ML24079A076
| ML24079A076 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle  |
| Issue date: | 05/23/2024 |
| From: | Scott Wall Plant Licensing Branch III |
| To: | Rhoades D Constellation Energy Generation |
| Wall, SP | |
| References | |
| EPID L-2023-LLA-0121 | |
| Download: ML24079A076 (1) | |
Text
May 23, 2024 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNIT 2; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-264, REVISION 0 (EPID L-2023-LLA-0121)
Dear David P. Rhoades:
The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued the enclosed amendments (listed below) in response to the Constellation Energy Generation, LLC application dated August 30, 2023 (Agencywide Documents Access and Management System Accession No. ML23242A107).
- 1.
Amendment No. 253 to Facility Operating License No. NPF-62 for Clinton Power Station, Unit No. 1;
- 2.
Amendment No. 284 to Renewed Facility Operating License No. DPR-19 and Amendment No. 277 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, respectively;
- 3.
Amendment No. 263 to Renewed Facility Operating License No. NPF-11 and Amendment No. 248 to Renewed Facility Operating License No. NPF-18 for LaSalle County Station, Units 1 and 2, respectively;
- 4.
Amendment No. 196 to Renewed Facility Operating License No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2; and
- 5.
Amendment No. 300 to Renewed Facility Operating License No. DPR-29 and Amendment No. 296 to Renewed Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.
The amendments revise the technical specifications for each facility in accordance with Technical Specifications Task Force (TSTF) Traveler TSTF-264, Revision 0, 3.3.9 and 3.3.10 -
Delete Flux Monitors Specific Overlap Requirement SRs [Surveillance Requirements].
Specifically, the proposed changes delete SRs which verify the overlap between the source range monitor and the intermediate range monitor, and between the intermediate range monitor and the average power range monitor.
A copy of the NRC staffs Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-461, 50-237, 50-249, 50-373, 50-374, 50-410, 50-254, and 50-265
Enclosures:
- 1. Amendment No. 253 to NPF-62
- 2. Amendment No. 284 to DPR-19
- 3. Amendment No. 277 to DPR-25
- 4. Amendment No. 263 to NPF-11
- 5. Amendment No. 248 to NPF-18
- 6. Amendment No. 196 to NPF-69
- 7. Amendment No. 300 to DPR-29
- 8. Amendment No. 296 to DPR-30
- 9. Safety Evaluation
- 10. Notices and Environmental Findings cc: Listserv
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 253 License No. NPF-62
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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 Facility Operating License No. NPF-62 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 253, are hereby incorporated into this license. Constellation Energy Generation, LLC 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 Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:45:13 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 253 FACILITY OPERATING LICENSE NO. NPF-62 CLINTON POWER STATION, UNIT NO. 1 DOCKET NO. 50-461 Replace the following pages of the Facility Operating License and 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 NPF-62 License NPF-62 Page 3 Page 3 TSs TSs 3.3-4 3.3-4 3.3-7 3.3-7 Amendment No. 253 (4)
Constellation Energy Generation, LLC, pursuant to the Act and to 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)
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; (6)
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. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation; and (7)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.
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 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 Constellation Energy Generation, LLC is authorized to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 253, are hereby incorporated into this license.
Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
RPS Instrumentation 3.3.1.1 CLINTON 3.3-4 Amendment No. 2534 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 Deleted SR 3.3.1.1.7 Deleted SR 3.3.1.1.8 Calibrate the local power range monitors.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10 Calibrate the analog trip module.
In accordance with the Surveillance Frequency Control Program (continued)
RPS Instrumentation 3.3.1.1 CLINTON 3.3-7 Amendment No. 253 149 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.
Intermediate Range Monitors a.
Neutron Flux-High 2
4 H
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.15 122/125 divisions of full scale 5(a) 4 I
SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.13 SR 3.3.1.1.15 122/125 divisions of full scale b.
Inop 2
4 H
SR 3.3.1.1.4 SR 3.3.1.1.15 NA 5(a) 4 I
SR 3.3.1.1.5 SR 3.3.1.1.15 NA 2.
Average Power Range Monitors a.
Neutron Flux-High, Setdown 2
4 H
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15 20% RTP b.
Flow Biased Simulated Thermal Power - High 1
4 G
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17 0.55 W +
62% RTP and 113%
RTP(b) c.
Fixed Neutron Flux - High 1
4 G
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.17 120% RTP d.
Inop 1,2 4
H SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.15 NA (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b)
Allowable Value is < 0.55 (W-8) + 42.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 284 Renewed License No. DPR-19
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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. DPR-19 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 284, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 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 Jeffrey A. Whited, 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: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:46:01 -04'00'
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 277 Renewed License No. DPR-25
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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 3.B. of Renewed Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 277, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 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 Jeffrey A. Whited, 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: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:47:03 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 284 AND 277 RENEWED FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-237 AND 50-249 Replace the following pages of the Renewed Facility Operating Licenses and 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 DPR-19 License DPR-19 Page 3 Page 3 License DPR-25 License DPR-25 Page 4 Page 4 TSs TSs 3.3.1.1-5 3.3.1.1-5 3.3.1.1-9 3.3.1.1-9 Renewed License No. DPR-19 Amendment No. 284 (2)
Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear materials 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)
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 special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I; 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 steady state reactor core power levels not in excess of 2957 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. 284, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Operation in the coastdown mode is permitted to 40% power.
Renewed License No. DPR-25 Amendment No. 277
- f.
Surveillance Requirement 4.9.A.10 - Diesel Storage Tank Cleaning (Unit 3 and Unit 2/3 only)
Each of the above Surveillance Requirements shall be successfully demonstrated prior to entering into MODE 2 on the first plant startup following the fourteenth refueling outage (D3R14).
- 3.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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:
A.
Maximum Power Level The licensee is authorized to operate the facility at steady state power levels not in excess of 2957 megawatts (thermal), except that the licensee shall not operate the facility at power levels in excess of five (5) megawatts (thermal), until satisfactory completion of modifications and final testing of the station output transformer, the auto-depressurization interlock, and the feedwater system, as described in the licensees telegrams; dated February 26, 1971, have been verified in writing by the Commission.
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 277, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Restrictions Operation in the coastdown mode is permitted to 40% power.
RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-5 Amendment No. 284 / 27730 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.4
NOTE-------------------
Not required to be performed when entering MODE 2 from MODE 1 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform a functional test of each RPS automatic scram contactor.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 Deleted.
SR 3.3.1.1.7 Deleted.
SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program (continued)
RPS Instrumentation 3.3.1.1 Dresden 2 and 3 3.3.1.1-9 Amendment No. 284 / 27730 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.
Intermediate Range Monitors a.
Neutron FluxHigh 2
3 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.17 SR 3.3.1.1.18 121/125 divisions of full scale 5(a) 3 H
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.17 SR 3.3.1.1.18 121/125 divisions of full scale b.
Inop 2
5(a) 3 3
G H
SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.18 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.18 NA NA 2.
Average Power Range Monitors a.
Neutron FluxHigh, Setdown 2
2 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.15 SR 3.3.1.1.18 17.1% RTP b.
Flow Biased Neutron FluxHigh 1
2 F
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.18 SR 3.3.1.1.19 0.56 W
(continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) 0.56 W + 63.2% and 118.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 263 Renewed License No. NPF-11
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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-11 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 263, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in 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 Jeffrey A. Whited, 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: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:48:18 -04'00'
CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 248 Renewed License No. NPF-18
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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-18 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 248, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in 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 Jeffrey A. Whited, 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: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:48:45 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 263 AND 248 RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 Replace the following pages of the Renewed Facility Operating Licenses and 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 NPF-11 License NPF-11 Page 3 Page 3 License NPF-18 License NPF-18 Page 3 Page 3 TSs TSs 3.3.1.1-5 3.3.1.1-5 3.3.1.1-9 3.3.1.1-9
Renewed License No. NPF-11 Amendment No. 263 (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 LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
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 full power (3546 megawatts thermal).
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 263, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
DELETED (4)
DELETED (5)
DELETED Am. 198 09/16/10 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 Am. 263 05/23/24
Renewed License No. NPF-18 Amendment No. 248 (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 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 LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
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 full power (3546 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 248, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Am. 185 09/16/10 Am. 248 05/23/24
RPS Instrumentation 3.3.1.1 LaSalle 1 and 2 3.3.1.1-5 Amendment No. 263/248 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1.1.4
NOTE-------------------
Not required to be performed when entering MODE 2 from MODE 1 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 (Deleted)
SR 3.3.1.1.7 (Deleted)
SR 3.3.1.1.8 Calibrate the local power range monitors.
In accordance with the Surveillance Frequency Control Program (continued)
RPS Instrumentation 3.3.1.1 LaSalle 1 and 2 3.3.1.1-9 Amendment No. 263/2487 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.
- a. Neutron FluxHigh 2
3 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.15 123/125 divisions of full scale 5(a) 3 H
SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.13 SR 3.3.1.1.15 123/125 divisions of full scale
- b. Inop 2
3 G
SR 3.3.1.1.4 SR 3.3.1.1.15 NA 5(a) 3 H
SR 3.3.1.1.5 SR 3.3.1.1.15 NA 2.
Average Power Range Monitors
- a. Neutron FluxHigh, Setdown 2
2 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15 20% RTP b.
Flow Biased Simulated Thermal PowerUpscale 1
2 F
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11(b) (c)
SR 3.3.1.1.14 SR 3.3.1.1.15 0.61 W +
68.2% RTP and 115.5%
RTP(d)
- c. Fixed Neutron Flux-High 1
2 F
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.17 120% RTP (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b)
If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(c)
The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the nominal trip setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures (field setting) to confirm channel performance. The NTSP and the methodologies used to determine the as-found and the as-left tolerances are specified in the Technical Requirements Manual.
(d)
Allowable Value is 0.54 W + 55.9% RTP and 112.3% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
NINE MILE POINT NUCLEAR STATION, LLC LONG ISLAND LIGHTING COMPANY CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 196 Renewed License No. NPF-69
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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-69 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 196, are hereby incorporated into this license. Constellation Energy Generation, LLC 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 Jeffrey A. Whited, 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: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:49:18 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 196 RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, UNIT 2 DOCKET NO. 50-410 Replace the following pages of the Renewed Facility Operating License and 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 NPF-69 License NPF-69 Page 4 Page 4 TSs TSs 3.3.1.1-7 3.3.1.1-7 3.3.1.1-10 3.3.1.1-10 Renewed License No. NPF-69 Amendment 117 through 195,196 (1)
Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 196, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Fuel Storage and Handling (Section 9.1, SSER 4)*
- a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
- b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
- c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
- d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.
(4)
Turbine System Maintenance Program (Section 3.5.1.3.10 SER)
The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturers calculations of missile generation probabilities.
(Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III).
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.
RPS Instrumentation 3.3.1.1 NMP2 3.3.1.1-7 Amendment 91, 92, 151, 152, 186, 196 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Deleted SR 3.3.1.1.6 Deleted SR 3.3.1.1.7 Calibrate the local power range monitors.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 Calibrate the trip units.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10
NOTES -----------------------------
1.
For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
2.
For Function 2.e, the CHANNEL FUNCTIONAL TEST only requires toggling the appropriate outputs of the APRM.
Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program (continued)
RPS Instrumentation 3.3.1.1 NMP2 3.3.1.1-10 Amendment 91, 92, 123, 140, 151, 186, 196 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.
Intermediate Range Monitors a.
Neutron Flux Upscale 2
3 H
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.14 122/125 divisions of full scale 5(a) 3 I
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.13 SR 3.3.1.1.14 122/125 divisions of full scale b.
Inop 2
3 H
SR 3.3.1.1.4 SR 3.3.1.1.14 NA 5(a) 3 I
SR 3.3.1.1.4 SR 3.3.1.1.14 NA 2.
Average Power Range Monitors a.
Neutron Flux - Upscale, Setdown 2
3 per logic channel H
SR 3.3.1.1.2 SR 3.3.1.1.7 SR 3.3.1.1.10 SR 3.3.1.1.13 20% RTP b.
Flow Biased Simulated Thermal Power - Upscale 1
3 per logic channel G
SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.7 SR 3.3.1.1.10 SR 3.3.1.1.13(c)(d) 0.61W +
63.4% RTP and 115.5%
RTP(b)(e) c.
Fixed Neutron Flux - Upscale 1
3 per logic channel G
SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.7 SR 3.3.1.1.10 SR 3.3.1.1.13 120% RTP d.
Inop 1,2 3 per logic channel H
SR 3.3.1.1.7 SR 3.3.1.1.10 NA (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b)
Allowable Value is.50(W - 5%) + 53.5% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
(c)
If the As-Found channel setpoint is outside its predefined As-Found tolerances, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(d)
The instrument channel setpoint shall be reset to a value within the As-Left tolerance around the nominal trip setpoint at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the nominal trip setpoint are acceptable provided that the As-Found and As-Left tolerances apply to the actual setpoint implemented in the surveillance procedures to confirm channel performance. The nominal trip setpoint and the methodologies used to determine the As-Found and the As-Left tolerances are specified in the Bases associated with the specified function.
(e)
With OPRM Upscale (function 2.e) inoperable, reset the APRM-STP High scram setpoint to the values defined by the COLR to Implement the automated BSP Scram Region in accordance with Action F.2 of this Specification.
CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 300 Renewed License No. DPR-29
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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 3.B. of Renewed Facility Operating License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 300, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 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 Jeffrey A. Whited, 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: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:52:15 -04'00'
CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 296 Renewed License No. DPR-30
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Constellation Energy Generation, LLC dated August 30, 2023, 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 3.B. of Renewed Facility Operating License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 296, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
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 Jeffrey A. Whited, 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: May 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.05.23 16:52:51 -04'00'
ATTACHMENT TO LICENSE AMENDMENT NOS. 300 AND 296 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Renewed Facility Operating Licenses and 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 DPR-29 License DPR-29 Page 4 Page 4 License DPR-30 License DPR-30 Page 4 Page 4 TSs TSs 3.3.1.1-4 3.3.1.1-4 3.3.1.1-8 3.3.1.1-8 Renewed License No. DPR-29 Amendment No. 300 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 300, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 17, 2006.
Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The CSP was approved by License Amendment No. 249 as modified by License Amendment No. 259.
1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-30 Amendment No. 296 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 296, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 17, 2006.
Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The CSP was approved by License Amendment No. 244 and modified by License Amendment No. 254.
1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS Quad Cities 1 and 2 3.3.1.1-4 Amendment No. 300/2963 SURVEILLANCE FREQUENCY SR 3.3.1.1.4
NOTE-------------------
Not required to be performed when entering MODE 2 from MODE 1 until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform a functional test of each RPS automatic scram contactor.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 DELETED SR 3.3.1.1.7 DELETED SR 3.3.1.1.8 Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program (continued)
RPS Instrumentation 3.3.1.1 Quad Cities 1 and 2 3.3.1.1-8 Amendment No. 300/2963 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.
Intermediate Range Monitors a.
Neutron FluxHigh 2
3 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.16 SR 3.3.1.1.17 121/125 divisions of full scale 5(a) 3 H
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.16 SR 3.3.1.1.17 121/125 divisions of full scale b.
Inop 2
5(a) 3 3
G H
SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.17 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.17 NA NA 2.
Average Power Range Monitors a.
Neutron FluxHigh, Setdown 2
2 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.14 SR 3.3.1.1.17 17.1% RTP b.
Flow Biased Neutron FluxHigh 1
2 F
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.16 SR 3.3.1.1.17 SR 3.3.1.1.18 0.56 W
(continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) 0.56 W + 63.2% and 118.4% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 253 TO FACILITY OPERATING LICENSE NO. NPF-62 AMENDMENT NO. 284 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19 AMENDMENT NO. 277 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25 AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-11 AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-18 AMENDMENT NO. 196 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 AMENDMENT NO. 300 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 296 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 CONSTELLATION ENERGY GENERATION, LLC CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 LASALLE COUNTY STATION, UNITS 1 AND 2 NINE MILE POINT NUCLEAR STATION, UNIT 2 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-461, 50-237, 50-249, 50-373, 50-374, 50-410, 50-254, AND 50-265 Application (i.e., initial and supplements)
Safety Evaluation Date
August 30, 2023, ML23242A107 May 23, 2024 Principal Contributor to Safety Evaluation
1.0 INTRODUCTION
Constellation Energy Generation, LLC (CEG, the licensee) requested changes to the technical specifications (TSs) for Clinton Power Station (Clinton), Unit No. 1; Dresden Nuclear Power Station (Dresden), Units 2 and 3; LaSalle County Station (LaSalle), Units 1 and 2; Nine Mile Point Nuclear Station, Unit 2 (NMP-2); and Quad Cities Nuclear Power Station (Quad Cities),
Units 1 and 2 (collectively, the facilities), by license amendment request (LAR), dated August 30, 2023. The proposed changes would modify the TSs for each facility by deleting surveillance requirements (SRs) which verify the overlap between the source range monitor (SRM) and the intermediate range monitor (IRM), and between the IRM and the average power range monitor (APRM).
The proposed changes are based on Technical Specifications Task Force (TSTF) traveler TSTF-264, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs, dated April 28, 1998 (Agencywide Documents Access and Management System Accession No. ML040620165), and the associated U.S. Nuclear Regulatory Commission (NRC, the Commission) staff safety evaluation (SE) of TSTF-264 dated July 26, 1999 (ML19067A141).
1.1 Proposed TS Changes to Adopt TSTF-264 For Clinton, Dresden, LaSalle, and Quad Cities, the licensee proposes to delete SRs 3.3.1.1.6 and 3.3.1.1.7 from TS 3.3.1.1, Reactor Protection System (RPS) Instrumentation. For NMP-2, the licensee proposes to delete similar SRs that have been renumbered as 3.3.1.1.5 and 3.3.1.1.6.
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 NMP-2 current numbering for the relevant SRs differs from the standard technical specifications (STS) on which TSTF-264 was based. NMP-2 uses SRs 3.3.1.1.5 and 3.3.1.1.6 instead of SRs 3.3.1.1.6 and 3.3.1.1.7. Additionally, TSTF-264 deletes the SRs and all subsequent surveillances are renumbered, with corresponding cross-references to the renumbered surveillances being revised. The licensee is choosing to retain the SR numbers and show them as Deleted instead of renumbering the remaining SRs. These differences are editorial and do not affect the applicability of TSTF-264 to the proposed LAR with respect to these facilities.
1.2.2 Other Variations The plant-specific Bases wording for TSTF-264 discusses an acceptable one decade overlap between IRMs and APRMs. All facilities, except Clinton, currently have a 1/2 decade overlap requirement. This difference does not affect the applicability of TSTF-264 to the proposed LAR, but are evaluated in sections 3.2 of this SE.
2.0 REGULATORY EVALUATION
Section 50.36(c)(3) of Title 10 of the Code of Federal Regulations (10 CFR) requires that TSs include items in the category of SRs, which are requirements relating 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 limiting conditions for operation (LCOs) will be met.
The NRC staffs guidance for the review of TSs is provided in chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP),
March 2010 (ML100351425). As described therein, as part of the regulatory standardization effort, the staff has prepared STSs for each of the LWR nuclear designs. Accordingly, the staffs review includes consideration of whether the proposed changes are consistent with the STSs1, as modified by NRC-approved travelers.
3.0 TECHNICAL EVALUATION
3.1 Proposed TS Changes to Adopt TSTF-264 The NRC staff compared the licensees proposed TS changes in section 1.1 of this SE against the changes approved in TSTF-264. In accordance with SRP, chapter 16.0, the staff determined that the STS changes approved in TSTF-264 are applicable because each facility is a BWR
[boiling-water reactor] -design plant, and the staff approved the TSTF-264 changes for BWR designs. The staff finds that the licensees proposed changes, as stated in section 1.1 of this SE are consistent with those found acceptable in TSTF-264.
3.1.1. Current TS Requirements for Nuclear Instrumentation Neutron Flux Indication Overlap Verification TS 3.3.1.1, Reactor Protection System (RPS) Instrumentation, SRs 3.3.1.1.6 (3.3.1.1.5 for NMP-2) and 3.3.1.1.7 (3.3.1.1.6 for NMP-2), require verification of overlap for the SRM and IRM indications, and for the IRM and APRM indications, respectively. Table 1 below provides what the Bases for these SRs states, in part, to explain what constitutes acceptable overlap in each case.
Table 1 Facility Acceptable Overlap Clinton Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block. Overlap between the SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are above the downscale value of 5 and increasing as neutron flux increases, prior to the SRMs indication reaching their upscale limit.
1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, General Electric Plants,
[Boiling-Water Reactor] BWR/4, NUREG-1433, Volume 1, Specifications, and Volume 2, Bases, 5.0, September 2021 (ML21272A357 and ML21272A358, respectively).
U.S. Nuclear Regulatory Commission, Standard Technical Specifications, General Electric Plants, BWR/6, NUREG-1434, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21271A582 and ML21271A596, respectively).
Facility Acceptable Overlap Dresden The overlap between IRMs and APRMs is of concern when reducing power into the IRM range. On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained. The IRM/APRM and SRM/IRM overlaps are acceptable if a 1/2 decade overlap exists.
LaSalle The overlap between IRMs and APRMs is of concern when reducing power into the IRM range. On power increases, the system design will prevent further increases (initiate a rod block) if adequate overlap is not maintained.
The IRM/APRM and SRM/IRM overlaps are acceptable if a 1/2 decade overlap exists.
NMP-2 The overlap between IRMs and APRMs is of concern when reducing power into the IRM range. On power increases, the system design will prevent further increases (initiate a rod block) if adequate overlap is not maintained.
Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block. Overlap between SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are above mid-scale on range 1 before SRMs have reached the upscale rod block. The IRM/APRM and SRM/IRM overlaps are also acceptable if a 1/2 decade overlap exists.
Quad Cities The overlap between IRMs and APRMs is of concern when reducing power into the IRM range. On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained. The IRM/APRM and SRM/IRM overlaps are acceptable if a 1/2 decade overlap exists.
Table 2 below provides what the Frequency of SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) (IRM-SRM overlap verification) is at each facility.
Table 2 - SR 3.3.1.1.6 (3.3.1.1.5 for NMP 2)
Facility Frequency Clinton Prior to withdrawing SRMs from the fully inserted position Dresden Prior to fully withdrawing SRMs LaSalle Prior to fully withdrawing SRMs NMP-2 Prior to fully withdrawing SRMs Quad Cities Prior to fully withdrawing SRMs The surveillance column NOTE in SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) (APRM-IRM overlap verification) states, Only required to be met during entry into MODE 2 from MODE 1. The Frequency of SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) is In accordance with the Surveillance Frequency Control Program.
SR 3.3.1.1.1, for all facilities, requires a CHANNEL CHECK of IRM and APRM channels In accordance with the Surveillance Frequency Control Program.
As specified in TS Table 3.3.1.1-1, in Mode 2, SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) applies to RPS Function 1.a, IRM Neutron Flux - High (IRM Neutron Flux - Upscale for NMP-2), and SR 3.3.1.1.7 (3.3.1.1.6 for NMP-2) applies to RPS Function 1.a, and Function 2.a, APRM Neutron Flux - High Setdown (APRM Neutron Flux - Upscale Setdown for NMP-2). In addition, SR 3.3.1.1.1 applies to both Function 1.a and Function 2.a.
3.1.2. Proposed TS Requirements for Nuclear Instrumentation Neutron Flux Indication Overlap Verification The proposed change revises TS 3.3.1.1, RPS Instrumentation, by deleting SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) and SR 3.3.1.1.7 (3.3.1.1.6 for NMP-2), which verify the SRM-IRM neutron flux indication overlap and the IRM-APRM neutron flux indication overlap, respectively.
TS 3.3.1.1 retains the surveillance number designators but replaces the surveillance statement and any associated surveillance NOTE with the phrase Deleted and leaves the frequency column blank in the SRs table rows for existing SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) and SR 3.3.1.1.7 (3.3.1.1.6 for NMP-2).
At each facility, a CHANNEL CHECK is currently required for Functions 1.a and 2.a with a Frequency of In accordance with the Surveillance Frequency Control Program. TS Section 1.1, for each facility, defines a CHANNEL CHECK as follows (the same as the STS definition):
A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
As explained in TSTF-264, this definition of a CHANNEL CHECK in the STS may be interpreted as requiring SRM-IRM and IRM-APRM neutron flux indication overlap verification for the IRM-and APRM-associated RPS Functions that are required to be operable in Mode 2 (i.e., Functions 1.a and 2.a). Therefore, consistent with TSTF-264, the present indication overlap verifications may be considered redundant to the channel check SR.
The licensee stated that it will relocate the existing discussions of the SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) and SR 3.3.1.1.7 (3.3.1.1.6 for NMP-2) overlap verification requirements from the existing Bases to the Bases for SR 3.3.1.1.1. Table 3 below provides the paragraph that the licensee plans to add to the SR 3.3.1.1.1 Bases at each facility:
Table 3 - SR 3.3.1.1.1 Bases Facility Additional Paragraph Clinton The agreement criteria includes an expectation of overlap when transitioning between neutron flux instrumentation. The overlap between SRMs and IRMs must be demonstrated prior to withdrawing SRMs from the fully inserted position since indication is being transitioned from the SRMs to the IRMs. This will ensure that reactor power will not be increased into a neutron flux region without adequate indication. The overlap between IRMs and APRMs is of concern when reducing power into the IRM range (entry into MODE 2 from MODE 1). On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained. Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block. Overlap between SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are above the downscale value of 5 and increasing as neutron flux increases prior to the SRMs indication reaching their upscale limit.
If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate channel(s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable.
Dresden The agreement criteria includes an expectation of 1/2 decade of overlap when transitioning between neutron flux instrumentation. The overlap between SRMs and IRMs must be demonstrated prior to fully withdrawing SRMs since indication is being transitioned from the SRMs to the IRMs. This will ensure that reactor power will not be increased into a neutron flux region without adequate indication. The overlap between IRMs and APRMs is of concern when reducing power into the IRM range (entry into MODE 2 from MODE 1). On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained.
Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block. Overlap between SRMs and IRMs similarly exists when, prior to fully withdrawing the SRMs, IRMs respond to control rod movement before SRMs have reached the upscale rod block.
If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate channel(s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable.
LaSalle The agreement criteria includes an expectation of 1/2 decade of overlap when transitioning between neutron flux instrumentation. The overlap between SRMs and IRMs must be demonstrated prior to withdrawing SRMs from the fully inserted position since indication is being transitioned from the SRMs to the IRMs. This will ensure that reactor power will not be increased into a neutron flux region without adequate indication. The overlap between IRMs and APRMs is of concern when reducing power into the IRM range (entry into MODE 2 from MODE 1). On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained. Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block. Overlap between SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are above mid-scale on range 1 before SRMs have reached the upscale rod block.
If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate channel(s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable.
NMP-2 The agreement criteria includes an expectation of 1/2 decade of overlap when transitioning between neutron flux instrumentation. The overlap between SRMs and IRMs must be demonstrated prior to withdrawing SRMs from the fully inserted position since indication is being transitioned from the SRMs to the IRMs. This will ensure that reactor power will not be increased into a neutron flux region without adequate indication. The overlap between IRMs and APRMs is of concern when reducing power into the IRM range (entry into MODE 2 from MODE 1). On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained. Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block. Overlap between SRMs and IRMs similarly exists when, prior to withdrawing the SRMs from the fully inserted position, IRMs are above mid-scale on range 1 before SRMs have reached the upscale rod block.
If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate channel(s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable.
Quad Cities The agreement criteria includes an expectation of 1/2 decade of overlap when transitioning between neutron flux instrumentation. The overlap between SRMs and IRMs must be demonstrated prior to fully withdrawing SRMs since indication is being transitioned from the SRMs to the IRMs. This will ensure that reactor power will not be increased into a neutron flux region without adequate indication. The overlap between IRMs and APRMs is of concern when reducing power into the IRM range (entry into MODE 2 from MODE 1). On power increases, the system design will prevent further increases (by initiating a rod block) if adequate overlap is not maintained.
Overlap between IRMs and APRMs exists when sufficient IRMs and APRMs concurrently have onscale readings such that the transition between MODE 1 and MODE 2 can be made without either APRM downscale rod block, or IRM upscale rod block. Overlap between SRMs and IRMs similarly exists when, prior to fully withdrawing the SRMs, IRMs respond to control rod movement before SRMs have reached the upscale rod block.
If overlap for a group of channels is not demonstrated (e.g., IRM/APRM overlap), the reason for the failure of the Surveillance should be determined and the appropriate channel(s) declared inoperable. Only those appropriate channels that are required in the current MODE or condition should be declared inoperable.
In adopting TSTF-264, each facilitys TS 3.3.1.1 retains the surveillance number designators but replaces the surveillance statement and any associated surveillance note with the phrase Deleted and leaves the frequency column blank in the SRs table rows for existing SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) and SR 3.3.1.1.7 (3.3.1.1.6 for NMP-2). This is in lieu of removing these rows and renumbering the existing subsequent SRs, as done in the travelers markup of NUREG-1433, Revision 1, and NUREG-1434, Revision 1. In addition, the references to these SRs in TS Table 3.3.1.1-1 are removed. References to SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2) and SR 3.3.1.1.7 (3.3.1.1.6 for NMP-2) in the Bases for TS 3.3.1.2, Source Range Monitor (SRM)
Instrumentation, will be replaced by references to SR 3.3.1.1.1. No changes were needed to TS 3.3.1.2 requirements on SRM channel operability, actions, or surveillances in Mode 2 with IRMs on Range 2 or below.
Based on the above, the NRC staff has determined that the proposed changes are in accordance with NRC-approved TSTF-264, Revision 0, with no technical deviations; are consistent with STS, Revision 5.0; and that the overlap check will still be performed during surveillance testing.
Additionally, the NRC staff concludes that the requirements of 10 CFR 50.36(c)(3) continue to be met because the revised SR provides the appropriate surveillance to ensure the necessary quality of components is maintained and that the LCO will be met. Based on the above, the NRC staff concludes the proposed changes to SR 3.3.1.1.6 (3.3.1.1.5 for NMP-2), SR 3.3.1.1.7 (3.3.1.1.6 for NMP-2), and Table 3.3.1.1 1 of TS 3.3.1.1 to be acceptable.
3.2 Additional Proposed Bases Changes As previously mentioned, the plant-specific Bases wording for TSTF-264 discusses an acceptable one decade overlap between IRMs and APRMs. All facilities, except Clinton, currently have a 1/2 decade overlap requirement. The licensee stated that it would maintain the existing neutron flux monitor channel indication overlap criteria by relocating the discussion of the criteria to the Bases for TS SR 3.3.1.1.1 for RPS Functions 1.a and 2.a. The overlap check will be performed when SR 3.3.1.1.1 is performed for RPS Functions 1.a and 2.a. Although the TS Bases are a licensee-controlled document, changes to the TS Bases are controlled by the 10 CFR 50.59 process. The NRC staff finds that the licensee continues to uphold the previously approved definition of overlap and will maintain compliance with the requirement to verify SRM-IRM and IRM-APRM indication overlap at the necessary ranges of reactor power by performing the channel check specified for TS 3.3.1.1 Functions 1.a and 2.a at the Frequencies stated in the surveillance frequency control program.
3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for 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 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.
0 NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 253 TO FACILITY OPERATING LICENSE NO. NPF-62 AMENDMENT NO. 284 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19 AMENDMENT NO. 277 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25 AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-11 AMENDMENT NO. 248 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-18 AMENDMENT NO. 196 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 AMENDMENT NO. 300 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 296 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 CONSTELLATION ENERGY GENERATION, LLC CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 LASALLE COUNTY STATION, UNITS 1 AND 2 NINE MILE POINT NUCLEAR STATION, UNIT 2 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-461, 50-237, 50-249, 50-373, 50-374, 50-410, 50-254, AND 50-265 Application (i.e., initial and supplements)
Safety Evaluation Date
August 30, 2023, ML23242A107 May 23, 2024
1.0 INTRODUCTION
Constellation Energy Generation, LLC, requested changes to the technical specifications (TSs) for Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; LaSalle County Station, Units 1 and 2; Nine Mile Point Nuclear Station, Unit 2; and Quad Cities Nuclear Power Station, Units 1 and 2 (collectively, the facilities), by license amendment request (application), dated August 30, 2023. The amendments would revise the TSs for each facility based on Task Force (TSTF) Traveler TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs [Surveillance Requirements] (Agencywide Documents Access and Management System Accession No. ML040620165), and the associated U.S. Nuclear Regulatory Commission (NRC, the Commission) staff safety evaluation of TSTF-264 (ML19067A141).
2.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Illinois and New York State officials were notified of the proposed issuance of the amendments on March 8, 2024. The State officials had no comments.
3.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility component 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 Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, which was published in the Federal Register on October 31, 2023 (88 FR 74526), and there has been no public comment on such finding.
Accordingly, the amendment meets 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 amendment.
D. Rhoades
SUBJECT:
CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNIT 2; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-264, REVISION 0 (EPID L-2023-LLA-0121)
DATED MAY 23, 2024 DISTRIBUTION:
PUBLIC RidsNrrDorlLpl1 Resource RidsNrrDorlLpl3 Resource RidsRgn1MailCenter Resource RidsRgn3MailCenter Resource RidsNrrLASRohrer Resource RidsNrrLAABaxter Resource RidsNrrLAKEntz Resource RidsNrrLAKZeleznock Resource RidsAcrs_MailCTR Resource RidsNrrPMComstellation Resource RidsNrrPMClinton Resource RidsNrrPMDresden Resource RidsNrrPMLaSalle Resource RidsNrrPMNineMilePoint Resource RidsNrrPMQuadCities Resource RidsNrrDssStsb Resource TSweat, NRR NCarte Accession No.: ML24079A076 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC NAME SWall SRohrer SMehta (RElliott for)
DATE 03/12/2024 03/20/2024 03/29/2024 OFFICE NRR/DEX/EICB/BC OGC - NLO NRR/DORL/LPL3/BC NAME FSacko IMurphy JWhited DATE 03/27/2024 04/12/2024 05/23/2024 OFFICE NRR/DORL/LPL3/PM NAME SWall DATE 05/23/2024 OFFICIAL RECORD COPY