, the licensee did not propose any changes to these criteria. Therefore, the NRC st aff considers the variation as information for awareness purposes, rather than a variation from the traveler or a change to the plant-specific TSs.
3.3 TS Change Consistency
The NRC staff reviewed the proposed TS changes fo r technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with Chapter 16.0 of the SRP and are therefore acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Georgia State officials were notified on November 18, 2021, of the proposed issuance of the amendments. On November 18, 2021, the State official indicated the State of Georgia has no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment relates, in part, to changes in recordkeeping, reporting, or administrative procedures or requirements. The amendment also relates, in part, to changing requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commissi on has previously issued a proposed finding that the amendment involves no significant hazards consideration (86 FR 60485 dated November 2, 2021), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for cat egorical exclusion set forth in 10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Charley Peabody, Jr., NRR/DSS
Date: January 5, 2022
ML21316A055 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC OGC - NLO NAME JLamb KGoldstein NJordan (MHamm for) CKreuzberger DATE 11/10/2021 12/13/2021 11/9/2021 12/8/2021 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley JLamb DATE 1/5/2022 1/5/2022