Text

Issuance of Amendments Revising Instrument Testing and Calibration Definitions
	ML20034G546
Person / Time
Site:	Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle
Issue date:	03/12/2020
From:	Blake Purnell; Plant Licensing Branch III
To:	Bryan Hanson; Exelon Generation Co, Exelon Nuclear
	Purnell B
References
	EPID L 2019 LLA 0131
	Download: ML20034G546 (182)
	v • d • e

March 12, 2020 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2; CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; JAMES A. FITZPATRICK NUCLEAR POWER PLANT; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND R. E. GINNA NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENTS REVISING INSTRUMENT TESTING AND CALIBRATION DEFINITIONS (EPID L-2019-LLA-0131)

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the following enclosed amendments in response to the Exelon Generation Company, LLC application dated June 25, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19176A498):

1.

Amendment No. 206 to Renewed Facility Operating License No. NPF-72 and Amendment No. 206 to Renewed Facility Operating License No. NPF-77 for Braidwood Station, Units 1 and 2, respectively;

2.

Amendment No. 212 to Renewed Facility Operating License No. NPF-37 and Amendment No. 212 to Renewed Facility Operating License No. NPF-66 for Byron Station, Unit Nos. 1 and 2, respectively;

3.

Amendment No. 334 to Renewed Facility Operating License No. DPR-53 and Amendment No. 312 to Renewed Facility Operating License No. DPR-69 for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, respectively;

4.

Amendment No. 229 to Facility Operating License No. NPF-62 for Clinton Power Station, Unit No. 1;

5.

Amendment No. 266 to Renewed Facility Operating License No. DPR-19 and Amendment No. 259 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, respectively;

6.

Amendment No. 333 to Renewed Facility Operating License No. DPR-59 for James A.

FitzPatrick Nuclear Power Plant;

7.

Amendment No. 242 to Renewed Facility Operating License No. NPF-11 and Amendment No. 228 to Renewed Facility Operating License No. NPF-18 for LaSalle County Station, Units 1 and 2, respectively;

8.

Amendment No. 243 to Renewed Facility Operating License No. NPF-39 and Amendment No. 206 to Renewed Facility Operating License No. NPF-85 for Limerick Generating Station, Units 1 and 2, respectively;

9.

Amendment No. 241 to Renewed Facility Operating License No. DPR-63 and Amendment No. 179 to Renewed Facility Operating License No. NPF-69 for Nine Mile Point Nuclear Station, Units 1 and 2, respectively;

10.

Amendment No. 332 to Subsequent Renewed Facility Operating License No. DPR-44 and Amendment No. 335 to Subsequent Renewed Facility Operating License No. DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, respectively;

11.

Amendment No. 279 to Renewed Facility Operating License No. DPR-29 and Amendment No. 274 to Renewed Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively; and

12.

Amendment No. 138 to Renewed Facility Operating License No. DPR-18 for R. E. Ginna Nuclear Power Plant.

The amendments revise the instrument testing and calibration definitions in the technical specifications for each facility to incorporate the surveillance frequency control program. The amendments are primarily based on Technical Specifications Task Force (TSTF) traveler TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program (ADAMS Accession No. ML17130A819).

A copy of the NRC staffs Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

Blake Purnell, 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, STN 50-455, 50-317, 50-318, 50-461, 50-237, 50-249, 50-333, 50-373, 50-374, 50-352, 50-353, 50-220, 50-410, 50-277, 50-278, 50-254, 50-265, and 50-244

Enclosures:

1. Amendment No. 206 to NPF-72

2. Amendment No. 206 to NPF-77

3. Amendment No. 212 to NPF-37

4. Amendment No. 212 to NPF-66

5. Amendment No. 334 to DPR-53

6. Amendment No. 312 to DPR-69

7. Amendment No. 229 to NPF-62

8. Amendment No. 266 to DPR-19

9. Amendment No. 259 to DPR-25

10. Amendment No. 333 to DPR-59

11. Amendment No. 242 to NPF-11

12. Amendment No. 228 to NPF-18

13. Amendment No. 243 to NPF-39

14. Amendment No. 206 to NPF-85

15. Amendment No. 241 to DPR-63

16. Amendment No. 179 to NPF-69

17. Amendment No. 332 to DPR-44

18. Amendment No. 335 to DPR-56

19. Amendment No. 279 to DPR-29

20. Amendment No. 274 to DPR-30

21. Amendment No. 138 to DPR-18

22. Safety Evaluation cc: Listserv

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 206 Renewed License No. NPF-72

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 206 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

/RA/ Robert Kuntz for 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: March 12, 2020

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 206 Renewed License No. NPF-77

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 206 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 206 AND 206 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 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-72 License NPF-72 Page 3 Page 3 License NPF-77 License NPF-77 Page 3 Page 3 TSs TSs 1.1-1 1.1-1 1.1-2 1.1-2 1.1-8 1.1-8 Renewed License No. NPF-72 Amendment No. 206 (2)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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. 206 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. 206 (2)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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. 206 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.

1.0 USE AND APPLICATION 1.1 Definitions Definitions 1.1

NOTE-------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

ACTIONS ACTUATION LOGIC TEST AXIAL FLUX DIFFERENCE (AFD)

CHANNEL CALIBRATION BRAIDWOOD - UNITS 1 & 2 Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AFD shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions.

Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANN CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

1.1 - 1 Amendment 206

1.1 Definitions CHANNEL CHECK CHANNEL OPERATIONAL TEST (COT)

CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)

BRAIDWOOD - UNITS 1 & 2 Definitions 1.1 A CHANN 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.

A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions.

The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

The COT may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Unit operation within these limits is addressed in individual Specifications.

1.1 2

Amendment 206

1.1 Definitions TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)

BRAIDWOOD - UNITS 1 & 2 Definitions 1.1 A TADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of required alarm, interlock, display, and trip functions.

The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy.

The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

1.1 8

Amendment 206

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 212 Renewed License No. NPF-37

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 212 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

/RA/ Robert Kuntz for 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: March 12, 2020

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 212 Renewed License No. NPF-66

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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-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. 212, 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 212 AND 212 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 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-37 License NPF-37 Page 3 Page 3 License NPF-66 License NPF-66 Page 3 Page 3 TSs TSs 1.1-1 1.1-1 1.1-2 1.1-2 1.1-8 1.1-8 Renewed License No. NPF-37 Amendment No. 212 (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 power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 212 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. 212 (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. 212, 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.

1.0 USE AND APPLICATION 1.1 Definitions Definitions 1.1

NOTE-------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

ACTIONS ACTUATION LOGIC TEST AXIAL FLUX DIFFERENCE (AFD)

CHANNEL CALIBRATION BYRON - UNITS 1 & 2 Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.

AFD shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, interlock, display, and trip functions.

Calibration of instrument channels with Resistance Temperature Detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANN CALIBRATION may be performed by means of any series of sequential, overlapping calibrations or total channel steps so that the entire channel is calibrated, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

1.1 - 1 Amendment 212

1.1 Definitions CHANNEL CHECK CHANNEL OPERATIONAL TEST (COT)

CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)

BYRON - UNITS 1 & 2 Definitions 1.1 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.

A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions.

The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints so that the setpoints are within the required range and accuracy.

The COT may be performed by means of any series of sequential, overlappin~ or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Unit operation within these limits is addressed in individual Specifications.

1.1 - 2 Amendment 212

1.1 Definitions TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)

BYRON - UNITS 1 & 2 Definitions 1.1 A TADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of required alarm, interlock, display, and trip functions.

The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy.

The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

1.1 8

Amendment 212

CALVERT CLIFFS NUCLEAR POWER PLANT, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 334 Renewed License No. DPR-53

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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-53 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 334, are hereby incorporated into this license. Exelon Generation 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

/RA/ Robert Kuntz for 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: March 12, 2020

CALVERT CLIFFS NUCLEAR POWER PLANT, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 312 Renewed License No. DPR-69

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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-69 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 312, are hereby incorporated into this 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 334 AND 312 RENEWED FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 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-53 License DPR-53 Page 3 Page 3 License DPR-69 License DPR-69 Page 3 Page 3 TSs TSs 1.1-1 1.1-1 1.1-2 1.1-2 Amendment No. 334 (4)

Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and 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)

Exelon Generation pursuant to the Act and 10 CFR Parts 30 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 license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:

(1)

Maximum Power Level Exelon Generation is authorized to operate the facility at steady-state reactor core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 334, are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.

(a)

For Surveillance Requirements (SRs) that are new, in Amendment 227 to Facility Operating License No. DPR-53, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 227. For SRs that existed prior to Amendment 227, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 227.

(3)

Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 327 are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Additional Conditions.

(4)

Secondary Water Chemistry Monitoring Program Exelon Generation shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

Amendment No. 312 (4)

Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, in amounts as required, any byproduct, source, and 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)

Exelon Generation pursuant to the Act and 10 CFR Parts 30 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 license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:

(1)

Maximum Power Level Exelon Generation is authorized to operate the facility at steady-state reactor core power levels not in excess of 2737 megawatts-thermal in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 312, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

(a)

For Surveillance Requirements (SRs) that are new, in Amendment 201 to Facility Operating License No. DPR-69, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 201. For SRs that existed prior to Amendment 201, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 201.

(3)

Less Than Four Pump Operation The licensee shall not operate the reactor at power levels in excess of five (5) percent of rated thermal power with less than four (4) reactor coolant pumps in operation. This condition shall remain in effect until the licensee has submitted safety analyses for less than four pump operation, and approval for such operation has been granted by the Commission by amendment of this license.

(4)

Environmental Monitoring Program If harmful effects or evidence of irreversible damage are detected by the biological monitoring program, hydrological monitoring program, and the

1.0 USE AND APPLICATION 1.1 Definitions Definitions 1.1

NOTE-----------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

ACTIONS AXIAL SHAPE INDEX (ASI)

AZIMUTHAL POWER TILT (Tq)

CHANNEL CALIBRATION CHANNEL CHECK CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS - UNIT 2 Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

ASI shall be the power generated in the lower half of the core less the power generated in the upper half of the core, divided by the sum of the power generated in the lower and upper halves of the core.

ASI lower -

upper lower + upper AZIMUTHAL POWER TILT shall be the power asymmetry between azimuthally symmetric core locations.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

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 1.1-1 Amendment No. 334 Amendment No. 312

1.1 Definitions CHANNEL FUNCTIONAL TEST CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT I-131 CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS - UNIT 2 Definitions 1.1 indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

A CHANNEL FUNCTIONAL TEST shall be:

Analog Channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

Bistable Channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY of all devices in.the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133, I-134, and I-135 actually present.

The TEDE (Total Effective Dose Equivalent) inhalation dose conversion factors used for this calculation shall be those listed in Table 2.1 in the column headed "effective of Federal Guidance Report 11, ORNL, 1988, "Limiting Values of Radionuclide Intake and 1.1-2 Amendment No. 334 Amendment No. 312

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 229 License No. NPF-62

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 229, are hereby incorporated into this license.

Exelon Generation Company 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

/RA/ Robert Kuntz for 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 Facility Operating License Date of Issuance: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 229 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 1.0-1 1.0-1 1.0-2 1.0-2 1.0-3 1.0-3 1.0-4 1.0-4 1.0-5 1.0-5 1.0-6 1.0-6 1.0-7 1.0-7 1.0-8 1.0-8 1.0-9 1.0-9 1.0-10 1.0-10 1.0-11 1.0-11 1.0-12 1.0-12 1.0-13 1.0-13 1.0-14 1.0-14 1.0-15 1.0-15 1.0-16 1.0-16 1.0-17 1.0-17 1.0-18 1.0-18 1.0-19 1.0-19 1.0-20 1.0-20 1.0-21 1.0-21 1.0-22 1.0-22 1.0-23 1.0-23 1.0-24 1.0-24 1.0-25 1.0-25 1.0-26 1.0-26 1.0-27 1.0-27 1.0-28 1.0-28 1.0-29 Amendment No. 229 (4)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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 Commission's 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 Exelon Generation Company 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. 229, are hereby incorporated into this license.

Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

1.0 USE AND APPLICATION 1.1 Definitions Definitions 1.1

NOTE-------------------------------------

The defined terms of this section appear in talized type and are applicable these Technical fications and Bases.

Term ACTIONS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

CHANNEL CALIBRATION CLINTON Definit ACTIONS shall be that part of a Specification that prescribes Actions to be taken under des Conditions within fied Times.

The APLHGR sha 1 be icable to a fie planar hei and is equal to the sum of the LHGRs for all the fuel rods in the fied bundle at the specified divided by the number of fuel rods in the fuel bundle at the height.

A CHANNEL CALIBRATION shall be the ustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass all devices in the channel for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.

Calibration of instrument channels with resistance temperature detector (RTD) or e sensors may consist of an qualitative assessment of sensor behavior and normal calibration of the rema ustable devices in the channel.

The CHANNEL CALIBRATION may be performed by means of any series of sequential,

, or total channel steps, and each step must be within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

(continued) 1.0-1 Amendment No. 229

Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK CHANNEL FUNCTIONAL TEST CORE ALTERATION CLINTON A CHANNEL CHECK shal be the qualitative assessment, observation, of channel behavior during operation.

This determination shall include, where e, comparison of the channel indication and status to other indications or status derived from instrument channels the same parameter.

A CHANNEL FUNCTIONAL TEST shall be the ection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overl

, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.

The fol exceptions are not considered to be CORE ALTERATIONS:

a.

Movement of source range monitors, range monitors, intermediate range travers incore probes, or detectors undervessel and local power

monitors, movable acement);

b.

Control rod movement, there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not etion of movement of a component to a safe position.

(continued) 1.0-2 Amendment No. 229

Definitions 1.1 1.1 Definitions (continued)

CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT I-131 DRAIN TIME CLINTON The COLR is the unit specific document that provides cycle specific parameter limits for the current reload These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5.

Plant within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries that alone would produce the same inhalation CEDE dose as the quantity and i mixture of I-131, I 132, I-133, I-134, and I-135 actual present.

The inhalation CEDE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," ORNL, 1989.

The DRAIN TIME is the time it would take for the water in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a.

The water above the TAF is divided

b.

The limi drain rate is the larger of the drain rate through a single penetration flow with the t flow rate, or the sum of the drain rates through mult penetration flow paths susceptible to a comrnon mode failure (e.g., seismic event, loss of normal power, s human error), for all (continued) 1.0-3 Amendment No. 229

Definitions DRAIN TIME (continued)

EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME CLINTON Definitions 1.1 penetration flow paths below the TAF except:

1.

Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2.

Penetration flow paths capable of isolated by valves that will close without offsite power prior to the RPV water level equal to the TAF when actuated RPV water level isolation instrumentation; or

3.

Penetration flow paths with isolation devices that can be closed to the RPV water level to the TAF a dedicated operator trained in the task, who is in continuous communication with the control room, is stationed at the controls, and is capable of the penetration flow path isolation devices without offsite power.

c.

The penetration flow paths to be evaluated per b) are assumed to open instantaneous y and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory;

d.

No additional events occur; and

e.

Realistic cross-sectional areas and drain rates are used.

A DRAIN TIME may be used in lieu of a calculated value.

The ECCS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until the ECCS is capable of its safety function (i.e., the valves travel to their positions, pump discharge pressures reach their required values, etc.).

Times shall include diesel generator starting and sequence loading

, where icable.

The response time may be measured means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

1.0-4 Amendment No. 229

Definitions 1.1 1.1 Definitions (continued)

END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) SYSTEM RESPONSE TIME INSERVICE TESTING PROGRAM ISOLATION SYSTEM RESPONSE TIME LEAKAGE CLINTON The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval from initial movement of the associated turbine stop valve or turbine control valve to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker.

The response time may be measured means of any series of sequential,

, or total steps so that the entire response time is measured.

The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 1 0 C FR 5 0. 5 5 a ( f ).

The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation at the channel sensor until the to their required may be measured means sequential, overlapping, the entire response time LEAKAGE shall be:

a.

Identified LEAKAGE isolation valves travel The response time of any series of or total steps so that is measured.

1. LEAKAGE into the drywell such as that from pump seals or valve

, that is captured and conducted to a sump or collect tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both and known either not the operation of or not to be

b.

Unidentified LEAKAGE All LEAKAGE into the identified LEAKAGE;

c.

Total LEAKAGE l that is not Sum of the identified and unidentified LEAKAGE;

d.

Pressure LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

(continued) 1.0-5 Amendment No. 229

Definitions 1.1

1. 1 Definitions (continued)

LINEAR HEAT GENERATION RATE (LHGR)

LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR)

MODE OPERABLE~OPERABILITY RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS) RESPONSE TIME CLINTON The LHGR shall be the heat generation rate per unit length of fuel rod.

It is the of the heat flux over the heat transfer area associated with the unit length.

A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a circuit, from as close to the sensor as practicable up to, but not the actuated device, to veri OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be means of any series of total system steps so that the entire tested.

The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each class of fuel.

The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to ence boil transition, divided the actual as operat power.

A MODE shall to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1 1 with fuel in the reactor vessel.

A system, subsystem, division, component, or device shal be OPERABLE or have OPERABILITY when it is capable of performing its fied safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxil that are for the system, subsystem, component, or device to perform its sa function(s) are also capable their related support function(s).

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 34 3 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram lot valve solenoids.

The response time may be measured by means of any series of

, or total steps so that the entire response time is measured.

(continued) 1.0-6 Amendment No. 229

Definitions 1.1

1. 1 Definitions (continued)

SHUTDOWN MARGIN (SOM)

STAGGERED TEST BASIS THERMAL POWER TURBINE BYPASS SYBTEM RESPONSE TIME CLINTON SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating as that:

a.

The reactor is xenon free;

b.

The moderator temperature is~ 68°F, corresponding to the most reactive state; and

c.

All control rods are fully inserted except control rod of worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the worth of these control rods must be accounted for in the determination of SOM.

A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other ed components are tested where n is the total number of systems, subsystems, channels, or other desi components in the associated function.

THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

The TURBINE BYPASS SYSTEM RESPONSE TIME consists of two components:

a.

The time from initial movement of the main turbine stop valve or control valve unti 80%

of the turbine bypass ty is established; and

b.

The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine s valve.

The response time may be measured by means of any series of sequential,

, or total steps so that the entire response time is measured.

1.0-7 Amendment No. 229

MODE TITLE 1

Power Operation 2

Startup 3

Shutdown(a)

Hot 4

Cold Shutdown(a) 5 Refuel (b)

Table 1.1-1 (page 1 of 1)

MODES REACTOR MODE SWITCH POSITION Run Refue1(a) or Startup/Hot Standby Shutdown Shutdown Shutdown or Refuel Definitions 1.1 AVERAGE REACTOR COOLANT TEMPERATURE (OF)

NA NA

> 200

~ 200 NA (a)

All reactor vessel head closure bolts fully tensioned.

(b)

One or more reactor vessel head closure bolts less than fully tensioned.

CLINTON 1.0-8 Amendment No. 229

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE BACKGROUND EXAMPLES CLINTON The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions,

Times, Surveillances, and logical connectors that appear in TS are AND and arrangement of these connectors constitutes logical conventions with specific meanings.

Several levels of Actions.

These levels nesting) of the l ass to each may be used to state are identified by the placement (or connectors and by the number Action.

The first leve of logic is identified the first di of the number as to a Required Action and the acement of the logical connector in the first level of nest (i.e., left justified with the number of the Action).

The successive levels of additional s of the Required Action number successive indentions of the connectors.

When logical connectors are used to state a Condition, ion Time, Surveillance, or Frequency, only the first level of is used, and the connector is left justified with the statement of the Condition, ion Time, Surveillance, or Frequency.

The following examples illustrate the use of 1 connectors.

continued 1.0-9 Amendment No. 229

1.2 EXAMPLES (continued)

CLINTON Connectors EXAMPLE 1.2-1 ACTIONS CONDITION A.

LCO not met.

REQUIRED ACTION A. l Verify...

AND A.2 Restore...

Logical Connectors 1.2 COMPLETION TIME In this

, the logical connector AND is used to indicate that, when in Condition A, Actions A.1 and A.2 must be 1.0-10 Amendment No. 229

1. 2 EXAMPLES (continued)

CLINTON Connectors EXAMPLE 1. 2-2 ACTIONS CONDITION A.

LCO not met.

REQUIRED ACTION A. l Trip OR A.2.1 Verify AND A.2.2.1 Reduce OR A.2.2.2 Perform A.3 Align.

Logical Connectors 1.2 COMPLETION TIME This represents a more icated use of cal connectors.

Required Actions A.l, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the l cal connector OR and the left justified placement.

Any one of these Actions may be chosen.

If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated the logical connector AND.

Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2.

The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative

, only one of which must be 1.0-11 Amendment No. 229

Completion Times

1. 3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE BACKGROUND DESCRIPTION CLINTON The purpose of this section is to establish the ion Time convention and to provide for its use.

Operation (LCOs) fy minimum s for safe of the unit.

The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the of the LCO can fai to be met.

Specified with each stated Condition are Action(s) and Completion Time(s).

The ion Time is the amount of time allowed for a Required Action.

It is referenced to the discovery of a situation (e.g.,

equipment or variable not within limits) that ACTIONS Condition unless otherwise the unit is in a MODE or in the Applicability of the LCO.

Unless otherwise fied, the Completion Time when a senior licensed operator on the operat shift crew with responsibility for plant operations makes the determination that an LCO is not met and an ACTIONS Condition is entered.

The "otherwise specified" exceptions are varied, such as a Action Note or Surveillance Requirement Note that provides an alternative time to perform fie tasks, such as test

, without start the etion Time.

While utilizing the Note, should a Condition be icable for any reason not addressed by the Note, the Completion Time begins.

Should the time allowance in the Note be exceeded, the Completion Time begins at that point.

The exceptions may also be into the Time.

For example, LCO 3.8.1, "AC Sources Action B.2, requires declaring supported by an i diesel generator, when the redundant required feature(s) are The Completion Time states, "4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required features ( s). "

In this case the Completion Time does not begin until the conditions in the Completion Time are satisfied.

Required Actions must be eted to the ion of the specified Completion Time.

An ACTIONS Condition remains in effect and the red Actions apply until the Condition no longer exists or the unit is not within the LCO Applicabil If situations are discovered that entry into more than one Condition at a time within a single LCO e

Conditions), the Required Actions for each Condition must be performed within the associated Completion Time.

When in multiple Conditions, separate Completion Times are tracked 1.0-12 Amendment No. 229

Completion Times

1. 3 1.3 Completion Times DESCRIPTION (continued)

CLINTON for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.

Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless speci lly stated.

The red Actions of the Condition continue to apply to each additional failure, with etion Times based on initial entry into the Condition, unless otherwise specified.

However, when a division, subsystem, component, or variable expres Condition is discovered to be or not within limits, the Completion Time(s) may be extended.

To apply this Completion Time extension, two criteria must first be met.

The subsequent lity:

a.

Must exist concurrent with the first and

b.

or not within limits after the resolved.

The total Completion Time allowed for completing a Action to address the subsequent lity shall be limited to the more restrictive of either:

a.

The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b.

ion Time as measured from discovery lity.

The above Completion Time extension does not apply to those Specifications that have exceptions that allow separate re-entry into the Condition (for each division, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.

These exceptions are stated in individual Specifications.

The above Completion Time extension does not to a Completion Time with a modified "time zero."

This modified "time zero" may be expressed as a repetitive time (i.e.,

"once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a ion of the Required Action versus the time of Condition entry) or as a time modified by the "from discovery.

(continued) 1.0-13 Amendment No. 229

Completion Times

1. 3 1.3 Completion Times (continued)

EXAMPLES CLINTON The foll examples illustrate the use of ion Times with different types of Conditions and changing Conditions.

EXAMPLE 1. 3-1 ACTIONS B.

CONDITION Action and associated Time not met.

REQUIRED ACTION B. 1 Be in MODE 3.

AND B. 2 Be in MODE 4.

COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours Condition B has two Required Actions.

Each has its own separate Time.

Each Time is referenced to the time that Condition Bis entered.

The Actions of Condition Bare to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is al for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for MODE 4 from the time that Condition B was entered.

If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for MODE 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition Bis entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

1.0-14 Amendment No. 229

Completion Times

1. 3

1. 3 ion Times EXAMPLES (continued)

CLINTON EXAMPLE

.3-2 ACTIONS CONDITION A.

One pump B. Required Action and associated Time not met.

REQUIRED ACTION A.1 Restore pump to OPERABLE status.

B.1 Be in MODE 3.

AND 8.2 Be in MODE 4.

COMPLETION TIME 7 days 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours When a pump is declared

, Condition A is entered.

If the pump is not restored to OPERABLE status within 7 days, Condition Bis also entered and the ion Time clocks for Required Actions B.1 and B.2 start.

If the e pump is restored to OPERABLE status after Condition Bis entered, Conditions A and Bare exited, and therefore, the red Actions of Condition B may be terminated.

When a second pump is declared while the first pump is still

, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump.

The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initial entered.

While in LCO 3.0.3, if one of the i e pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condit on A.

(continued) 1.0-15 Amendment No. 229

1.3 EXAMPLES CLINTON Times EXAMPLE 1.

(continued)

Completion Times 1.3 While in LCO 3.0.3, if one of the pumps is restored to OPERABLE status and the ion Time for Condition A has

, LCO 3.0.3 may be exited and operation continued in accordance with Condition B.

The Completion Time for Condition Bis tracked from the time the Condition A ion Time expired.

On one of the pumps to OPERABLE status, the Condition A ion Time is not reset, but continues from the time the first pump was declared This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump.

A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for

> 7 days.

continued 1.0-16 Amendment No. 229

1.3 Completion Times EXAMPLES (continued)

CLINTON ACTIONS CONDITION A. One Function X subsystem inoperable.

B. One Function Y subsystem C. One Function X subsystem AND One Function Y subsystem REQUIRED ACTION A.l Restore Function X to OPERABLE status.

B.1 Restore Function Y subsystem to OPERABLE status.

C.l Restore Function X subsystem to OPERABLE status.

OR C.2 Restore Function Y subsystem to OPERABLE status.

1. 0-1 7 Completion Times

1. 3 COMPLETION TIME 7 days 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Amendment No. 229

1.3 EXAMPLES CLINTON ion Times EXAMPLE 1.3-3 (continued)

Completion Times 1.3 When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition Bare concurrently applicable.

The Times for Condition A and Condition Bare tracked separately for each starting from the time each subsystem was declared inoperable and the Condition was entered.

A separate ion Time is established for Condition C and tracked from the time the second was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If red Action C.2 is within the specified Completion Time, Conditions Band Care exited.

If the Completion Time for red Action A.l has not operation may continue in accordance with Condition A.

The remaining Completion Time in Condition A is measured from the time the affected was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue without ever systems to meet the LCO.

However, doing so would be inconsistent with the basis of the Completion Times.

Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in as cont occurrence of fail to meet the LCO.

These administrative controls shall ensure that the Times for those Conditions are not 1.0-18 Amendment No. 229

1. 3 EXAMPLES (continued)

CLINTON Completion Times

1. 3 Times 4

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A. l Restore valve(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves to OPERABLE inoperable.

status.

B.

Required B. l Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Time not B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

A single Completion Time is used for any number of valves at the same time.

The Time associated with Condit on A is based on the initial entry into Condition A and is not tracked on a per valve basis.

valves inoperable, while Condition A is sti l in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared The ion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve.

The Condition A Completion Time may be extended for up to this does not result any subsequent valve e for> 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the etion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more valves are still inoperable, Condition Bis entered.

(continued) 1.0-19 Amendment No. 229

1. 3 EXAMPLES (continued)

CLINTON Times EXAMPLE 1.3-5 ACTIONS Completion Times

1. 3

NOTE----------------------------

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION A.

One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.l Be in MODE 3.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Action and associated AND ion Time not B.2 Be in MODE 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months met.

The Note above the ACTIONS table is a method of modi how the ion Time is tracked.

If this method of e

TIME modi ng how the etion Time is tracked was icable only to a fie Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for

each valve, and on Times tracked on a per valve basis.

When a valve is declared Condition A is entered and its Completion Time starts.

If subsequent valves are declared

, Condition A is entered for each valve and separate Times start and are tracked for each valve.

(continued) 1.0-20 Amendment No. 229

1. 3 EXAMPLES CLINTON Times Completion Times

1. 3 (continued)

If the Completion Condition A If the Time associated with a valve in

, Condition Bis entered for that valve.

Times associated with subsequent valves in re, Condition Bis entered separately for each valve and separate Completion Times start and are tracked for each valve.

If a valve that caused entry into Condition Bis restored to OPERABLE status, Condition Bis exited for that valve.

Since the Note in this allows mult Condition entry and tra of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION A.

One channel inoperable.

B. Required Action and associated Time not met.

REQUIRED ACTION A.1 Perform SR 3.x.x.x.

OR A.2 Reduce THERMAL POWER to

50 RTF.

B.1 Be in MODE 3.

1.0-21 COMPLETION TIME Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Amendment No. 229

1. 3 EXAMPLES CLINTON on Times EXAMPLE 1.3-6 (continued)

Completion Times

1. 3 Entry into Condition A offers a choice between Action A.l or A.2.

red Action A.l has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial If Action A.l is followed and the is not met within the Time (plus the extension allowed SR 3.0.2), Condition Bis entered.

If red Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition Bis entered.

If after entry into Condition B, Action A.l or A.2 is met, Condition Bis exited and operation may then continue in Condition A.

1.0-22 Amendment No. 229

1. 3 EXAMPLES (continued)

CLINTON Times EXAMPLE l.

ACTIONS CONDITION A.

One A.1 subsystem inoperable.

AND A.2 B.

B.1 Action and associated AND Time not B.

met.

REQUIRED ACTION Verify affected isolated.

Restore to OPERABLE status.

Be in MODE 3.

Be in MODE 4.

Completion Times

1. 3 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 2 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two ion Times.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Action A.1.

If after Condition A is entered, Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the (plus the extension allowed by SR 3.0.2), Condition Bis entered.

The Completion Time clock for Condition A does not stop after 1.0-23 Amendment No. 229

Completion Times

l. 3 1.3 Completion Times EXAMPLES IMMEDIATE COMPLETION TIME CLINTON (continued)

Condition Bis entered, but continues from the time Condition A was initially entered.

If Required Action A.1 is met after Condition Bis entered, Condition Bis exited and may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not "is used as a Completion Time, the should be pursued without delay and in a controlled manner.

1.0-24 Amendment No. 229

Frequency

1. 4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE DESCRIPTION CLINTON The purpose of this section is to define the proper use and application of Frequency requirements.

Each Surveillance (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation (LCO).

An understanding of the correct ion of the specified Frequency is necessary for with the SR.

The" fied Frequency" is referred to this section and each of the fications of Section 3.0, Surveillance Requirement (SR) Applicabi The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that rements.

Sometimes situations dictate when the s

of a Surveillance are to be met.

are "otherwise stated" conditions allowed by.SR 3.0.1.

They may be stated as clari Notes in the Surveillance, as part of the Surveillance, or both.

Example 1.4-4 discusses these special situations.

Situations where a Surveillance could be (i.e., its Frequency could

), but where it is not possible or not desired that it be performed unti sometime after the associated LCO is within its icabil

, represent potential SR 3.0.4 conflicts.

To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only" red" when it can be and should be performed.

With an SR satisfied, SR 3.0.4 no restriction.

The use of "met" or "performed" in these instances conveys specified meanings.

A Survei lance is "met" only when the acceptance criteria are satisfied.

Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met."

"Performance" refers only to the to specifically determine the to meet the acceptance (continued) 1.0-25 Amendment No. 229

1.4 Frequency DESCRIPTION (continued)

EXAMPLES CLINTON criteria.

SR 3.0.4 restrictions would not following conditions are satisfied:

Frequency

1. 4 if both the

a.

The Surveillance is not to be performed; and

b.

The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

examples illustrate the various ways that are fied.

In these

, the of the LCO (LCO not shown) is MODES 1, 2, examples do not reflect the potential application of LCO 3.0.4.b.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE Perform CHANNEL CHECK.

FREQUENCY 1

hours Example 1.4 contains the type of SR mos often encountered in the Technical fications (TS).

The Frequency fies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) which the associated Surveillance must be at least one time.

Performance of the Surveillance initiates the subsequent interval.

Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed SR 3.0.2 for operational flexibility.

The measurement of this interval continues at all times, even when the SR is not to be met per SR 3.0.1 (such as when the is

, a variable is outside fied limits, or the unit is outside the icabil of the LCO).

f the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other fied condition in the icabi of the LCO, and the performance of the Surveillance is not otherwise modified (refer to 1.4 3 and 1.4-4), then SR 3.0.3 becomes applicable.

(continued) 1.0-26 Amendment No. 229

1.4 Frequency EXAMPLES CLINTON EXAMPLE 1 4-1 (continued)

Frequency

1. 4 If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the icabi of the LCO for which performance of the SR is

, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 to entry into the MODE or other specified condition.

Failure to do so would result in a violation of SR 3.0.4.

EXAMPLE 1.4-2 SURVEILLANCE SURVEILLANCE Verify flow is within limits.

FREQUENCY Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

~ 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1.

The connector "AND" indicates that both Frequency requirements must be met.

Each time reactor power is increased from a power level< 25% RTP to

~ 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates as will satisfy the specified Frequency Frequencies are connected by "AND").

This type of Frequency does not i

for the extension allowed by SR 3~0.2.

(continued)

1. 0-27 Amendment No. 229

1.4 Frequency EXAMPLES CLINTON EXAMPLE 1 4-2 (continued)

Frequency

1. 4

'.'Thereafter" indicates future performances must be established per SR 3.0.2, but after a specified condition is first met (i.e., the "once" performance in this example).

If reactor power decreases to< 25% RTP, the measurement of both intervals stops.

New intervals start upon reactor power reaching 25% RTP.

EXAMPLE 1.4-3 SURVEILLANCE SURVEILLANCE FREQUENCY

NOTE------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 2 25% RTP.

Perform channel ustment.

7 The interval continues whether or not the unit operation is

< 25% RTP between performances.

As the Note modifies the required Surveillance, it is construed to part fied Frequency."

Should the 7 day interval be exceeded while operation is< 25 RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches 2 25% RTP to perform the Surveillance.

The Surveillance is still considered to be within the" fied Frequency."

Therefore, if the Surveillance were not performed within the 7 day interval (

the extension allowed by SR 3.0.2), but operation was< 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO.

Also, no violation of SR 3.0.4 occurs when MODES, even with the 7 day Frequency not met, operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (plus the extension allowed by SR 3.0.2) with power 2 25% RTF.

(continued) 1.0-28 Amendment No. 229

1.4 Frequency EXAMPLES CLINTON EXAMPLE 1. 4 -

(continued)

Frequency

1. 4 Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance.

If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval (

the extension allowed by SR 3.0.2), there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

EXAMPLE 1.4-4 SURVEILLANCE IREMENTS SURVEILLANCE

NOTE------------------

Only to be met in MODE 1.

Verify leakage rates are within limits.

FREQUENCY 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 fies that the of this Surveillance do not have to be met until the unit is in MODE 1.

The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1.

However, the Note constitutes an "otherwise stated" exception to the icability of this Surveillance.

Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (plus the extension allowed by SR 3.0.2) interval, but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO.

Therefore, no violation of SR 3.0.4 occurs when MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, the MODE change was not made into MODE 1.

Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4 would require satis the SR.

1. 0-2 9 Amendment No. 229

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 266 Renewed License No. DPR-19

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 266, 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

/RA/ Robert Kuntz for 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: March 12, 2020

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 259 Renewed License No. DPR-25

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 259, 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 266 AND 259 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 1.1-1 1.1-1 1.1-2 1.1-2 1.1-3 1.1-3 1.1-4 1.1-4 1.1-5 1.1-5 1.1-6 1.1-6 1.1-7 1.1-7 1.1-8 Renewed License No. DPR-19 Amendment No. 266 (2)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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. 266, 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. 259

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. 259, 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.

1.0 USE AND APPLICATION 1.1 Definitions

NOTE ----------

Definitions

1. 1 The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

ACTIONS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

CHANNEL CALIBRATION Dresden 2 and 3 Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

The APLHGR shall be applicable to a specific planar height and is equal to the sum of the LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass all devices in the channel required for channe}

OPERABILITY and the CHANNEL FUNCTIONAL TEST.

Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANN L CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

(continued)

1. 1-1 Amendment No. 266/259

Definitions

1. 1 1.1 Definitions (continued)

CHANNEL CHECK CHANNEL FUNCTIONAL TEST Dresden 2 and 3 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.

A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

(continued)

1. 1-2 Amendment No. 266/259

Definitions 1.1 1.1 Definitions (continued)

CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT I-131 Dresden 2 and 3 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a.

Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);

and

b.

Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I 131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of I-131, I 132, I 133, I-134, and I 135 actually present.

The dose conversion factors used for this calculation shall be the inhalation committed dose conversion factors in Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989.

(continued)

1. 1-3 Amendment No. 266/259

Definitions 1.1 1.1 Definitions (continued)

DRAIN TIME Dresden 2 and 3 The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a.

The water inventory above the TAF is divided by the limiting drain rate;

b.

The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single human error),

for all penetration flow paths below the TAF except:

1.

Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2.

Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or

3.

Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who is in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.

(continued) 1.1 4 Amendment No. 266/259

1.1 Definitions DRAIN TIME (continued)

INSERVICE TESTING PROGRAM LEAKAGE Dresden 2 and 3 Definitions 1.1

c.

The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory;

d.

No additional draining events occur; and

e.

Realistic cross-sectional areas and drain rates are used.

A bounding DRAIN TIME may be used in lieu of a calculated value.

The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 10 CFR 50.55a(f).

LEAKAGE shall be:

a.

Identified LEAKAGE

1. LEAKAGE into the drywel 1, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywel l atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b.

Unidentified LEAKAGE A 11 LEAKAGE into the drywel 1 that is not identified LEAKAGE; (continued)

1. 1-5 Amendment No. 266/259

1.1 Definitions LEAKAGE (continued)

LINEAR HEAT GENERATION RATE ( LHGR)

LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR)

MODE OPERABLE-OPERABILITY Dresden 2 and 3

c.

Total LEAKAGE Definitions 1.1 Sum of the identified and unidentified LEAKAGE; and

d.

Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

The LHGR shall be the heat generation rate per unit length of fuel rod.

It is the integral of the heat flux over the heat transfer area associated with the unit length.

A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each class of fuel.

The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, (continued) 1.1-6 Amendment No. 266/259

1.1 Definitions OPERABLE-OPERABILITY (continued)

RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SOM)

THERMAL POWER TURBINE BYPASS SYSTEM RESPONSE TIME Dresden 2 and 3 Definitions 1.1 lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2957 MWt.

The RPS RESPONSE TIME shall be that time interval from the opening of the sensor contact until the opening of the trip actuator.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:

a. The reactor is xenon free;

b.

The moderator temperature is~ 68°F, corresponding to the most reactive state; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM.

THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time interval from when the turbine bypass control unit generates a turbine bypass valve flow signal until the turbine bypass valves travel to their required positions.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

1.1 7 Amendment No. 266/259

MODE TITLE 1

Power Operation 2

Startup 3

Hot Shutdown<al 4

Cold Shutdown(aJ 5

Refuel i ng(b)

Table 1.1-1 (page 1 of 1)

MODES REACTOR MODE SWITCH POSITION Run Refuel <ai or Startup/Hot Standby Shutdown Shutdown Shutdown or Refuel Definitions 1.1 AVERAGE REACTOR COOLANT TEMPERATURE

( a F)

NA NA

> 212

~ 212 NA (a)

All reactor vessel head closure bolts fully tensioned.

(bl One or more reactor vessel head closure bolts less than fully tensioned.

Dresden 2 and 3 1.1-8 Amendment No. 266/259

0 EXELON FITZPATRICK, LLC AND EXELON GENERATION COMPANY, LLC DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 333 Renewed License No. DPR-59

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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-59 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 333, are hereby incorporated in the 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 333 RENEWED FACILITY OPERATING LICENSE NO. DPR-59 JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 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 DPR-59 License DPR-59 Page 3 Page 3 TSs TSs 1.1-1 1.1-1 1.1-2 1.1-2 Amendment 333 Renewed License No. DPR-59 (4)

Exelon Generation Company 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 without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.

(5)

Pursuant to the Act and 10 CFR Parts 30 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 operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 Exelon Generation Company is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 333, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3)

Fire Protection Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protections program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated November 20, 1972; the SER Supplement No. 1 dated February 1, 1973; the SER Supplement No. 2 dated October 4, 1974; the SER dated August 1, 1979; the SER Supplement dated October 3, 1980; the SER Supplement dated February 13, 1981; the NRC Letter dated February 24,1981; Technical Specification Amendments 34 (dated January 31, 1978), 80 (dated May 22, 1984), 134 (dated July 19, 1989),

135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994), and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985,

1.0 USE AND APPLICATION 1.1 Definitions Definitions 1.1

NOTE-------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

ACTIONS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

CHANNEL CALIBRATION CHANNEL CHECK JAFNPP Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

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.

(continued) 1.1-1 Amendment 333

1.1 Definitions (continued)

Definitions 1.1 CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT 1-131 JAFNPP

a.

Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and

b.

Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the plant specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, l-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in International Commission on Radiological Protection Publication 30 (ICRP-30), "Limits for Intake by Workers," or in NRC Regulatory Guide 1.109, Rev. 1, 1977.

(continued) 1.1-2 Amendment 333

1 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 242 Renewed License No. NPF-11

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 242, 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

/RA/ Robert Kuntz for 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: March 12, 2020

2 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 228 Renewed License No. NPF-18

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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. 228, 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 242 AND 228 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 1.1-1 1.1-1 1.1-2 1.1-2 1.1-3 1.1-3 1.1-4 1.1-4 1.1-5 1.1-5 1.1-6 1.1-6 1.1-7 1.1-7 1.1-8 1.1-8 1.1-9 1.1-9 1.1-10

Renewed License No. NPF-11 Amendment No. 242 (3)

Exelon Generation Company, 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)

Exelon Generation Company, 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)

Exelon Generation Company, 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. 242, 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. 146 01/12/01 Am. 202 07/21/11 Am. 198 09/16/10 Am. 242 03/12/20 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09

Renewed License No. NPF-18 Amendment No. 228 (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)

Exelon Generation Company, 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). 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. 228, 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. 189 07/21/11 Am. 185 09/16/10 Am. 228 03/12/20

1.0 USE AND APPLICATION 1.1 Definitions NOTE-------

Definitions 1.1 The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

ACTIONS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

CHANNEL CALIBRATION LaSalle 1 and 2 Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

The APLHGR shall be applicable to a specific planar height and is equal to the sum of the LHGRs for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST.

Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

(continued)

1. 1-1 Amendment No. 242/228

Definitions 1.1 1.1 Definitions (continued)

CHANNEL CHECK CHANNEL FUNCTIONAL TEST LaSalle 1 and 2 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.

A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

(continued)

1. 1-2 Amendment No. 242/228

Definitions 1.1 1.1 Definitions (continued)

CORE ALTERATION CORE OPERATING LIMITS REPORT ( COLR)

DOSE EQUIVALENT I 131 LaSalle 1 and 2 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a.

Movement of source range monitors, local power range monitors, intermediate range monitors, traversing i ncore probes, or special movable detectors (including undervessel replacement);

and

b.

Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I 131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131, I-132, I-133, I 134, and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites;" Table E-7 of Regulatory Gui de 1.109, Rev. 1, NRC, 1977; or ICRP (continued) 1.1-3 Amendment No. 242/228

1.1 Definitions DOSE EQUIVALENT I-131 (continued)

DRAIN TIME LaSalle 1 and 2 Definitions 1.1 30, Supplement to Part 1, pages 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a.

The water inventory above the TAF is divided by the limiting drain rate;

b.

The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single human error), for all penetration flow paths below the TAF except:

1.

Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2.

Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or (continued)

1. 1-4 Amendment No. 242/228

1.1 Definitions DRAIN TIME (continued)

EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME LaSalle 1 and 2 Definitions 1.1

3.

Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who is in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation devices without offsite power.

c.

The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory;

d.

No additional draining events occur; and

e. Realistic cross-sectional areas and drain rates are used.

A bounding DRAIN TIME may be used in lieu of a calculated value.

The ECCS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ECCS initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).

Times shall include diesel generator starting and sequence loading delays, where applicable.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for selected components provided that the components and method for verification have been previously reviewed and approved by the NRC.

(continued)

1. 1-5 Amendment No. 242/228

Definitions 1.1 1.1 Definitions (continued)

END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) SYSTEM RESPONSE TIME INSERVICE TESTING PROGRAM ISOLATION SYSTEM RESPONSE TIME LaSalle 1 and 2 The EOC-RPT SYSTEM RESPONSE TIME shall be that time interval from initial signal generation by the associated turbine stop valve limit switch or from when the turbine control valve hydraulic oil control oil pressure drops below the pressure switch setpoint to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for selected components provided that the components and method for verification have been previously reviewed and approved by the NRC.

The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 10 CFR 50.55a(f).

The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for selected components provided that the components and method for verification have been previously reviewed and approved by the NRC.

(continued)

1. 1-6 Amendment No. 242/228

Definitions 1.1 1.1 Definitions (continued)

LEAKAGE LINEAR HEAT GENERATION RATE ( LHGR)

LOGIC SYSTEM FUNCTIONAL TEST LaSalle 1 and 2 LEAKAGE shall be:

a.

Identified LEAKAGE

1. LEAKAGE into the drywel l such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b.

Unidentified LEAKAGE A 11 LEAKAGE into the drywel l that is not identified LEAKAGE;

c.

Total LEAKAGE Sum of the identified and unidentified LE A KA GE ; and

d.

Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

The LHGR shall be the heat generation rate per unit length of fuel rod.

It is the integral of the heat flux over the heat transfer area associated with the unit length.

A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

(continued)

1. 1-7 Amendment No. 242/228

Definitions

1. 1 1.1 Definitions (continued)

MINIMUM CRITICAL POWER RATIO (MCPR)

MODE OPERABLE-OPERABILITY RATED THERMAL POWER

( RTP)

REACTOR PROTECTION SYSTEM (RPS) RESPONSE TIME LaSalle 1 and 2 The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each class of fuel.

The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1 1 with fuel in the reactor vessel.

A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3546 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for selected components provided that the components and method for verification have been previously reviewed and approved by the NRC.

(continued) 1.1 8 Amendment No. 242/228

Definitions 1.1 1.1 Definitions (continued)

SHUTDOWN MARGIN (SDM)

STAGGERED TEST BASIS THERMAL POWER TURBINE BYPASS SYSTEM RESPONSE TIME LaSalle 1 and 2 SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:

a.

The reactor is xenon free;

b.

The moderator temperature is~ 68°F, corresponding to the most reactive state; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that a 11 systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER shal 1 be the total reactor core heat transfer rate to the reactor coolant.

The TURBINE BYPASS SYSTEM RESPONSE TIME shall be that time interval from when the turbine bypass control unit generates a turbine bypass valve flow signal until the turbine bypass valves travel to their required positions.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

1. 1-9 Amendment No. 242/228

MODE TITLE 1

Power Operation 2

Startup 3

Hot Shutdown(al 4

Cold Shutdown(ai 5

Refuel i ng(bl Table 1.1 1 (page 1 of 1)

MODES REACTOR MODE SWITCH POSITION Run Refuel (al or Startup/Hot Standby Shutdown Shutdown Shutdown or Refuel Definitions 1.1 AVERAGE REACTOR COOLA~T TEMPERATURE (OF)

NA NA

> 200 s: 200 NA (a)

All reactor vessel head closure bolts fully tensioned.

(b)

One or more reactor vessel head closure bolts less than fully tensioned.

LaSalle 1 and 2 1.1-10 Amendment No. 242/228

3 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 Renewed License No. NPF-39

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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-39 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 243, are hereby incorporated into this renewed license. Exelon Generation Company 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 243 RENEWED FACILITY OPERATING LICENSE NO. NPF-39 LIMERICK GENERATING STATION, UNIT 1 DOCKET NO. 50-352 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-39 License NPF-39 Page 3 Page 3 TSs TSs 1.1-1 1.1-1 Renewed License No. NPF-39 Amendment No. 243 (2)

Pursuant to the Act and 10 CFR Part 70, to receive, possess and to 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, 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, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

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 (except as exempted from compliance in Section 2.D. below) 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 Exelon Generation Company is authorized to operate the facility at reactor core power levels not in excess of 3515 megawatts thermal (100% rated power) in accordance with the conditions specified herein and in Attachment 1 to this license. The items identified in Attachment 1 to this renewed license shall be completed as specified. Attachment 1 is hereby incorporated into this renewed license.

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 243, are hereby incorporated into this renewed license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The following terms are defined so that uniform interpretation of these specifications may be achieved.

The defined terms appear in capitalized type and shall be applicable throughout these Technical Specifications.

ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.

AVERAGE PLANAR EXPOSURE 1.2 The AVERAGE PLANAR EXPOSURE shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

AVERAGE PLANAR LINEAR HEAT GENERATION RATE 1.3 The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATES for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

CHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.

The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

CHANNEL CHECK 1.5 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.6 A CHANNEL FUNCTIONAL TEST shall be:

a.

Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions and channel failure trips.

b.

Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

The CHANNEL FUNCTIONAL TEST may be *performed by any series of sequential, overlapping or total channel steps such that the entire channel is tested, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.

LIMERICK - UNIT 1 1-1 Amendment No. 243

4 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 206 Renewed License No. NPF-85

1.

The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC dated June 25, 2019, 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-85 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 206, are hereby incorporated into this renewed license. Exelon Generation Company 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

/RA/ Robert Kuntz for 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: March 12, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 206 RENEWED FACILITY OPERATING LICENSE NO. NPF-85 LIMERICK GENERATING STATION, UNIT 2 DOCKET NO. 50-353 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-85 License NPF-85 Page 3 Page 3 TSs TSs 1.1-1 1.1-1 Renewed License No. NPF-85 Amendment No. 206 (2)

Pursuant to the Act and 10 CFR Part 70, to receive, possess and to 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, 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, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

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 (except as exempted from compliance in Section 2.D. below) 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 Exelon Generation Company is authorized to operate the facility at reactor core power levels of 3515 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.