ML22210A031
| ML22210A031 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 08/30/2022 |
| From: | Joel Wiebe Plant Licensing Branch III |
| To: | Rhoades D Exelon Generation Co |
| Wiebe J | |
| References | |
| EPID L-2022-LLA-0067 | |
| Download: ML22210A031 (31) | |
Text
August 30, 2022 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer (CNO)
Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; AND BYRON STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS NOS. 230, 230, 230, AND 230, RESPECTIVELY, REGARDING ADOPTION OF TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER (TSTF) 501, REVISION 1, RELOCATE STORED FUEL OIL AND LUBE OIL VOLUME VALUES TO LICENSEE CONTROL (EPID L-2022-LLA-0067)
Dear Mr. Rhoades:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 230 to Renewed Facility Operating License No. NPF-72 and Amendment No. 230 to Renewed Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, respectively and Amendment No. 230 to Renewed Facility Operating License No. NPF-37 and Amendment No. 230 to Renewed Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated April 21, 2022, as supplemented by letter dated May 19, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML22111A300 and ML22139A152).
These amendments revise the Technical Specifications (TSs) 3.8.3, "Diesel Fuel Oil," by relocating the current stored diesel fuel oil numerical volume requirements from the TS to the TS Bases so that it may be modified under licensee control. The TS is modified so that the stored diesel fuel oil inventory will require that a 7-day supply be available for each diesel generator. The amendments are consistent with TSTF-501, Revision 1, "Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control."
A copy of the Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Joel S. Wiebe, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, and STN 50-455
Enclosures:
- 1. Amendment No. 230 to NPF-72
- 2. Amendment No. 230 to NPF-77
- 3. Amendment No. 230 to NPF-37
- 4. Amendment No. 230 to NPF-66
- 5. Safety Evaluation cc: Listserv
CONSTELLATION ENERGY GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 230 Renewed License No. NPF-72
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated April 21, 2022, as supplemented by letter dated May 19, 2022, 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.
- 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-72 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 230, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 30, 2022 Nancy L.
Salgado Digitally signed by Nancy L. Salgado Date: 2022.08.30 12:20:03 -04'00'
CONSTELLATION ENERGY GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 230 Renewed License No. NPF-77
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated April 21, 2022, as supplemented by letter dated May 19, 2022, 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.
- 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-77 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 230, and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 30, 2022 Nancy L.
Salgado Digitally signed by Nancy L. Salgado Date: 2022.08.30 12:20:35 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 230 AND 230 RENEWED FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Renewed Facility Operating 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 INSERT License No. NPF-72 License No. NPF-72 Page 3 Page 3 License No. NPF-77 License No. NPF-77 Page 3 Page 3 TSs TSs 3.8.1 - 7 3.8.1 - 7 3.8.3 - 1 3.8.3 - 1 3.8.3 - 2 3.8.3 - 2 Renewed License No. NPF-72 Amendment No. 230 (2)
Constellation Energy Generation, LLC, 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; (3)
Constellation Energy Generation, LLC, 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; (4)
Constellation Energy Generation, LLC, 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; and (5)
Constellation Energy Generation, LLC, 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 incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 230 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Renewed License No. NPF-77 Amendment No. 230 (2)
Constellation Energy Generation, LLC, 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; (3)
Constellation Energy Generation, LLC, 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; (4)
Constellation Energy Generation, LLC, 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; and (5)
Constellation Energy Generation, LLC, 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.
The 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 incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 230 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
AC Sources-Operating 3.8.1 BRAIDWOOD UNITS 1 & 2 3.8.1 7 Amendment 230221 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains one hour supply of fuel oil.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.5 Check for and remove accumulated water from each day tank.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.6 Verify the fuel oil transfer system operates to automatically transfer fuel oil from storage tank(s) to the day tank.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.7 Verify each DG starts from normal standby condition and achieves:
a.
In 10 seconds, voltage 3950 V and frequency 58.8 Hz; and b.
Steady state voltage 3950 V and 4370 V, and frequency 59.5 Hz and 60.5 Hz.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.8 Verify manual transfer of AC power sources from the required normal qualified circuit(s) to the reserve required qualified circuit(s).
In accordance with the Surveillance Frequency Control Program (continued)
Diesel Fuel Oil 3.8.3 BRAIDWOOD UNITS 1 & 2 3.8.3 1 Amendment 23098 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil LCO 3.8.3 The stored diesel fuel oil shall be within limits for each required Diesel Generator (DG).
APPLICABILITY:
When associated DG is required to be OPERABLE.
ACTIONS
NOTE-------------------------------------
Separate Condition entry is allowed for each DG.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more DGs with stored fuel volume less than a 7 day supply and greater than a 6 day supply in storage tank(s).
A.1 Restore stored fuel oil volume to within limits.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> B.
One or more DGs with stored fuel oil total particulates not within limit.
B.1 Restore fuel oil total particulates within limit.
7 days C.
One or more DGs with new fuel oil properties not within limits.
C.1 Restore stored fuel oil properties to within limits.
30 days (continued)
Diesel Fuel Oil 3.8.3 BRAIDWOOD UNITS 1 & 2 3.8.3 2 Amendment 2301623230235 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and associated Completion Time of Conditions A, B, or C not met.
OR One or more DGs with diesel fuel oil not within limits for reasons other than Condition A, B, or C.
D.1 Declare associated DG inoperable.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each DG fuel oil storage tank(s) contains 7 day supply of fuel.
In accordance with the Surveillance Frequency Control Program SR 3.8.3.2 Verify fuel oil properties of new and stored fuel oil are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program.
In accordance with the Diesel Fuel Oil Testing Program SR 3.8.3.3 Check for and remove accumulated water from each fuel oil storage tank.
In accordance with the Surveillance Frequency Control Program
CONSTELLATION ENERGY GENERATION COMPANY, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 230 Renewed License No. NPF-37
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated April 21, 2022, as supplemented by letter dated May 19, 2022, 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.
- 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-37 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 230, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 30, 2022 Nancy L.
Salgado Digitally signed by Nancy L. Salgado Date: 2022.08.30 12:22:05 -04'00'
CONSTELLATION ENERGY GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 230 Renewed License No. NPF-66
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated April 21, 2022, as supplemented by letter dated May 19, 2022, 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.
2.
Accordingly, the renewed operating 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-66 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 230, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: August 30, 2022 Nancy L.
Salgado Digitally signed by Nancy L. Salgado Date: 2022.08.30 12:22:41 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 230 AND 230 RENEWED FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Renewed Facility Operating License 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 INSERT License No. NPF-37 License No. NPF-37 Page 3 Page 3 License No. NPF-66 License No. NPF-66 Page 3 Page 3 TSs TSs 3.8.1 - 7 3.8.1 - 7 3.8.3 - 1 3.8.3 - 1 3.8.3 - 2 3.8.3 - 2 Renewed License No NPF-37 Amendment No. 230 (2)
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 Updated Final Safety Analysis Report, as supplemented and amended; (3)
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; (4)
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; and (5)
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.
The 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 incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 230 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
(4)
Deleted.
Renewed License No. NPF-66 Amendment No. 230 (2)
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 Updated Final Safety Analysis Report, as supplemented and amended; (3)
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; (4)
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; and (5)
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.
The 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 incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 230, and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
AC Sources-Operating 3.8.1 BYRON UNITS 1 & 2 3.8.1 7 Amendment 230224 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains one hour supply of fuel oil.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.5 Check for and remove accumulated water from each day tank.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.6 Verify the fuel oil transfer system operates to automatically transfer fuel oil from storage tank(s) to the day tank.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.7 Verify each DG starts from normal standby condition and achieves:
a.
In 10 seconds, voltage 3950 V and frequency 58.8 Hz; and b.
Steady state voltage 3950 V and 4370 V, and frequency 59.5 Hz and 60.5 Hz.
In accordance with the Surveillance Frequency Control Program SR 3.8.1.8 Verify manual transfer of AC power sources from the required normal qualified circuit(s) to the reserve required qualified circuit(s).
In accordance with the Surveillance Frequency Control Program (continued)
Diesel Fuel Oil 3.8.3 BYRON UNITS 1 & 2 3.8.3 1 Amendment 230106 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil LCO 3.8.3 The stored diesel fuel oil shall be within limits for each required Diesel Generator (DG).
APPLICABILITY:
When associated DG is required to be OPERABLE.
ACTIONS
NOTE-------------------------------------
Separate Condition entry is allowed for each DG.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more DGs with stored fuel volume less than a 7 day supply and greater than a 6 day supply in storage tank(s).
A.1 Restore stored fuel oil volume to within limits.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> B.
One or more DGs with stored fuel oil total particulates not within limit.
B.1 Restore fuel oil total particulates within limit.
7 days C.
One or more DGs with new fuel oil properties not within limits.
C.1 Restore stored fuel oil properties to within limits.
30 days (continued)
Diesel Fuel Oil 3.8.3 BYRON UNITS 1 & 2 3.8.3 2 Amendment 230171 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and associated Completion Time of Conditions A, B, or C not met.
OR One or more DGs with diesel fuel oil not within limits for reasons other than Condition A, B, or C.
D.1 Declare associated DG inoperable.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each DG fuel oil storage tank(s) contains a 7 day supply of fuel.
In accordance with the Surveillance Frequency Control Program SR 3.8.3.2 Verify fuel oil properties of new and stored fuel oil are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program.
In accordance with the Diesel Fuel Oil Testing Program SR 3.8.3.3 Check for and remove accumulated water from each fuel oil storage tank.
In accordance with the Surveillance Frequency Control Program
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 230 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-72 AMENDMENT NO. 230 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-77 AMENDMENT NO. 230 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-37 AND AMENDMENT NO. 230 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-66 CONSTELLATION ENERGY GENERATION, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-456, 50-457, 50-454, AND 50-455
1.0 INTRODUCTION
By application dated April 21, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22111A300), as supplemented by letter dated May 19, 2022 (ML22139A152), Constellation Energy Generation, LLC (CEG, the licensee), submitted a license amendment request (LAR) to modify the technical specifications (TSs) for Braidwood Station (BWD), Units 1 and 2, and Byron Station (BYR), Unit Nos. 1 and 2. The proposed changes would revise TS 3.8.3, Diesel Fuel Oil, and Surveillance Requirement (SR) 3.8.3.1 (verification of fuel oil storage tank volume), by removing the current stored diesel fuel oil numerical volume requirements and replacing them with duration-based diesel operating time requirements, consistent with Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (ML090510686). The availability of this TS improvement was published in the Federal Register on May 26, 2010 (75 FR 29588), as part of the consolidated line item improvement process (CLIIP). In addition, the licensee proposed changes that would revise SR 3.8.1.4 (verification of day tank fuel oil volume) to replace the specific day tank numerical volume requirement with a duration-based diesel operating time requirement.
The licensee also proposed associated changes to the TS Bases.
Any change to the numerical volume requirements in the TSs requires prior approval by the U.S. Nuclear Regulatory Commission (NRC or the Commission). Licensees may need to modify diesel fuel oil numerical volumes to account for changes to the energy content (British Thermal Units (BTU)/gallon) of available fuel oils in the market. Fluctuations in energy content could be caused by a variety of factors including changes to regulatory requirements. The proposed changes would remove the numerical volume requirements for stored diesel fuel oil from the TSs and would replace them with duration-based diesel operating time requirements. This amendment would permit the numerical volume requirements for stored diesel fuel oil to be modified under licensee control pursuant to Title 10 of the Code of Federal Regulations (10 CFR) section 50.59, Changes, tests, and experiments, and, therefore, would not require prior NRC review under 10 CFR 50.90.
The supplement dated May 19, 2022, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC or the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on June 14, 2022 (87 FR 36006).
2.0 REGULATORY EVALUATION
2.1
System Description
The onsite (emergency) alternating current (AC) power sources are a part of the primary success path and function or actuate to mitigate a design-basis accident or transient that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier.
Diesel fuel oil requirements are retained in the TSs as a limiting condition for operation (LCO) under 10 CFR 50.36(c)(2)(i) because they support the operation of the emergency AC power sources.
The BWD and BYR emergency AC power system for each unit is powered by two diesel generators (DGs). The DGs provide an independent emergency source of power in the event of a complete loss of offsite power. The DGs supply all of the electrical loads necessary for reactor safe shutdown either with or without a loss-of-coolant accident. The DG support systems, such as fuel oil and cooling water, are necessary for operation of each DG.
The design bases for the fuel oil storage and transfer system are to provide each of the two diesel engine generator sets with sufficient bulk storage for 7 days of operation under post-accident generator loads that will occur during the 7-day interval. There are two fuel oil transfer pumps for each engine, each pump capable of transferring oil from the diesel oil storage tank to its corresponding day tank. Each fuel oil day tank provides enough fuel to allow a minimum of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of DG operation at full load plus ten percent.
2.2 Description of the Proposed Changes The proposed changes would revise TS 3.8.3, Diesel Fuel Oil, and SRs 3.8.3.1 and 3.8.1.4 by removing the current stored diesel fuel oil volume numerical requirements and replacing them with duration-based diesel operating time requirements. The proposed changes would mean that the volume necessary to meet the TS duration requirements may be modified under licensee control. The specific TS changes are described in the following sections.
2.2.1 Proposed Changes to TS 3.8.3 Actions Table Condition A Condition A of TS LCO 3.8.3 would be revised in the Actions table. Currently, Condition A applies when the stored diesel fuel oil numerical volume requirement is not met. As discussed in the TS Bases, the numerical diesel fuel oil volume requirement in Condition A is based on a combined volume of less than a 7-day supply, but at least a 6-day supply. The proposed amendment would remove the numerical volume requirement from the TSs and replace it with a duration-based requirement. Specifically, the TSs would be modified so that Condition A is entered when the stored diesel fuel oil is less than a 7-day supply, but greater than a 6-day supply for one or more DGs.
2.2.2 Proposed Changes to SR 3.8.3.1 and SR 3.8.1.4 Currently, SR 3.8.3.1 requires the licensee to verify each DG fuel oil storage tank contains a volume greater than or equal to 44,000 gallons of fuel oil. Currently, SR 3.8.1.4 requires the licensee to verify that each day tank contains a volume greater than or equal to 450 gallons of fuel oil. As described in the current TS Bases, the numerical requirement in SRs 3.8.3.1 is based on maintaining at least a 7-day supply, while the numerical requirement in SR 3.8.1.4 is based on a 1-hour supply at full load plus 10 percent. The proposed amendment would remove the numerical volume requirements from these SRs. SR 3.8.3.1 would be revised to require the licensee to verify that the stored diesel fuel oil volume is greater than or equal to a 7-day supply for each DG. SR 3.8.1.4 would be revised to require the licensee to maintain a minimum 1-hour supply of fuel oil.
2.3 Licensee-Identified Differences with TSTF-501, Revision 1 In LAR, section 2.1, Variations, the licensee proposed four variations from TSTF-501, Revision 1, as described below:
Variation 1: BWD and BYR SR 3.8.1.4, concerning fuel oil day tank inventory, currently specifies verification of greater than or equal to a minimum volume of fuel oil. The licensee proposed a revision to SR 3.8.1.4 to remove the day tank volume requirement and replace it with a duration-based requirement.
Variation 2: BWD and BYR calculations that determine fuel oil volumes do not include the fuel oil volume required to support periodic testing. Instead, the licensee administratively controls fuel oil in support of periodic testing.
Variation 3: BWD and BYR application contains editorial variations from the model application. In some instances, Division 1 and Division 2 DGs are referred to as Train A and Train B DGs. This is an editorial variation to comport with how the BWD and BYR refer to the DGs.
Variation 4: Traveler TSTF-501 references lube oil levels in the proposed TS changes. BWD and BYR do not reference lube oil levels in the applicable BWD and BYR TS sections and are, therefore, intentionally excluded from discussion.
2.4 Regulatory Requirements and Guidance Used in the Evaluation of the Changes 2.4.1 Regulatory Requirements The regulation in 10 CFR 50.36, Technical specifications, provides the regulatory requirements for the content of the TSs and requires, in part, that a summary statement of the bases for such specifications shall be included by applicants for a license authorizing operation of a production or utilization facility. Specifically, 10 CFR 50.36(c) requires that TSs include items in five specific categories related to station operation. These categories are: (1) safety limits, limiting safety system settings, and limiting control settings, (2) LCOs, (3) SRs, (4) design features, and (5) administrative controls.
The regulation in 10 CFR 50.36(c)(2), Limiting conditions for operation, states, in part, that TSs will include LCOs, which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. Section 50.36(c)(2)(i) of 10 CFR further states that [w]hen a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
The regulation in 10 CFR 50.36(c)(3), Surveillance requirements, states that [s]urveillance requirements are requirements related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
2.4.2 Guidance Regulatory Guide (RG) 1.137, Revision 1, Fuel-Oil Systems for Standby Diesel Generators (ML003740180), provides guidance that describes a method acceptable to the NRC staff for complying with the Commissions regulations regarding fuel oil systems for standby DGs and endorses American National Standards Institute (ANSI) Standard ANSI N195-1976, Fuel Oil Systems for Standby Diesel Generators, with certain limitations. RG 1.137, section C.1.c sets forth two methods for the calculation of fuel oil storage requirements as described in ANSI N195-1976, Section 5.4 Calculation of Fuel Oil Storage Requirements. These methods are: (1) calculations based on the assumption that the DG operates continuously for 7 days at its rated capacity, and (2) calculations based on the time-dependent loads of the DG. If the time-dependent load method is used, the minimum required capacity should include the capacity to power engineered safety features.
NUREG-1431, Revision 5, Standard Technical Specifications for Westinghouse Plants, Volume 1, Specifications (ML21259A155), provides example TS LCOs and acceptable remedial actions that meet the requirements in 10 CFR 50.36(c)(2)(i) for a standard plant design.
The NRC-approved Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (ML090510686), provides an acceptable method of modifying the stored fuel oil and lube oil requirements contained in the STS.
3.0 TECHNICAL EVALUATION
The licensee assessed the model safety evaluation (SE), which was published in the Federal Register on May 26, 2010 (75 FR 29588), as part of the CLIIP notice of availability. The licensee concluded, as stated on page 3 of Attachment 1 of the LAR, that the justifications presented in the model SE are applicable to BWD and BYR, and therefore justify the proposed changes to the BWD and BYR TSs.
Each DG is provided with a fuel oil capacity sufficient to operate that DG for a period of 7 days.
This onsite fuel oil capacity is sufficient to operate the DGs long enough to place BWD and BYR in a shutdown condition and to bring in replenishment fuel oil from offsite sources.
The standby (emergency) AC power sources (i.e., the DGs), are a part of the primary success path and function or actuate to mitigate a design-basis accident or transient that either assumes the failure of, or presents a challenge to the integrity of, a fission product barrier. Requirements for diesel fuel oil supplies are retained in the TSs under 10 CFR 50.36(c)(2)(i) because they support the operation of the standby AC power sources.
The proposed changes would revise TS 3.8.3 and SRs 3.8.3.1 and 3.8.1.4 by removing the current stored diesel fuel oil numerical volume requirements from the TSs and replacing them with the associated duration-based diesel operating times. These changes would permit the fuel oil volumes necessary to support a duration-based diesel operating time to be modified under licensee control pursuant to 10 CFR 50.59. The NRC staffs evaluation of the proposed TS changes is provided in the following sections.
3.1 NRC Staff Evaluation of Proposed Changes to TS 3.8.3 Actions Table Condition A Currently, Condition A of TS 3.8.3 is entered when the fuel oil volume requirement is not met.
The current TS Bases state that the numerical volume requirement in Condition A is based on a volume that is less than a 7-day supply, but at least a 6-day supply. The proposed change would modify Condition A by replacing the numerical volume requirements with duration-based diesel operating time requirements, such that Condition A is entered when the stored fuel oil inventory is less than a 7-day supply, but greater than a 6-day supply for one or more DGs. No other parts of Condition A are proposed to be modified.
In LAR, Attachment 1, page 3 of 5, the licensee describes that the stored diesel fuel oil numerical volumes sufficient to meet the duration-based operating time requirements are calculated in accordance with the NRC-approved methodology described in RG 1.137, Revision 1, and ANSI N195-1976. The use of this NRC-approved methodology ensures that the supplies of stored diesel fuel oil for each DG that dictate condition entry conform to the assumptions in the safety analyses.
Based on the above evaluation, the NRC staff concludes that the changes to the TS 3.8.3 Actions table, Condition A, are acceptable.
3.2 NRC Staff Evaluation of Proposed Changes to SRs 3.8.3.1 and 3.8.1.4 Currently, SR 3.8.3.1 requires the licensee to verify that the stored diesel fuel oil numerical volume requirement is met. Currently, SR 3.8.1.4 requires the licensee to verify that each day tank contains the required volume of diesel fuel oil.
The licensee proposed to revise SR 3.8.3.1 to reflect the change from a numerical volume requirement to a duration-based requirement made in TS 3.8.3 Actions table, Condition A.
Specifically, SRs 3.8.3.1 would be revised to require availability of a 7-day supply of fuel oil for each DG, rather than a specified numerical volume. As a result, SR 3.8.3.1 would require the licensee to verify each DG fuel oil storage tank contains greater than or equal to a 7-day supply of fuel.
The licensee also proposed to revise SR 3.8.1.4, which contains the DG day tank volume requirement. The proposed change to SR 3.8.1.4 is similar to the proposed change for SR 3.8.3.1 in that the numerical volume requirement would be replaced with duration-based requirement. The revised SR 3.8.1.4 would require the licensee to verify each day tank contains greater than or equal to a 1-hour supply of fuel oil. The licensees proposed change to the day tank storage requirements in the LAR is identified as variation 1 in section 2.3 of this SE.
On page 2 of LAR, Attachment 1, the licensee describes how the volume of fuel oil necessary to support operation of the standby DGs is managed at the site, as follows:
BWD and BYR calculations that determine fuel oil volumes required to support operation of the DGs for the 7-days do not include an explicit allowance for fuel oil consumption due to periodic testing. Instead, BWD and BYR administratively controls fuel oil in support of required periodic testing, such that the required volumes for the fuel oil tanks are maintained.
This is identified as variation 2 in section 2.3 of this SE.
The methodology in ANSI N195-1976 discusses how the stored diesel fuel oil requirement can be calculated based upon the DGs operating at the minimum required capacity for the plant condition that is most limiting for the calculation of such capacity. One method for calculating the stored diesel fuel oil supply in ANSI N195-1976 considers the time dependence of DG loads.
That is, if DG loads increase or decrease during the event, the load changes should be included in the required fuel oil storage calculation. If the design includes provisions for an operator to supply power to equipment other than the minimum required for the plant condition, such additional loads should be included in the calculation of required fuel oil storage capacity.
Revision 1 of RG 1.137 supplements the above by stating that for the time-dependent load method, the minimum required capacity should include the capacity to power the engineered safety features. A minimum margin of 10 percent shall be added to the calculated storage requirement if the alternate conservative calculation discussed next is not used. Another method for calculating the stored diesel fuel oil supply, which is more conservative than the time-dependent load method, is to calculate the storage capacity by assuming that the diesel engine operates continuously for 7 days at its rated capacity.
Since both methods described in ANSI N195-1976 are approved for use by the NRC staff in RG 1.137, Revision 1, and the licensee calculates the volume of fuel oil in accordance with RG 1.137, Revision 1, the NRC staff has reasonable assurance that the volume of fuel oil calculated by the licensee will meet the new duration-based limits specified in SR 3.8.3.1 and SR 3.8.1.4. Additionally, the licensee will administratively control the amount of fuel oil required to support periodic testing, such that the volume of fuel oil required for testing will exist in addition to the 7-day supply requirement.
One variable used in both stored diesel fuel oil calculation methods is the fuel oil consumption rate. The property of diesel fuel oil having the most significant effect on the fuel oil consumption rate is the energy content (heating value) of the fuel oil. Standards exist that correlate the energy content to the fuel oils American Petroleum Institute (API) gravity or absolute specific gravity. At a minimum, licensees calculate the required fuel oil storage values for their plants assuming the most limiting API gravity or absolute specific gravity, and therefore, the most limiting fuel oil energy content. As long as the fuel oil placed in the storage tank is within the API gravity range or absolute specific gravity range specified by the licensee, the calculations of fuel oil consumption and required stored volume remain valid. SR 3.8.3.2 requires new fuel oil to be tested in accordance with and maintained within the limits of the diesel fuel oil testing program (TS 5.5.13), by determining in part, that the fuel oil has an API gravity or absolute specific gravity within limits.
The above methods still provide assurance that the necessary quantity and quality of diesel fuel oil will continue to be maintained and calculated in accordance with NRC-approved methods.
Variation 1 is acceptable because revising the day tank supply to a duration-based amount continues to provide assurance that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. The method used to calculate the day tank oil volumes is one of the acceptable methods provided in RG 1.137. Variation 2 is acceptable because the calculation method used to determine the volume of oil required to be controlled is one of the acceptable methods provided in RG 1.137 and continues to provide assurance that the necessary quality of systems and components is maintained, that facility operation will be within the safety limits, and that the LCOs will be met because only the calculated volume of oil, less testing volume, is necessary if the DG was used in an accident. Therefore, the NRC staff considers the duration-based changes to SRs 3.8.3.1 and 3.8.1.4 to be acceptable.
3.3 NRC Staff Evaluation of Licensee-Identified Differences with TSTF-501, Revision 1 The licensee-identified differences with TSTF-501, Revision 1, are described in section 2.3 of this SE. Variations 1 and 2 are dispositioned in section 3.2 of this SE. Variations 3 and 4 are discussed in this SE section.
Variation 3 described that the licensee uses train versus division to refer to BWD and BYR DGs. This licensee identified variation is only associated with the TS Bases for the day tank (variation 1). TS Bases changes are not subject to NRC approval. For TS Bases changes, see discussion in section 3.4 of this SE.
Variation 4 described that the TSTF-501 model application and SE reference lube oil levels in their evaluation and proposed TS changes. However, the licensee explained that BWD and BYR TSs applicable to the DGs do not contain lube oil level requirements in the context of this LAR (i.e., adopting TSTF-501), and were, therefore, intentionally excluded from discussion. The NRC staff considers this variation acceptable because the BWD and BYR TSs do not contain explicit DG lube oil level requirements and therefore, changes to lube oil level requirements in the context of adopting TSTF-501 are not applicable.
3.4 TS Bases Changes The regulation at 10 CFR 50.36(a)(1) states that a summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the TSs. Consistent with 10 CFR 50.36(a)(1), the licensee submitted corresponding TS Bases changes that provide the reasons for the proposed TSs changes. The licensee makes changes to the BWD and BYR TS Bases in accordance with TS 5.5.14, Technical Specifications (TS) Bases Control Program.
3.4 Technical Conclusion The proposed changes will continue to require that the appropriate volumes of stored diesel fuel oil be maintained. The proposed changes to TS 3.8.3 Actions table continue to provide assurance that the lowest functional capability or performance levels of equipment required for safe operation of the facility will continue to be met. Condition A of TS 3.8.3 Actions table continues to provide acceptable remedial actions to follow until LCO 3.8.3 can be met. The NRC staff concludes that replacement of the TS numerical value volume requirements with duration-based requirements does not change the current plant configuration or the current basis for fuel oil volume requirements. Therefore, the changes to TS 3.8.3 Actions table will continue to meet 10 CFR 50.36(c)(2) and are acceptable.
In addition, the proposed changes to SRs 3.8.3.1 and 3.8.1.4 continue to provide assurance that the necessary quality of systems and components is maintained, the facility will be within safety limits, and that the LCO will be met. The revised SRs will continue to meet 10 CFR 50.36(c)(3),
and are, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendment on July 28, 2022. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20, and changes surveillance requirements. The NRC staff has determined that the amendments involve 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 Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (June 14, 2022; 87 FR 36006). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The NRC staff 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 Commission's 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: C. Ashley Date of Issuance: August 30, 2022
ML22210A031 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC OGC - NLO NAME JWiebe SRohrer VCusumano KDowling DATE 8/5/22 8/4/22 07/12/2022 8/23/22 OFFICE NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME NSalgado JWiebe DATE 8/24/22 8/30/22