Text

Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580
	ML23305A140
Person / Time
Site:	Dresden, Peach Bottom, Nine Mile Point, Clinton, Quad Cities, LaSalle
Issue date:	12/13/2023
From:	Scott Wall; NRC/NRR/DORL/LPL3
To:	Rhoades D; Constellation Energy Generation, Constellation Nuclear
	Wall S, NRR/DORL/LPL3
References
	EPID L-2023-LLA-0077
	Download: ML23305A140 (94)
	v • d • e

December 13, 2023 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNIT 2; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-580 (EPID L-2023-LLA-0077)

Dear Mr. Rhoades:

The U.S. Nuclear Regulatory Commission (NRC or Commission) has issued the enclosed amendments (listed below) in response to the Constellation Energy Generation, LLC (CEG) application dated May 25, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23145A086), as supplemented by letter dated October 20, 2023 (ML23293A103):

1.

Amendment No. 251 to Facility Operating License No. NPF-62 for Clinton Power Station, Unit No. 1;

2.

Amendment No. 283 to Renewed Facility Operating License No. DPR-19 and Amendment No. 276 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, respectively;

3.

Amendment No. 261 to Renewed Facility Operating License No. NPF-11 and Amendment No. 246 to Renewed Facility Operating License No. NPF-18 for LaSalle County Station, Units 1 and 2, respectively;

4.

Amendment No. 195 to Renewed Facility Operating License No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2;

5.

Amendment No. 344 to Subsequent Renewed Facility Operating License No. DPR-44 and Amendment No. 347 to Subsequent Renewed Facility Operating License No. DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, respectively; and

6.

Amendment No. 297 to Renewed Facility Operating License No. DPR-29 and Amendment No. 293 to Renewed Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendments revise the technical specifications (TSs) for each facility in accordance with Technical Specifications Task Force (TSTF) Traveler TSTF-580, Revision 1, Provide Exception

from Entering Mode 4 With No Operable [Residual Heat Removal] RHR Shutdown Cooling.

Specifically, the proposed changes provide a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable.

On October 20, 2023, CEG withdrew its application for TSTF-580 as it pertains to the James A.

FitzPatrick Nuclear Power Plant.

The NRC staff notes that by letter dated November 22, 2023 (ML23284A251), the NRC issued Amendment No. 250 for Clinton Power Station, Unit No. 1. During the issuances of this amendment, a typographical error on page 3 of Facility Operating License No. NPF-62 was introduced. Specifically, in paragraph 2.C.(2) of Facility Operating License No. NPF-62, LLC was removed from Constellation Energy Generation, LLC. The version of page 3 that is being issued with Amendment No. 251 for Clinton Power Station, Unit No. 1, corrects this error. We apologize for any inconvenience this may have caused.

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

Sincerely,

/RA/

Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-461, 50-237, 50-249, 50-373, 50-374, 50-410, 50-277, 50-278, 50-254, and 50-265

Enclosures:

1. Amendment No. 251 to NPF-62

2. Amendment No. 283 to DPR-19

3. Amendment No. 276 to DPR-25

4. Amendment No. 261 to NPF-11

5. Amendment No. 246 to NPF-18

6. Amendment No. 195 to NPF-69

7. Amendment No. 344 to DPR-44

8. Amendment No. 347 to DPR-56

9. Amendment No. 297 to DPR-29

10. Amendment No. 293 to DPR-30

11. Safety Evaluation

12. Notices and Environmental Findings cc: Listserv

CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 251 License No. NPF-62

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 251, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:40:49 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 251 FACILITY OPERATING LICENSE NO. NPF-62 CLINTON POWER STATION, UNIT NO. 1 DOCKET NO. 50-461 Replace the following pages of the Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-62 License NPF-62 Page 3 Page 3 TSs TSs 3.4-22 3.4-22 3.4-23 3.4-23 3.4-24 Amendment No. 251 (4)

Constellation Energy Generation, LLC, pursuant to the Act and to 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation; and (7)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 251, are hereby incorporated into this license.

Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-22 Amendment No. 25136 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown LCO 3.4.9 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES--------------------------

1.

Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor steam dome pressure less than the RHR cut in permissive pressure.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion time of Condition A not met.

B.1 Initiate action to restore RHR Shutdown Cooling subsystem to OPERABLE status.

Immediately C.

Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-23 Amendment No. 251 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately E.

No RHR shutdown cooling subsystem in operation.

AND E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

Immediately No recirculation pump in operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND E.3 Monitor reactor coolant temperature and pressure.

Once per hour

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-24 Amendment No. 251 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control program SR 3.4.9.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control program

CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 283 Renewed License No. DPR-19

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-19 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 283, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:41:43 -05'00'

CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 276 Renewed License No. DPR-25

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-25 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 276, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:42:09 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NOS. 283 AND 276 RENEWED FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-237 AND 50-249 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License DPR-19 License DPR-19 Page 3 Page 3 License DPR-25 License DPR-25 Page 4 Page 4 TSs TSs 3.4.7-1 3.4.7-1 3.4.7-2 3.4.7-2 3.4.7-3 3.4.7-3 3.4.7-4 Renewed License No. DPR-19 Amendment No. 283 (2)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear materials as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct special nuclear materials as may be produced by the operation of the facility.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2957 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 283, 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. 276

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. 276, 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.

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-1 Amendment No. 283 / 276 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Shutdown Cooling (SDC) SystemHot Shutdown LCO 3.4.7 Two SDC subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one SDC subsystem shall be in operation.

NOTES---------------------------

1.

Both required SDC subsystems and recirculation pumps may be not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required SDC subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor vessel coolant temperature less than the SDC cut-in permissive temperature.

ACTIONS

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

Separate Condition entry is allowed for each SDC subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One required SDC subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required SDC subsystem to OPERABLE status.

Immediately C.

Two required SDC subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable SDC subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one required SDC subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one SDC subsystem to OPERABLE status.

Immediately (continued)

Amendment No. 283 / 276

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

No required SDC subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one required SDC subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour Amendment No. 283 / 276

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor vessel coolant temperature is less than the SDC cut-in permissive temperature.

Verify one SDC subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program SR 3.4.7.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor vessel coolant temperature is less than the SDC cut-in permissive temperature.

Verify SDC subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program Amendment No. 283 / 276

CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 261 Renewed License No. NPF-11

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-11 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 261, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:43:16 -05'00'

CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 246 Renewed License No. NPF-18

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-18 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 246, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:44:00 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NOS. 261 AND 246 RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-11 License NPF-11 Page 3 Page 3 License NPF-18 License NPF-18 Page 3 Page 3 TSs TSs 3.4.9-1 3.4.9-1 3.4.9-2 3.4.9-2 3.4.9-3 3.4.9-3 3.4.9-4

Renewed License No. NPF-11 Amendment No. 261 (3)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal).

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 261, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

DELETED (4)

DELETED (5)

DELETED Am. 198 09/16/10 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 Am. 261 12/13/23

Renewed License No. NPF-18 Amendment No. 246 (2)

Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 246, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Am. 185 09/16/10 Am. 246 12/13/23

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-1 Amendment No. 261 / 246 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.9 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES---------------------------

1.

Both RHR shutdown cooling subsystems and recirculation pumps may be not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor vessel pressure less than the RHR cut-in permissive pressure.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately (continued)

Amendment No. 261 / 246

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour Amendment No. 261 / 246

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor vessel pressure is less than the RHR cut-in permissive pressure.

Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program SR 3.4.9.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR cut-in permissive pressure.

Verify RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program Amendment No. 261 / 246

NINE MILE POINT NUCLEAR STATION, LLC LONG ISLAND LIGHTING COMPANY CONSTELLATION ENERGY GENERATION, LLC DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 Renewed License No. NPF-69

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-69 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 195, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:44:49 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 195 RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, UNIT 2 DOCKET NO. 50-410 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-69 License NPF-69 Page 4 Page 4 TSs TSs 3.4.9-1 3.4.9-1 3.4.9-2 3.4.9-2 3.4.9-3 3.4.9-3 3.4.9-4 Renewed License No. NPF-69 Amendment 117 through 194, 195 (1)

Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the facility at reactor core power levels not in excess of 3988 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 195, are hereby incorporated into this license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Fuel Storage and Handling (Section 9.1, SSER 4)*

a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.

b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.

c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.

d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.

(4)

Turbine System Maintenance Program (Section 3.5.1.3.10 SER)

The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturers calculations of missile generation probabilities.

(Submitted by NMPC letter dated October 30, 1989 from C.D. Terry and approved by NRC letter dated March 15, 1990 from Robert Martin to Mr. Lawrence Burkhardt, III).

The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-1 Amendment 91, 109, 185 195 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.9 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES----------------------------------------------

1.

Both RHR shutdown cooling subsystems and recirculation pumps may be not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor steam dome pressure less than the RHR cut-in permissive pressure.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-2 Amendment 91, 185 195 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met B.1 Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately (continued)

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour Amendment 91, 185 195

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-4 Amendment 91, 150, 152 195 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut-in permissive pressure.

Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program SR 3.4.9.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR cut-in permissive pressure.

Verify RHR shutdown cooling subsystem Locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program

CONSTELLATION ENERGY GENERATION, LLC PSEG NUCLEAR, LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 344 Subsequent Renewed License No. DPR-44

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Subsequent Renewed Facility Operating License No. DPR-44 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 344, are hereby incorporated in the license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Subsequent Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:45:41 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 344 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-44 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 DOCKET NO. 50-277 Replace the following pages of the Subsequent 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-44 License DPR-44 Page 3 Page 3 TSs TSs 3.4-16 3.4-16 3.4-17 3.4-17 3.4-18 3.4-18 3.4-19 3.4-19 3.4-20 3.4-20 3.4-21 3.4-21 3.4-22 3.4-22 3.4-23 3.4-23 3.4-24 3.4-24 3.4-25 3.4-25 3.4-26 3.4-26 3.4-27 3.4-27 3.4-28 3.4-28 3.4-29

Page 3 Subsequent Renewed License No. DPR-44 Amendment No. 344 (1)

Constellation Energy Generation, LLC, pursuant to Section 104b of the Act and 10 CFR Part 50, Licensing of Production and Utilization Facilities, to possess, use, and operate the facility and PSEG Nuclear to possess the facility at the designated location in Peach Bottom, York County, Pennsylvania in accordance with the procedures and limitations set forth in this license; (2)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or components; (5)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.

C.

This subsequent renewed 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1)

Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the Peach Bottom Atomic Power Station, Unit 2, at steady state reactor core power levels not in excess of 4016 megawatts thermal.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 344, are hereby incorporated in the license.

Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.

RHR Shutdown Cooling System Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES---------------------------

1.

Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One required RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 2 3.4-16 Amendment No. 344

RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

PBAPS UNIT 2 3.4-17 CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two required RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately Amendment No. 344

PBAPS UNIT 2 3.4-18 RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour Amendment No. 344

RHR Shutdown Cooling System Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.7.2

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

1.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

2.

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-19 Amendment No. 344

RHR Shutdown Cooling System Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES---------------------------

1.

Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 4.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required RHR shutdown cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately (continued)

PBAPS UNIT 2 3.4-20 Amendment No. 344

RHR Shutdown Cooling System Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Verify reactor coolant circulating by an alternate method.

AND C.2 Monitor reactor coolant temperature and pressure.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.8.2

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

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-21 Amendment No. 344

RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within the limits specified in the PTLR.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE--------

Required Action A.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in MODE 1, 2, or 3.

A.1 Restore parameter(s) to within limits.

AND A.2 Determine RCS is acceptable for continued operation.

30 minutes 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours (continued)

PBAPS UNIT 2 3.4-22 Amendment No. 344

RCS P/T Limits 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE---------

Required Action C.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in other than MODES 1, 2, and 3.

C.1 Initiate action to restore parameter(s) to within limits.

AND C.2 Determine RCS is acceptable for operation.

Immediately Prior to entering MODE 2 or 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify:

a.

RCS pressure and RCS temperature are within the limits specified in the PTLR; and b.

RCS heatup and cooldown rates are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

(continued)

PBAPS UNIT 2 3.4-23 Amendment No. 344

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are within the criticality limits specified in the PLTR.

Once within 15 minutes prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the bottom head coolant temperature and the reactor pressure vessel (RPV) coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump SR 3.4.9.4

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump (continued)

PBAPS UNIT 2 3.4-24 Amendment No. 344

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5

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

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.6

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

Not required to be performed until 30 minutes after RCS temperature 80°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.7

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature 100°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-25 Amendment No. 344

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 2 3.4-26 Amendment No. 344

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 2 3.4-27 Amendment No. 344

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 2 3.4-28 Amendment No. 344

Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be 1053 psig.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Reactor steam dome pressure not within limit.

A.1 Restore reactor steam dome pressure to within limit.

15 minutes B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 1053 psig.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-29 Amendment No. 344

CONSTELLATION ENERGY GENERATION, LLC PSEG NUCLEAR, LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 347 Subsequent Renewed License No. DPR-56

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Subsequent Renewed Facility Operating License No. DPR-56 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 347, are hereby incorporated in the license. Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Subsequent Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:46:41 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NO. 347 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 DOCKET NO. 50-278 Replace the following pages of the Subsequent 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-56 License DPR-56 Page 3 Page 3 TSs TSs 3.4-16 3.4-16 3.4-17 3.4-17 3.4-18 3.4-18 3.4-19 3.4-19 3.4-20 3.4-20 3.4-21 3.4-21 3.4-22 3.4-22 3.4-23 3.4-23 3.4-24 3.4-24 3.4-25 3.4-25 3.4-26 3.4-26 3.4-27 3.4-27 3.4-28 3.4-28 3.4-29

Page 3 Subsequent Renewed License No. DPR-56 Amendment No. 347 Pennsylvania in accordance with the procedures and limitations set forth in this license; (2)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or when associated with radioactive apparatus or components; (5)

Constellation Energy Generation, LLC, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Limerick Generating Station, Units 1 and 2.

C.

This subsequent renewed 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, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1)

Maximum Power Level Constellation Energy Generation, LLC is authorized to operate the Peach Bottom Atomic Power Station, Unit No. 3, at steady state reactor core power levels not in excess of 4016 megawatts thermal.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 347, are hereby incorporated in the license.

Constellation Energy Generation, LLC shall operate the facility in accordance with the Technical Specifications.

RHR Shutdown Cooling System Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES---------------------------

1.

Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One required RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 3 3.4-16 Amendment No. 347

RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two required RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

DC.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately (continued)

PBAPS UNIT 3 3.4-17 Amendment No. 347

PBAPS UNIT 3 3.4-18 RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour Amendment No. 347

RHR Shutdown Cooling System Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.7.2

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

1.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

2.

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-19 Amendment No. 347

RHR Shutdown Cooling System Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES---------------------------

1.

Both required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 4.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required RHR shutdown cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately (continued)

PBAPS UNIT 3 3.4-20 Amendment No. 347

RHR Shutdown Cooling System Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Verify reactor coolant circulating by an alternate method.

AND C.2 Monitor reactor coolant temperature and pressure.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.8.2

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

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-21 Amendment No. 347

RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within the limits specified in the PTLR.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE---------

Required Action A.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in MODE 1, 2, or 3.

A.1 Restore parameter(s) to within limits.

AND A.2 Determine RCS is acceptable for continued operation.

30 minutes 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours (continued)

PBAPS UNIT 3 3.4-22 Amendment No. 347

RCS P/T Limits 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE---------

Required Action C.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in other than MODES 1, 2, and 3.

C.1 Initiate action to restore parameter(s) to within limits.

AND C.2 Determine RCS is acceptable for operation.

Immediately Prior to entering MODE 2 or 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify:

a.

RCS pressure and RCS temperature are within the limits specified in the PTLR; and b.

RCS heatup and cooldown rates are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

(continued)

PBAPS UNIT 3 3.4-23 Amendment No. 347

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are within the criticality limits specified in the PTLR.

Once within 15 minutes prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the bottom head coolant temperature and the reactor pressure vessel (RPV) coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump SR 3.4.9.4

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump (continued)

PBAPS UNIT 3 3.4-24 Amendment No. 347

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5

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

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.6

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

Not required to be performed until 30 minutes after RCS temperature 80°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.7

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature 100°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-25 Amendment No. 347

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 3 3.4-26 Amendment No. 347

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 3 3.4-27 Amendment No. 347

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 3 3.4-28 Amendment No. 347

Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be 1053 psig.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Reactor steam dome pressure not within limit.

A.1 Restore reactor steam dome pressure to within limit.

15 minutes B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 1053 psig.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-29 Amendment No. 347

CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 297 Renewed License No. DPR-29

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-29 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 297, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:48:16 -05'00'

0 CONSTELLATION ENERGY GENERATION, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 293 Renewed License No. DPR-30

1.

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

A.

The application for amendment by Constellation Energy Generation, LLC dated May 25, 2023, as supplement by letter dated October 20, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Renewed Facility Operating License No. DPR-30 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 293, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance: December 13, 2023 Jeffrey A.

Whited Digitally signed by Jeffrey A. Whited Date: 2023.12.13 16:52:38 -05'00'

ATTACHMENT TO LICENSE AMENDMENT NOS. 297 AND 293 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License DPR-29 License DPR-29 Page 4 Page 4 License DPR-30 License DPR-30 Page 4 Page 4 TSs TSs 3.4.7-1 3.4.7-1 3.4.7-2 3.4.7-2 Renewed License No. DPR-29 Amendment No. 297 B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 297, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

D.

Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 17, 2006.

Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The CSP was approved by License Amendment No. 249 as modified by License Amendment No. 259.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-30 Amendment No. 293 B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 293, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

D.

Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 17, 2006.

Constellation Energy Generation, LLC shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The CSP was approved by License Amendment No. 244 and modified by License Amendment No. 254.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

RHR Shutdown Cooling SystemHot Shutdown 3.4.7 Quad Cities 1 and 2 3.4.7-1 Amendment No. 297 / 293 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE.

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

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR cut-in permissive pressure.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

(continued)

RHR Shutdown Cooling SystemHot Shutdown 3.4.7 Quad Cities 1 and 2 3.4.7-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately E.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour Amendment No. 297 / 293

1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 251 TO FACILITY OPERATING LICENSE NO. NPF-62 AMENDMENT NO. 283 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19 AMENDMENT NO. 276 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25 AMENDMENT NO. 261 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-11 AMENDMENT NO. 246 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-18 AMENDMENT NO. 195 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 AMENDMENT NO. 344 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-44 AMENDMENT NO. 347 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-56 AMENDMENT NO. 297 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 293 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 CONSTELLATION ENERGY GENERATION, LLC CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 LASALLE COUNTY STATION, UNITS 1 AND 2 NINE MILE POINT NUCLEAR STATION, UNIT 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-461, 50-237, 50-249, 50-373, 50-374, 50-410, 50-277, 50-278, 50-254, AND 50-265 Application (i.e., initial and supplements)

Safety Evaluation Date May 25, 2023, ML23145A086 October 20, 2023, ML23293A103 December 13, 2023 Principal Contributor to Safety Evaluation Ravi Grover Scott Wall

1.0 PROPOSED CHANGE

S Constellation Energy Generation, LLC (CEG, the licensee) requested changes to the technical specifications (TSs) for Clinton Power Station (Clinton), Unit No. 1; Dresden Nuclear Power Station (Dresden), Units 2 and 3; James A. FitzPatrick Nuclear Power Plant (FitzPatrick);

LaSalle County Station (LaSalle), Units 1 and 2; Nine Mile Point Nuclear Station, Unit 2 (NMP-2); Peach Bottom Atomic Power Station (Peach Bottom), Units 2 and 3; and Quad Cities Nuclear Power Station (Quad Cities), Units 1 and 2 (collectively, the facilities), by license amendment request (LAR), dated May 25, 2023. The amendments would revise the TSs for each facility based on Technical Specifications Task Force (TSTF) Traveler TSTF-580, Revision 1, Provide Exception from Entering Mode 4 With No Operable RHR [Residual Heat Removal] Shutdown Cooling (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21025A232), and the associated U.S. Nuclear Regulatory Commission (NRC, the Commission) staff safety evaluation (SE) of TSTF-580 (ML21188A227).

By letter dated October 20, 2023, CEG withdrew its request to adopt TSTF-580 for FitzPatrick.

Irradiated fuel in the shutdown reactor core generates heat during the decay of fission products and increases the temperature of the reactor coolant. This decay heat must be removed to reduce the temperature of the reactor coolant to less than or equal to 200 or 212 degrees Fahrenheit (° F), depending on the plant. This decay heat is removed by the RHR shutdown cooling system in preparation for performing refueling or maintenance operations, or for keeping the reactor in the hot shutdown condition or cold shutdown condition.

There are two to four redundant, manually controlled, shutdown cooling subsystems of the RHR system that provide decay heat removal for each reactor unit. Each of the shutdown cooling subsystems of the RHR system can provide the required decay heat removal. Each RHR shutdown cooling subsystem consists of one or two motor-driven pumps, a heat exchanger, and associated piping and valves. The RHR heat exchangers transfer heat to the associated service water system. Some piping and heat exchangers that are passive components may be common to more than one subsystem.

The hot shutdown TSs for the RHR shutdown cooling system for each facility are listed in Table 1 below. The table provides the TS number, limiting condition for operation (LCO), and applicability.

Table 1: TSs for RHR Shutdown Cooling System - Hot Shutdown Facility TSs for RHR Shutdown Cooling System - Hot Shutdown Clinton TS 3.4.9:

Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.9:

Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

Applicability:

Mode 3 with reactor steam dome pressure less than the RHR cut in permissive pressure.

Dresden TS 3.4.7:

Shutdown Cooling (SDC) System-Hot Shutdown LCO 3.4.7:

Two SDC subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one SDC subsystem shall be in operation.

Applicability:

MODE 3, with reactor vessel coolant temperature less than the SDC cut-in permissive temperature.

LaSalle TS 3.4.9:

Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.9:

Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

Applicability:

MODE 3 with reactor vessel pressure less than the RHR cut-in permissive pressure.

NMP-2 TS 3.4.9:

Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.9:

Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

Applicability:

MODE 3 with reactor steam dome pressure less than the RHR cut-in permissive pressure.

Facility TSs for RHR Shutdown Cooling System - Hot Shutdown Peach Bottom TS 3.4.7:

Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.7:

Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

Applicability:

MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

Quad Cities TS 3.4.7:

Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO 3.4.7:

Two RHR shutdown cooling subsystems shall be OPERABLE.

Applicability:

MODE 3, with reactor steam dome pressure less than the RHR cut-in permissive pressure.

1.1 Proposed TS Changes to Adopt TSTF-580 In accordance with NRC staff approved TSTF-580, the licensee proposed changes that would revise the TSs listed in Table 1. Specifically, the licensee proposed the following changes to adopt TSTF-580:

Condition A is changed to be limited to a single inoperable subsystem by revising it to state: One RHR shutdown cooling subsystem inoperable with a Required Action to Verify an alternate method of decay heat removal is available.

Condition B addresses situations when Required Action A.1 and associated completion time (CT) are not met. The plural (s) is deleted in Required Action B.1 as a conforming change to Condition A, which now addresses a single inoperable RHR shutdown cooling subsystem.

A new Condition C is added, which addresses two RHR shutdown cooling subsystems inoperable with a Required Action C.1 to verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem. The new Condition C Required Action has a CT of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

A new Condition D is added to address situations when new Required Action C.1 and associated CT are not met. New Required Action D.1 requires action be initiated to restore one RHR shutdown cooling subsystem to operable status immediately. Required Action D.1 is modified by a note that states that LCO 3.0.3 and all other LCO Required Actions requiring a mode change to Mode 4 may be suspended until one RHR shutdown cooling subsystem is restored to operable status.

Existing Condition C and associated Required Actions are renumbered as Condition E due to the new Conditions C and D.

TSTF-580 makes additional changes to the LCO Actions that were revised by TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, which is consistent with the NRC staffs approval of TSTF-580. The TSTF-580 justification states that adoption is dependent on the previous adoption of TSTF-566-A. The NRC staff approved adoption of TSTF-566 for the facilities on April 1, 2021 (ML21033A530).

1.2 Additional Proposed TS Changes In addition to the changes proposed consistent with the traveler discussed in section 1.1, the licensee proposed the following variations.

1.2.1 Editorial Variations The Dresden, Peach Bottom, and Quad Cities TSs listed in Table 1 use different numbering than the standard technical specifications (STS) on which TSTF-580 was based. The Dresden TSs use the term Shutdown Cooling (SDC) instead of Residual Heat Removal (RHR)

Shutdown Cooling. The Quad Cities TS listed in Table 1 do not currently include a Condition C.

The licensee proposes to make these changes to the TSs as described. These differences are editorial and do not affect the applicability of TSTF-580 to the proposed LAR with respect to these facilities.

1.2.2 Other Variations Condition A for Quad Cities TS 3.4.7 includes two additional required actions that are not included in the STS. These differences do not affect the applicability of TSTF-580 to the proposed LAR with respect to Quad Cities, but are evaluated in section 3.2 of this SE.

2.0 REGULATORY EVALUATION

The regulation at paragraph 50.36(c)(2) of Title 10 of the Code of Federal Regulations (10 CFR) requires that TSs include LCOs. Per 10 CFR 50.36(c)(2)(i), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. The regulation also requires that when an LCO of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met.

The NRC staffs guidance for the review of TSs is provided in chapter 16.0, Technical Specifications, of NUREG-0800, Revision 3, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition (SRP),

March 2010 (ML100351425). As described therein, as part of the regulatory standardization effort, the NRC staff has prepared STSs for each of the LWR nuclear designs. Accordingly, the NRC staffs license amendment request review includes consideration of whether the proposed changes are consistent with the STSs1, as modified by NRC approved travelers.

1 U.S. Nuclear Regulatory Commission, Standard Technical Specifications, General Electric Plants, [Boiling-Water Reactor]

BWR/4, NUREG-1433, Volume 1, Specifications, and Volume 2, Bases, 5.0, September 2021 (ML21272A357 and ML21272A358, respectively).

U.S. Nuclear Regulatory Commission, Standard Technical Specifications, General Electric Plants, BWR/6, NUREG-1434, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, September 2021 (ML21271A582 and ML21271A596, respectively).

Traveler TSTF-580 revised the STSs related to RHR shutdown cooling system. The NRC approved TSTF-580 under the consolidated line item improvement process (CLIIP) on July 11, 2021 (ML21188A283).

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes to Adopt TSTF-580 The NRC staff compared the licensees proposed TS changes in section 1.1 of this SE against the changes approved in TSTF-580. In accordance with the SRP, chapter 16.0, the NRC staff determined that the STS changes approved in TSTF-580 are applicable because each facility is a BWR-design plant, and the NRC staff approved the TSTF-580 changes for BWR designs. The NRC staff finds that the licensees proposed changes, as stated in section 1.1 of this SE, are consistent with those found acceptable in TSTF-580.

In the SE of TSTF-580, the NRC staff concluded that TSTF-580 changes to STS 3.4.9, Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown, Condition A, Required Actions A.1 and B.1, and new Condition C, Required Action C.1, and associated CTs were acceptable because these changes preserve the existing requirements and do not alter the way the TSs are implemented. Therefore, the NRC staff finds these changes continue to meet the requirements of 10 CFR 50.36(c)(2)(i) by providing remedial actions for when the LCO is not met.

The NRC staff also concluded that the addition of TSTF-580 proposed new Condition D to STS 3.4.9 is acceptable because without an operable RHR shutdown cooling subsystem, and in a period of high decay heat load, it may not be possible to reduce the reactor coolant system temperature to the Mode 4 entry condition within the CT. Under this condition, remaining in Mode 3 allows fission product decay heat and other residual heat from the reactor core to be transferred at a rate such that specified acceptable fuel design limits and the design conditions of the reactor coolant pressure boundary will not be exceeded. The CT reflects the importance of restoring a normal path for heat removal. The NRC staff finds that proposed new Condition D and associated Required Action D.1 and CT, are acceptable because they provide appropriate remedial actions if the LCO is not met and, therefore, continues to meet the requirements of 10 CFR 50.36(c)(2)(i).

The NRC staff finds that the proposed changes to the TSs listed in Table 1 are acceptable because the proposed changes continue to meet the requirements of 10 CFR 50.36(c)(2)(i), as discussed in section 3.0 of the NRC staffs SE of TSTF-580.

3.2 Additional Proposed TS Changes When in Condition A, if both RHR shutdown cooling subsystems are inoperable, the Quad Cities TS 3.4.7 also requires operators to:

verify reactor coolant circulation by an alternative method (current Required Action A.2) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter and monitor reactor coolant temperature and pressure (current Required Action A.3) once per hour.

The new Condition E requires the same actions as proposed Required Actions E.2 and E.3. As such, requiring these actions under Condition A is no longer needed as modified. Therefore, the proposed changes continue to meet the requirements of 10 CFR 50.36(c)(2)(i), as discussed in section 3.0 of the NRC staffs SE of TSTF-580.

3.3 TS Change Consistency The NRC staff reviewed the proposed TS changes for technical clarity and consistency with the existing requirements for customary terminology and formatting. The NRC staff finds that the proposed changes are consistent with chapter 16.0 of the SRP and are therefore acceptable.

4.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

2 NOTICES AND ENVIRONMENTAL FINDINGS RELATED TO AMENDMENT NO. 251 TO FACILITY OPERATING LICENSE NO. NPF-62 AMENDMENT NO. 283 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19 AMENDMENT NO. 276 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25 AMENDMENT NO. 261 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-11 AMENDMENT NO. 246 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-18 AMENDMENT NO. 195 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69 AMENDMENT NO. 344 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-44 AMENDMENT NO. 347 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-56 AMENDMENT NO. 297 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 293 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 CONSTELLATION ENERGY GENERATION, LLC CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 LASALLE COUNTY STATION, UNITS 1 AND 2 NINE MILE POINT NUCLEAR STATION, UNIT 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-461, 50-237, 50-249, 50-373, 50-374, 50-410, 50-277, 50-278, 50-254, AND 50-265 Application (i.e., initial and supplements)

Safety Evaluation Date May 25, 2023, ML23145A086 October 20, 2023, ML23293A103 December 13, 2023

1.0 INTRODUCTION

Constellation Energy Generation, LLC, requested changes to the technical specifications (TSs) for Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. FitzPatrick Nuclear Power Plant; LaSalle County Station, Units 1 and 2; Nine Mile Point Nuclear Station, Unit 2; Peach Bottom Atomic Power Station, Units 2 and 3; and Quad Cities Nuclear Power Station, Units 1 and 2 (collectively, the facilities), by license amendment request (LAR), dated May 25, 2023. The amendments would revise the TSs for each facility based on Task Force (TSTF) Traveler TSTF-580, Revision 1, Provide Exception from Entering Mode 4 With No Operable RHR [Residual Heat Removal] Shutdown Cooling (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21025A232), and the associated U.S. Nuclear Regulatory Commission (NRC, the Commission) staff safety evaluation of TSTF-580 (ML21188A227).

By letter dated October 20, 2023, CEG withdrew its request to adopt TSTF-580 for the James A. FitzPatrick Nuclear Power Plant.

On July 11, 2023, the NRC published a notice of consideration of approval of the application in the Federal Register (88 FR 44165). The supplemental letter dated October 20, 2023, provided additional information that clarified the application, did not expand the scope of the application as noticed, and did not change the NRC staff proposed no significant hazards consideration determination as published in the Federal Register on July 11, 2023 (88 FR 44165).

2.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Illinois, New York State, and Commonwealth of Pennsylvania officials were notified of the proposed issuance of the amendments on October 26, 2023. The relevant officials had no comments.

3.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in Title 10 of the Code of Federal Regulations (10 CFR), part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, which was published in the Federal Register on July 11, 2023 (88 FR 44165), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

SUBJECT:

CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNIT 2; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-580 (EPID L-2023-LLA-0077) DATED DECEMBER 13, 2023 DISTRIBUTION:

PUBLIC RidsNrrDorlLpl1 Resource RidsNrrDorlLpl3 Resource RidsRgn1MailCenter Resource RidsRgn3MailCenter Resource RidsNrrLASLent Resource RidsNrrLASRohrer Resource RidsNrrLAKEntz Resource RidsNrrLAKZeleznock Resource RidsAcrs_MailCTR Resource RidsNrrPMConstellation Resource RidsNrrPMClinton Resource RidsNrrPMDresden Resource RidsNrrPMFitzPatrick Resource RidsNrrPMLaSalle Resource RidsNrrPMNineMilePoint Resource RidsNrrPMPeachBottom Resource RidsNrrPMQuadCities Resource RidsNrrDssStsb Resource RidsNrrDssSnsb Resource RGrover, NRR Accession No.: ML23305A140 NRR-058 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DSS/STSB/BC (A)

NAME SWall SRohrer SMehta DATE 11/01/2023 11/02/2023 11/03/2023 OFFICE OGC - NLO NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME MWright JWhited SWall DATE 11/13/2023 12/13/2023 12/13/2023 OFFICIAL RECORD COPY

v t e Letter Sequence Approval
EPID:L-2023-LLA-0077, TSTF-580 (Approved, Closed)
Initiation Request, Request Acceptance Administration Questions 21 September 2023 Answers Results Approval Other:
MONTHYEAR2023-05-25 [Table View]

ML23305A140

Text

SUBJECT:

Dear Mr. Rhoades:

Enclosures:

Attachment:

Attachment:

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1.0 PROPOSED CHANGE

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 CONCLUSION

1.0 INTRODUCTION

2.0 STATE CONSULTATION

3.0 ENVIRONMENTAL CONSIDERATION

SUBJECT:

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