ML20021A070

Issuance of Amendments to Delete License Conditions for Decommissioning Trusts

ML20021A070
Person / Time
Site:	Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle, Crane
Issue date:	04/06/2020
From:	Blake Purnell Plant Licensing Branch III
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Purnell B
References
EPID L-2019-LLA-0185
Download: ML20021A070 (182)

Text

April 6, 2020 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 1, 2, AND 3; JAMES A. FITZPATRICK NUCLEAR POWER PLANT; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; PEACH BOTTOM ATOMIC POWER STATION, UNITS 1, 2, AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2; AND R. E. GINNA NUCLEAR POWER PLANT - ISSUANCE OF AMENDMENTS TO DELETE LICENSE CONDITIONS FOR DECOMMISSIONING TRUSTS (EPID L-2019-LLA-0185)

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the following enclosed amendments in response to the Exelon Generation Company, LLC (Exelon) application dated August 28, 2019 (Agencywide Documents Access and Management System Accession No. ML19240B609):

1.

Amendment No. 208 to Renewed Facility Operating License No. NPF-72 and Amendment No. 208 to Renewed Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, respectively;

2.

Amendment No. 214 to Renewed Facility Operating License No. NPF-37 and Amendment No. 214 to Renewed Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively;

3.

Amendment No. 230 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No. 1;

4.

Amendment No. 48 to Facility Operating License No. DPR-2, Amendment No. 267 to Renewed Facility Operating License No. DPR-19, and Amendment No. 260 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 1, 2, and 3, respectively;

5.

Amendment No. 334 to Renewed Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant;

6.

Amendment No. 243 to Renewed Facility Operating License No. NPF-11 and Amendment No. 229 to Renewed Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2, respectively;

7.

Amendment No. 244 to Renewed Facility Operating License No. NPF-39 and Amendment No. 207 to Renewed Facility Operating License No. NPF-85 for the Limerick Generating Station, Units 1 and 2, respectively;

8.

Amendment No. 242 to Renewed Facility Operating License No. DPR-63 and Amendment No. 180 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2, respectively;

9.

Amendment No. 16 to Facility Operating License No. DPR-12, Amendment No. 333 to Subsequent Renewed Facility Operating License No. DPR-44, and Amendment No. 336 to Subsequent Renewed Facility Operating License No. DPR-56 for the Peach Bottom Atomic Power Station, Units 1, 2, and 3, respectively;

10.

Amendment No. 280 to Renewed Facility Operating License No. DPR-29 and Amendment No. 275 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively; and

11.

Amendment No. 140 to Renewed Facility Operating License No. DPR-18 for the R. E. Ginna Nuclear Power Plant.

The amendments delete certain license conditions that specify requirements for decommissioning trust agreements for these facilities. The amendments also delete some obsolete license conditions associated with completed license transfers for these facilities.

Upon the implementation of the amendments, the decommissioning trust fund requirements in Title 10 of the Code of Federal Regulations (10 CFR) 50.75(h)(1) and (3) will apply to Exelon; PSEG Nuclear LLC; Nine Mile Point Nuclear Station, LLC; and R. E. Ginna Nuclear Power Plant, LLC.

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

Sincerely,

/RA/

Blake Purnell, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461,50-010, 50-237, 50-249, 50-333, 50-373, 50-374, 50-352, 50-353, 50-220, 50-410, 50-171 50-277, 50-278, 50-254, 50-265, and 50-244

Enclosures:

1.

Amendment No. 208 to NPF-72

2.

Amendment No. 208 to NPF-77

3.

Amendment No. 214 to NPF-37

4.

Amendment No. 214 to NPF-66

5.

Amendment No. 230 to NPF-62

6.

Amendment No. 48 to DPR-2

7.

Amendment No. 267 to DPR-19

8.

Amendment No. 260 to DPR-25

9.

Amendment No. 334 to DPR-59

10. Amendment No. 243 to NPF-11

11. Amendment No. 229 to NPF-18

12. Amendment No. 244 to NPF-39

13. Amendment No. 207 to NPF-85

14. Amendment No. 242 to DPR-63

15. Amendment No. 180 to NPF-69

16. Amendment No. 16 to DPR-12

17. Amendment No. 333 to DPR-44

18. Amendment No. 336 to DPR-56

19. Amendment No. 280 to DPR-29

20. Amendment No. 275 to DPR-30

21. Amendment No. 140 to DPR-18

22. Safety Evaluation cc: Listserv

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 208 Renewed License No. NPF-72

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-72 is hereby amended by deleting paragraphs 2.C.(9), 2.C.(10), and 2.C.(11).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 208 Renewed License No. NPF-77

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-77 is hereby amended by deleting paragraphs 2.C.(8), 2.C.(9), and 2.C.(10).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS.208 AND 208 RENEWED FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-72 License NPF-72 Page 4 Page 4 Page 5 Page 5 (pagination)

Page 6 Page 6 (pagination)

Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

License NPF-77 License NPF-77 Page 4 Page 4 Page 5 Page 5 (pagination)

Page 6 Page 6 (pagination)

Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

Page 9 Renewed License No. NPF-72 Amendment No. 208 (3)

Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agencys final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provision of 10 CFR Section 50.54(s)(2) will apply.

(4)

Deleted.

(5)

Deleted.

(6)

Deleted.

(7)

Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 193, are hereby incorporated into this renewed license.

The licensee shall operate the facility in accordance with the Additional Conditions.

(8)

Exelon Generation Company shall provide to the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Companys consolidated net utility plant, as recorded on Exelon Generation Companys books of account.

(9)

Deleted.

(10)

Deleted.

(11)

Deleted.

(12)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel Renewed License No. NPF-72 Amendment No. 208 (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (13)

License Renewal License Conditions (a)

The information in the UFSAR supplement, submitted pursuant to 10 CFR 54.21(d), as revised during the license renewal application review process, and as supplemented by the Commitments applicable to Braidwood Unit 1 in Appendix A of the Safety Evaluation Report Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (SER) dated July 2015, is collectively the License Renewal UFSAR Supplement. This Supplement is henceforth part of the UFSAR which will be updated in accordance with 10 CFR 50.71(e). As such, the licensee may make changes to the programs and activities applicable to Braidwood Unit 1 described in this Supplement provided the licensee evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(b)

This License Renewal UFSAR Supplement, as revised per License Condition 13(a) above, describes certain programs to be implemented and activities to be completed prior to the period of extended operation.

1.

The licensee shall implement those new programs and enhancements to existing programs no later than April 17, 2026.

2.

The licensee shall complete those activities as noted in the Commitments applicable to Braidwood Unit 1 in this Supplement no later than April 17, 2026 or the end of the last refueling outage prior to the period of extended operation, whichever occurs later.

3.

The licensee shall notify the NRC in writing within 30 days after having accomplished item (b)1 above and include the status of those activities that have been or remain to be completed in item (b)2 above.

Renewed License No. NPF-72 Amendment No. 208 (c)

The flux thimble tube corrective actions, inspections, and replacements identified in the SER, Commitment No. 24, for Braidwood Units 1 and 2, shall be implemented in accordance with the schedule in the Commitment. Periodic eddy current testing/inspections of all flux thimble tubes shall be performed at least every two refueling outages, and the data shall be trended and retained in auditable form. A flux thimble tube shall not remain in service for more than two (2) operating fuel cycles without successful completion of eddy current testing for that thimble tube.

(14)

Adoption of 10 CFR 50.69, Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants Exelon is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using:

Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2, Class 3, and non-Code class SSCs and their associated supports; and the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e.,

seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in the license amendment No. 198, dated October 22, 2018.

Exelon will complete the updated implementation items listed in of Exelon letter to NRC dated September 13, 2018, prior to implementation of 10 CFR 50.69. All issues identified in the attachment will be addressed and any associated changes will be made, focused scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2),

and any findings will be resolved and reflected in the PRA of record prior to implementation of the 10 CFR 50.69 categorization process.

Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment approach).

Renewed License No. NPF-72 Amendment No. 208 D.

An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1938, issued October 8, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

E.

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, as supplemented and amended, and as approved in the SER dated November 1983 and its supplements, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualifications, 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:

Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3, submitted by letter dated May 17, 2006.

Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 168 and modified by License Amendment No. 185.

G.

Deleted H.

The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

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

Renewed License No. NPF-72 Amendment No. 208 I.

This renewed license is effective as of the date of issuance and shall expire at midnight on October 17, 2046. In addition, Amendment 187 shall be implemented by March 16, 2016, and Amendment 188 shall be implemented prior to MODE 4 following the Fall 2016 refueling outage (i.e., A1R19).

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William M. Dean, Director Office of Nuclear Reactor Regulation Appendices:

1.

Appendix A - Technical Specifications (NUREG-1276)

2.

Appendix B - Environmental Protection Plan

3.

Appendix C - Additional Conditions Date of Issuance: January 27, 2016 Renewed License No. NPF-77 Amendment No. 208 (3)

Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agencys final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provision of 10 CFR Section 50.54(s)(2) will apply.

(4)

Deleted.

(5)

Deleted.

(6)

Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 193, are hereby incorporated into this renewed license.

The licensee shall operate the facility in accordance with the Additional Conditions.

(7)

Exelon Generation Company, LLC, shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC, to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Companys consolidated net utility plant, as recorded on Exelon Generation Company, LLCs books of account.

(8)

Deleted.

(9)

Deleted.

(10)

Deleted.

(11)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel Renewed License No. NPF-77 Amendment No. 208 (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (12)

License Renewal License Conditions (a)

The information in the UFSAR supplement, submitted pursuant to 10 CFR 54.21(d), as revised during the license renewal application review process, and as supplemented by the Commitments applicable to Braidwood Unit 2 in Appendix A of the Safety Evaluation Report Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (SER) dated July 2015, is collectively the License Renewal UFSAR Supplement. This Supplement is henceforth part of the UFSAR which will be updated in accordance with 10 CFR 50.71(e). As such, the licensee may make changes to the programs and activities applicable to Braidwood Unit 2 described in this Supplement provided the licensee evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(b)

This License Renewal UFSAR Supplement, as revised per License Condition 12(a) above, describes certain programs to be implemented and activities to be completed prior to the period of extended operation.

1.

The licensee shall implement those new programs and enhancements to existing programs no later than June 18, 2027.

2.

The licensee shall complete those activities as noted in the Commitments applicable to Braidwood Unit 2 in this Supplement no later than June 18, 2027 or the end of the last refueling outage prior to the period of extended operation, whichever occurs later.

3.

The licensee shall notify the NRC in writing within 30 days after having accomplished item (b)1 above and include the status of those activities that have been or remain to be completed in item (b)2 above.

Renewed License No. NPF-77 Amendment No. 208 (c)

The flux thimble tube corrective actions, inspections, and replacements identified in the SER, Commitment No. 24, for Braidwood Units 1 and 2, shall be implemented in accordance with the schedule in the Commitment. Periodic eddy current testing/inspections of all flux thimble tubes shall be performed at least every two refueling outages, and the data shall be trended and retained in auditable form. A flux thimble tube shall not remain in service for more than two (2) operating fuel cycles without successful completion of eddy current testing for that thimble tube.

(d)

The Braidwood Unit 2 reactor head closure stud hole location No. 35 will be repaired no later than June 18, 2027, or before the end of the last refueling outage prior to the period of extended operation (whichever occurs later), so that all 54 reactor head closure studs are operable and tensioned during the period of extended operation.

(13)

Adoption of 10 CFR 50.69, Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants Exelon is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using:

Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2, Class 3, and non-Code class SSCs and their associated supports; and the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e.,

seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in the license amendment No. 198, dated October 22, 2018.

Exelon will complete the updated implementation items listed in of Exelon letter to NRC dated September 13, 2018, prior to implementation of 10 CFR 50.69. All issues identified in the attachment will be addressed and any associated changes will be made, focused scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2),

and any findings will be resolved and reflected in the PRA of record prior to implementation of the 10 CFR 50.69 categorization process.

Renewed License No. NPF-77 Amendment No. 208 Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment approach).

D.

An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1938, issued October 8, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

E.

The licensee shall implement and maintain in affect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, as supplemented and amended, and as approved in the SER dated November 1983 and its supplements, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission, only if these changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualifications, 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:

Braidwood Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3, submitted by letter dated May 17, 2006.

Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 168 and modified by License Amendment No. 185.

G.

Deleted H.

The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

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

Renewed License No. NPF-77 Amendment No. 208 I.

This renewed license is effective as of the date of issuance and shall expire at midnight on December 18, 2047. In addition, Amendment 187 shall be implemented by March 16, 2016, and Amendment 188 shall be implemented prior to MODE 4 following the Fall 2016 refueling outage (i.e., A1R19).

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William M. Dean, Director Office of Nuclear Reactor Regulation Appendices:

1.

Appendix A - Technical Specifications (NUREG-1276)

2.

Appendix B - Environmental Protection Plan

3.

Appendix C - Additional Conditions Date of Issuance: January 27, 2016

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 214 Renewed License No. NPF-37

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-37 is hereby amended by deleting paragraphs 2.C.(19), 2.C.(20), and 2.C.(21).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 214 Renewed License No. NPF-66

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-66 is hereby amended by deleting paragraphs 2.C.(8), 2.C.(9), and 2.C.(10).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 214 AND 214 RENEWED FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-37 License NPF-37 Page 5 Page 5 Page 6 Page 6 (pagination)

Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

Page 9 License NPF-66 License NPF-66 Page 4 Page 4 Page 5 Page 5 (pagination)

Page 6 Page 6 (pagination)

Page 7 Page 7 (pagination)

Page 8 Renewed License No. NPF-37 Amendment No. 214 (18)

Exelon Generation Company, LLC shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company, LLCs consolidated net utility plant, as recorded on Exelon Generation Company, LLCs books of account.

(19)

Deleted.

(20)

Deleted.

(21)

Deleted.

(22)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (23)

License Renewal License Conditions (a)

The information in the UFSAR supplement, submitted pursuant to 10 CFR 54.21(d), as revised during the license renewal application review process, and as supplemented by the Commitments applicable to Byron Unit 1 in Appendix A of the Renewed License No. NPF-37 Amendment No. 214 Safety Evaluation Report Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (SER) dated July 2015, is collectively the License Renewal UFSAR Supplement. This Supplement is henceforth part of the UFSAR which will be updated in accordance with 10 CFR 50.71(e). As such, the licensee may make changes to the programs and activities applicable to Byron Unit 1 described in this Supplement provided the licensee evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(b)

This License Renewal UFSAR Supplement, as revised per License Condition 23(a) above, describes certain programs to be implemented and activities to be completed prior to the period of extended operation.

1.

The licensee shall implement those new programs and enhancements to existing programs no later than April 30, 2024.

2.

The licensee shall complete those activities as noted in the Commitments applicable to Byron Unit 1 in this Supplement no later than April 30, 2024 or the end of the last refueling outage prior to the period of extended operation, whichever occurs later.

3.

The licensee shall notify the NRC in writing within 30 days after having accomplished item (b)1 above and include the status of those activities that have been or remain to be completed in item (b)2 above.

(24)

Adoption of 10 CFR 50.69, Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants Exelon is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using:

Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2, Class 3, and non-Code class SSCs and their associated supports; and the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e.,

seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in the license amendment No. 204, dated October 22, 2018.

Renewed License No. NPF-37 Amendment No. 214 Exelon will complete the updated implementation items listed in of Exelon letter to NRC dated September 13, 2018, prior to implementation of 10 CFR 50.69. All issues identified in the attachment will be addressed and any associated changes will be made, focused scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2),

and any findings will be resolved and reflected in the PRA of record prior to implementation of the 10 CFR 50.69 categorization process.

Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment approach).

D.

The facility requires no exemptions from the requirements of 10 CFR Part 50.

E.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualifications, 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:

Byron Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3, submitted by letter dated May 17, 2006.

Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 175 and modified by License Amendment No. 191.

F.

Deleted G.

The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan Renewed License No. NPF-37 Amendment No. 214 H.

This renewed license is effective as of the date of issuance and shall expire at midnight on October 31, 2044.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William M. Dean, Director Office of Nuclear Reactor Regulation Appendices:

1.

Appendix A - Technical Specifications (NUREG-1113)

2.

Appendix B - Environmental Protection Plan

3.

Appendix C - Additional Conditions Date of Issuance: November 19, 2015 Renewed License No. NPF-66 Amendment No. 214 (3)

Deleted.

(4)

Deleted.

(5)

Deleted.

(6)

Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 198, are hereby incorporated into this renewed license.

The licensee shall operate the facility in accordance with the Additional Conditions.

(7)

Exelon Generation Company, LLC, shall provide to the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC, to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Companys consolidated net utility plant, as recorded on Exelon Generation Company, LLCs books of account.

(8)

Deleted.

(9)

Deleted.

(10)

Deleted.

(11)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures Renewed License No. NPF-66 Amendment No. 214 (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (12)

License Renewal License Conditions (a)

The information in the UFSAR supplement, submitted pursuant to 10 CFR 54.21(d), as revised during the license renewal application review process, and as supplemented by the Commitments applicable to Byron Unit 2 in Appendix A of the Safety Evaluation Report Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (SER) dated July 2015, is collectively the License Renewal UFSAR Supplement. This Supplement is henceforth part of the UFSAR which will be updated in accordance with 10 CFR 50.71(e). As such, the licensee may make changes to the programs and activities applicable to Byron Unit 2 described in this Supplement provided the licensee evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(b)

This License Renewal UFSAR Supplement, as revised per License Condition 12(a) above, describes certain programs to be implemented and activities to be completed prior to the period of extended operation.

1.

The licensee shall implement those new programs and enhancements to existing programs no later than May 6, 2026.

2.

The licensee shall complete those activities as noted in the Commitments applicable to Byron Unit 2 in this Supplement no later than May 6, 2026, or the end of the last refueling outage prior to the period of extended operation, whichever occurs later.

3.

The licensee shall notify the NRC in writing within 30 days after having accomplished item (b)1 above and include the status of those activities that have been or remain to be completed in item (b)2 above.

(13)

Adoption of 10 CFR 50.69, Risk-informed categorization and treatment of structures, systems, and components for nuclear power plants Exelon is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using:

Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess Renewed License No. NPF-66 Amendment No. 214 shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2, Class 3, and non-Code class SSCs and their associated supports; and the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e.,

seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in the license amendment No. 204, dated October 22, 2018.

Exelon will complete the updated implementation items listed in of Exelon letter to NRC dated September 13, 2018, prior to implementation of 10 CFR 50.69. All issues identified in the attachment will be addressed and any associated changes will be made, focused scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2),

and any findings will be resolved and reflected in the PRA of record prior to implementation of the 10 CFR 50.69 categorization process.

Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment approach).

D.

The facility requires no exemptions from the requirements of 10 CFR Part 50.

An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1916, issued March 4, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Therefore, the licensee is exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

E.

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensees Fire Protection Report and the licensees letters dated September 23, 1986, October 23, 1986, November 3, 1986, December 12 and 15, 1986, and January 21, 1987, and as approved in the SER dated February 1982 through Supplement No. 8, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualifications, and safeguards contingency plans including amendments made Renewed License No. NPF-66 Amendment No. 214 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:

Byron Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 3, submitted by letter dated May 17, 2006.

Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 175 and modified by License Amendment No. 191.

G.

Deleted H.

The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I.

This renewed license is effective as of the date of issuance and shall expire at midnight on November 6, 2046.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William M. Dean, Director Office of Nuclear Reactor Regulation Attachments:

1.

Appendix A - Technical Specifications (NUREG-1113)

2.

Appendix B - Environmental Protection Plan

3.

Appendix C - Additional Conditions Date of Issuance: November 19, 2015 1 The training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 230 License No. NPF-62

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Facility Operating License No. NPF-62 is hereby amended by deleting paragraphs 2.C.(15) through 2.C.(20).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 230 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 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 5 Page 5 Page 6 Page 6 (pagination)

Page 7 Page 7 (pagination)

Page 7a Page 8 (pagination)

Page 8 Page 9 Amendment No. 230 License Transfer Conditions (10)

Deleted.

(11)

Deleted.

(12)

Deleted.

(13)

Deleted.

(14)

Deleted (15)

Deleted.

(16)

Deleted.

(17)

Deleted.

(18)

Deleted.

(19)

Deleted.

(20)

Deleted.

(21)

Deleted (22)

Mitigation Strategy License Condition The licensee shall develop and maintain strategies for addressing large fires and explosions and that include the follow key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures Amendment No. 230 (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (23)

Upon implementation of Amendment No. 178 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.3.5, in accordance with TS 5.5.15.c.(i), the assessment of CRE habitability as required by Specification 5.5.15.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.15.d, shall be considered met. Following implementation:

(a)

The first performance of SR 3.7.3.5, in accordance with Specification 5.5.15.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from November 16, 2004, the date of the most recent successful tracer gas test, as stated in the February 8, 2005 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b)

The first performance of the periodic assessment of CRE habitability, Specification 5.5.15.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from November 16, 2004, the date of the most recent successful tracer gas test, as stated in the February 8, 2005 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c)

The first performance of the periodic measurement of CRE pressure, Specification 5.5.15.d, shall be within 24 months, plus the 6 months allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 6 months if not performed previously.

(24)

At the time of the closing of the transfer of CPS and the respective license from AmerGen Energy Company, LLC (AmerGen) to Exelon Generation Company, AmerGen shall transfer to Exelon Generation Company ownership and control of AmerGen Clinton NQF, LLC, and AmerGen Consolidation, LLC shall be merged into Exelon Generation Consolidation, LLC. Also at the time of the closing, decommissioning funding assurance provided by Exelon Generation Company, using an additional method allowed under 10 CFR 50.75 if necessary, must be equal to or greater than the minimum amount calculated on that date pursuant to, and required by 10 CFR 50.75 for CPS. Furthermore, funds dedicated for CPS prior to closing shall remain dedicated to CPS following the closing. The name of AmerGen Clinton NQF, LLC shall be changed to Exelon Generation Clinton NQF, LLC at the time of the closing.

Amendment No. 230 (25)

Irradiated GE14i fuel bundles shall be stored at least four feet from the wall of the Spent Fuel Pool.

D.

The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include: (a) an exemption from the requirements of 10 CFR 70.24 for the criticality alarm monitors around the fuel storage area; (b) an exemption from the requirement of 10 CFR Part 50, Appendix J -

Option B, paragraph III.B, exempting the measured leakage rates from the main steam isolation valves from inclusion in the combined leak rate for local leak rate tests (Section 6.2.6 of SSER 6); and (c) an exemption from the requirements of paragraph III.B of Option B of 10 CFR Part 50, Appendix J, exempting leakage from the valve packing and the body-to-bonnet seal of valve 1E51-F374 associated with containment penetration 1MC-44 from inclusion in the combined leakage rate for penetrations and valves subject to Type B and C tests (SER supporting Amendment 62 to Facility Operating License No. NPF-62). The special circumstances regarding each exemption, except for item (a) above, are identified in the referenced section of the safety evaluation report and the supplements thereto.

An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC Material License No. SNM-1886, issued November 27, 1985, and relieved the licensee from the requirement of having a criticality alarm system. Exelon Generation Company is hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions in items (b) and (c) above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E.

Exelon Generation Company 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:

Clinton Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2, submitted by letter dated May 17, 2006.

Exelon Generation Company 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).

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

Amendment No. 230 The Exelon Generation Company CSP was approved by License Amendment No. 194 and modified by License Amendment No. 206.

F.

Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report as amended, for the Clinton Power Station, Unit No. 1, and as approved in the Safety Evaluation Report (NUREG-0853) dated February 1982 and Supplement Nos. 1 thru 8 thereto subject to the following provision:

Exelon Generation Company may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G.

Deleted.

H.

Exelon Generation Company shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

I.

This license is effective as of the date of issuance and shall expire at midnight on April 17, 2027.

FOR THE NUCLEAR REGULATORY COMMISSION Original signed by:

Thomas E. Murley, Director Office of Nuclear Reactor Regulation

Enclosures:

1.

Attachments 1 (Deleted) and 2

2.

Appendix A - Technical Specifications (NUREG-1235)

3.

Appendix B - Environmental Protection Plan

4.

Appendix C - Deleted Date of Issuance: April 17, 1987

EXELON GENERATION COMPANY, LLC DOCKET NO.50-010 DRESDEN NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-2

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Facility Operating License No. DPR-2 is hereby amended by deleting paragraphs 2.C.(8), 2.C.(9), and 2.C.(10).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Bruce A. Watson, Chief Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery, and Waste Programs Office of Nuclear Material Safety and Safeguards

Attachment:

Changes to the Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. DPR-2 DRESDEN NUCLEAR POWER STATION, UNIT 1 DOCKET NO.50-010 Replace the following page of the Facility Operating License with the attached revised page.

The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert License DPR-2 License DPR-2 Page 4 Page 4 Amendment No. 48 (8)

Deleted.

(9)

Deleted.

(10)

Deleted.

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 267 Renewed License No. DPR-19

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. DPR-19 is hereby amended by deleting paragraphs 2.C.(11), 2.C.(12), and 2.C.(13).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 260 Renewed License No. DPR-25

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. DPR-25 is hereby amended by deleting paragraphs 3.S, 3.T, and 3.U.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 267 AND 260 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 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 5 Page 5 Page 6 Page 6 Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

Page 9 Page 9 (pagination)

Page 9A License DPR-25 License DPR-25 Page 7 Page 7 Page 8 Page 8 (pagination)

Renewed License No. DPR-19 Amendment No. 267 (7)

Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 191, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Additional Conditions.

(8)

Deleted (9)

Deleted (10)

Exelon Generation Company, LLC shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company, LLC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Company, LLCs consolidated net utility plant, as recorded on Exelon Generation Company, LLCs books of account.

(11)

Deleted.

(12)

Deleted.

(13)

Deleted.

(14)

Exelon Generation Company, LLC shall relocate certain Technical Specification requirements to EGG-controlled documents upon implementation of the Amendment No. 185. The items and appropriate documents are as described in Table LA, Removal of Details Matrix, and Table R, Relocated Specifications, that are attached to the NRCs Safety Evaluation enclosed with Amendment No. 185.

Renewed License No. DPR-19 Amendment No. 267 (15)

The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 185 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of Amendment No. 185.

For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of Amendment No. 185.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of Amendment No. 185.

For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of Amendment No. 185.

(16)

Following implementation of Amendment No. 185, the reactor protection system trip setpoint for main steam isolation valve closure shall be maintained at the previous setpoint (less than or equal to 10% closed) until startup after the first outage of sufficient duration to change the setpoint.

(17)

The license is amended to authorize changing the UFSAR to allow credit for containment overpressure as detailed below, to assure adequate Net Positive Suction Head is available for low pressure Emergency Core Cooling System pumps following a design-basis accident.

From (sec)

Accident start To (sec) 290 Credit (psig) 9.5 290 5,000 4.8 5,000 30,000 6.6 30,000 40,000 6.0 40,000 45,500 5.4 45,500 52,500 4.9 52,500 60,500 4.4 60,500 70,000 3.8 70,000 84,000 3.2 84,000 104,000 2.5 104,000 136,000 1.8 136,000 Accident end 1.1 Renewed License No. DPR-19 Amendment No. 267 (18)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (19)

The licensee shall implement and maintain all Actions required by to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

Renewed License No. DPR-19 Amendment No. 267 (20)

Upon implementation of Amendment No. 226 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.4.4, in accordance with TS 5.5.14.c.(i), the assessment of CRE habitability as required by Specification 5.5.14.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.14.d, shall be considered met. Following implementation:

(a)

The first performance of SR 3.7.4.4, in accordance with Specification 5.5.14.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from January 1997, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b)

The first performance of the periodic assessment of CRE habitability, Specification 5.5.14.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from January 1997, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c)

The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d, shall be within 24 months, plus the 6 months allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 6 months if not performed previously.

(21)

Upon implementation of Amendment No. 249 the licensee shall adhere to the following requirements as part of the DNPS unit 2 spent fuel pool coupon surveillance program to ensure that the B-10 areal density of the BORAL remains at or above its minimum credited value and that the regulatory requirement to maintain the Technical Specification value of keff 0.95 continues to be met:

1.

Ensure that coupon measurements of B-10 areal density are performed by a qualified laboratory;

2.

Ensure that the coupons are removed for evaluation every 10 years;

3.

Ensure that should any coupon be identified as failing the minimum certified B-10 areal density criterion based on coupon test results, EGC will perform in-situ testing to confirm that the minimum B-10 areal density (0.02 g/cm2) is met for the BORAL panels installed in the DNPS spent fuel pools; and, Renewed License No. DPR-19 Amendment No. 267

4.

Submit a report to the NRC within 90 days following the completion of evaluations associated with Item 3 above. The report shall include; a description of the testing results, the assessments performed, and the interim and long-term corrective actions for abnormal indications.

D.

The facility has been granted certain exemptions from the requirements of Section III.G of Appendix R to 10 CFR Part 50, Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979. This section relates to fire protection features for ensuring the systems and associated circuits used to achieve and maintain safe shutdown are free of fire damage. These exemptions were granted and sent to the licensee in letters dated February 2, 1983, September 28, 1987, July 6, 1989, and August 15, 1989.

In addition, the facility has been granted certain exemptions from Sections II and III of Appendix J to 10 CFR Part 50, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors. This section contains leakage test requirements, schedules and acceptance criteria for tests of the leak-tight integrity of the primary reactor containment and systems and components which penetrate the containment. These exemptions were granted and sent to the licensee in a letter dated June 25, 1982.

These exemptions granted pursuant to 10 CFR 50.12 are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E.

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated March 22, 1978 with supplements dated December 2, 1980, and February 12, 1981; January 19, 1983; July 17, 1987; September 28, 1987; and January 5, 1989, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

F.

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.

Renewed License No. DPR-25 Amendment No. 260 S.

Deleted.

T.

Deleted.

U.

Deleted.

V.

Exelon Generation Company, LLC shall relocate certain Technical Specification requirements to EGC-controlled documents upon implementation of the Amendment No. 180. The items and appropriate documents are as described in Table LA, Removal of Details Matrix, and Table R, Relocated Specifications, that are attached to the NRCs Safety Evaluation enclosed with Amendment No. 180.

W.

The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 180 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of Amendment No. 180.

For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of Amendment No. 180.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of Amendment No. 180.

For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of Amendment No. 180.

Renewed License No. DPR-25 Amendment No. 260 X.

The license is amended to authorize changing the UFSAR to allow credit for containment over pressure as detailed below, to assure adequate Net Positive Suction Head is available for low pressure Emergency Core Cooling System pumps following a design-basis accident.

From (sec)

Accident start To (sec) 290 Credit (psig) 9.5 290 5,000 4.8 5,000 30,000 6.6 30,000 40,000 6.0 40,000 45,500 5.4 45,500 52,500 4.9 52,500 60,500 4.4 60,500 70,000 3.8 70,000 84,000 3.2 84,000 104,000 2.5 104,000 136,000 1.8 136,000 Accident end 1.1

0 EXELON FITZPATRICK, LLC AND EXELON GENERATION COMPANY, LLC DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 334 Renewed License No. DPR-59

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. DPR-59 is hereby amended by deleting paragraphs 2.P and 2.Q.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 334 RENEWED FACILITY OPERATING LICENSE NO. DPR-59 JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert License DPR-59 License DPR-59 Page 7 Page 7 Amendment 334 Renewed License No. DPR-59 N.

DELETED O.

DELETED P.

DELETED Q.

DELETED R.

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders

1 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 Renewed License No. NPF-11

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-11 is hereby amended by deleting paragraphs 2.C.(39), 2.C.(40), and 2.C.(41).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

2 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 229 Renewed License No. NPF-18

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-18 is hereby amended by deleting paragraphs 2.C.(23), 2.C.(24), and 2.C.(25).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 243 AND 229 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 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 7 Page 7 License NPF-18 License NPF-18 Page 6 Page 6 Page 7 Page 7 Page 8 Page 8 (pagination)

Renewed License No. NPF-11 Amendment No. 243 (39)

Deleted.

(40)

Deleted.

(41)

Deleted.

(42)

DELETED Am. 243 04/06/20 Am. 243 04/06/20 Am. 243 04/06/20

Renewed License No. NPF-18 Amendment No. 229 (20)

DELETED (21)

Deleted.

(22)

EGC shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from EGC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of EGCs consolidated net utility plant, as recorded on EGCs books of account.

(23)

Deleted.

(24)

Deleted.

(25)

Deleted.

(26)

DELETED (27)

DELETED Am. 133 03/30/01 Am. 132 01/12/01 Am. 229 04/06/20 Am. 229 04/06/20 Am. 229 04/06/20

Renewed License No. NPF-18 Amendment No. 229 (28)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordination fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training or integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders Letter dated 08/09/07

Renewed License No. NPF-18 Amendment No. 229 (29)

Upon implementation of Amendment No. 173 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.4.5, in accordance with TS 5.5.15.c.(i), the assessment of CRE habitability as required by Specification 5.5.15.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.15.d, shall be considered met. Following implementation:

(a)

The first performance of SR 3.7.4.5, in accordance with Specification 5.5.15.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from 1998, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b)

The first performance of the periodic assessment of CRE habitability, Specification 5.5.15.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from 1998, the date of the most recent successful tracer gas test, as stated in the December 9, 2003 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c)

The first performance of the periodic measurement of CRE pressure, Specification 5.5.15.d, shall be within 24 months, plus the 6 months allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test, or within 6 months if not performed previously.

(30)

DELETED (31)

DELETED (32)

DELETED Am. 173 10/31/07 Am. 194 10/31/13 Am. 194 10/31/13 Am. 194 10/31/13

3 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 244 Renewed License No. NPF-39

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-39 is hereby amended by deleting paragraphs 2.C.(18), 2.C.(19), and 2.C.(20).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

4 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 207 Renewed License No. NPF-85

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-85 is hereby amended by deleting paragraphs 2.C.(6), 2.C.(7), and 2.C.(8).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 244 AND 207 RENEWED FACILITY OPERATING LICENSE NOS. NPF-39 AND NPF-85 LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-39 License NPF-39 Page 5 Page 5 Page 6 Page 6 License NPF-85 License NPF-85 Page 5 Page 5 Page 6 Page 6 Renewed License No. NPF-39 Amendment No. 244 (16)

Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 230, are hereby incorporated into this renewed license. Exelon Generation Company shall operate the facility in accordance with the Additional Conditions.

(17)

Exelon Generation Company shall provide to the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of Exelon Generation Companys consolidated net utility plant, as recorded on Exelon Generation Company's books of account.

(18)

Deleted.

(19)

Deleted.

(20)

Deleted.

Renewed License No. NPF-39 Amendment No. 244 (21)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders Renewed License No. NPF-85 Amendment No. 207 (6)

Deleted.

(7)

Deleted.

(8)

Deleted.

Renewed License No. NPF-85 Amendment No. 207 (9)

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (10)

The licensee shall implement and maintain all Actions required by to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

5 NINE MILE POINT NUCLEAR STATION, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 242 Renewed License No. DPR-63

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. DPR-63 is hereby amended by deleting paragraphs 2.D.(9) through 2.D.(12).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

6 NINE MILE POINT NUCLEAR STATION, LLC LONG ISLAND LIGHTING COMPANY EXELON GENERATION COMPANY, LLC DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 180 Renewed License No. NPF-69

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. NPF-69 is hereby amended by deleting paragraphs 2.C.(12) through 2.C.(15).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 242 AND 180 RENEWED FACILITY OPERATING LICENSE NOS. DPR-63 AND NPF-69 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-220 AND 50-410 Replace the following pages of the Renewed Facility Operating Licenses 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-63 License DPR-63 Page 8 Page 8 Page 9 Page 9 Page 10 Page 10 (pagination)

License NPF-69 License NPF-69 Page 6 Page 6 Page 7 Page 7 Page 8 Page 8 Page 9 Page 9 (pagination)

Renewed License No. DPR-63 Amendment No. 214, 242 (b)

NMP LLC shall restore the facility to a condition consistent with the FSAR or provide a change to the FSAR criteria for staff review and approval prior to restart from the forthcoming Cycle 8 outage.

(9)

Deleted.

(10)

Deleted.

(11)

Deleted.

(12)

Deleted.

Renewed License No. DPR-63 Revised by letter dated August 23, 2007 Amendment No. 214, 242 (13)

Mitigation Strategy License Condition Exelon Generation shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

a.

Fire fighting response strategy with the following elements:

(1) Pre-defined coordinated fire response strategy and guidance (2) Assessment of mutual aid fire fighting assets (3) Designated staging areas for equipment and materials (4) Command and control (5) Training of response personnel

b.

Operations to mitigate fuel damage considering the following:

(1) Protection and use of personnel assets (2) Communications (3) Minimizing fire spread (4) Procedures for implementing integrated fire response strategy (5) Identification of readily-available pre-staged equipment (6) Training on integrated fire response strategy (7) Spent fuel pool mitigation measures

c.

Actions to minimize release to include consideration of:

(1) Water spray scrubbing (2) Dose to onsite responders (14)

Exelon Generation shall implement and maintain all Actions required by to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

Renewed License No. DPR-63 Revised by letter dated August 23, 2007 Amendment No. 195, 214 215, 242 (15)

Upon implementation of Amendment No. 195 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by TS 4.4.5.g, in accordance with TS 6.5.8.c.(i), the assessment of CRE habitability as required by Specification 6.5.8.c.(ii), and the measurement of CRE pressure as required by Specification 6.5.8.d, shall be considered met. Following implementation:

(a)

The first performance of TS 4.4.5.g, in accordance with Specification 6.5.8.c.(i), shall be within the specified Frequency of 6 years plus the 18-month allowance of TS 4.0.2, as measured from February 19, 2004, the date of the most recent tracer gas test, as stated in the January 31, 2005 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent tracer gas test is greater than 6 years.

(b)

The first performance of the periodic assessment of CRE habitability, Specification 6.5.8.c.(ii), shall be within 3 years, plus the 9-month allowance of TS 4.0.2, as measured from February 19, 2004, the date of the most recent tracer gas test, as stated in the January 31, 2005 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent tracer gas test is greater than 3 years.

(c)

The first performance of the periodic measurement of CRE pressure, Specification 6.5.8.d, shall be within 24 months, plus the 182 days allowed by TS 4.0.2, as measured from March 1, 2007, the date of the most recent successful pressure measurement test, or within the next 182 days if not performed previously.

(16)

The existing E.D.F. International S.A.S. Support Agreement of approximately $145 million, dated November 6, 2009, may not be amended or modified without 30 days prior written notice to the Director of the Office of Nuclear Reactor Regulation or his designee. Nine Mile Point Nuclear Station, LLC, CENG or Exelon Generation shall not take any action to cause E.D.F. International S.A.S., or its successors and assigns, to void, cancel, or materially modify the E.D.F. International S.A.S. Support Agreement or cause it to fail to perform, or impair its performance under the E.D.F. International S.A.S. Support Agreement, without the prior written consent of the NRC. Exelon Generation shall inform the NRC in writing no later than 14 days after any funds are provided to or for the CENG subsidiary licensee under the E.D.F.

International S.A.S. Support Agreement.

Renewed License No. NPF-69 Amendment 124, 180 (10)

Additional Condition 1 The operating licensee is authorized by Amendment No. 91 to relocate certain Technical Specification requirements previously included in Appendix A to licensee-controlled documents, as described in Table R, Relocated Specifications and Removal of Details Matrix, attached to the NRC Staffs safety evaluation dated February 15, 2000, enclosed with the amendment. Implementation of Amendment No. 91 shall include the relocation of these requirements to the appropriate documents, which shall be completed no later than December 31, 2000. The relocations to the Updated Safety Analysis Report shall be reflected in updates completed in accordance with 10 CFR 50.71(e).

(11)

Additional Condition 2 The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 91 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.

For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to the implementation of this amendment.

(11a) Deleted (12)

Deleted.

Renewed License No. NPF-69 Amendment No. 180 (13)

Deleted.

(14)

Deleted.

(15)

Deleted.

Renewed License No. NPF-69 Revised by letter dated August 23, 2007 Amendment No. 180 (16)

Reactor Vessel Integrated Surveillance Program NMP LLC is authorized to revise the Updated Safety Analysis Report (USAR) to allow implementation of the Boiling Water Reactor Vessel and Internals Project reactor pressure vessel Integrated Surveillance Program as the basis for demonstrating compliance with the requirements of Appendix H to Title 10 of the Code of Federal Regulations, Part 50, Reactor Vessel Material Surveillance Program Requirements, as set forth in the licensees application dated January 9, 2004, and as supplemented on June 17, 2004.

(17)

Mitigation Strategy License Condition The operating licensee shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

a. Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel

b. Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated, fire response strategy.

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures

c. Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders Renewed License No. NPF-69 Revised by letter dated August 23, 2007 Amendment No. 126, 180 (18)

The operating licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(19)

Upon implementation of Amendment No. 126 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.2.4, in accordance with TS 5.5.13.c.(i), the assessment of CRE habitability as required by Specification 5.5.13.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.13.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.2.4, in accordance with Specification 5.5.13.c.(i), shall be within the specified Frequency of 6 years plus the 18-month allowance of SR 3.0.2, as measured from August 20, 2004, the date of the most recent tracer gas test, or within the next 18 months if the time period since the most recent tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.13.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from August 20, 2004, the date of the most recent tracer gas test, or within the next 9 months if the time period since the most recent tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.13.d, shall be within 24 months, plus the 182 days allowed by SR 3.0.2, as measured from March 6, 2006, the date of the most recent successful pressure measurement test, or within the next 182 days if not performed previously.

7 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-171 PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 16 License No. DPR-12

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Facility Operating License No. DPR-12 is hereby amended by deleting paragraphs 2.C.(5) and 2.C.(6).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Bruce A. Watson, Chief Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery, and Waste Programs Office of Nuclear Material Safety and Safeguards

Attachment:

Changes to the Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 16 FACILITY OPERATING LICENSE NO. DPR-12 PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 DOCKET NO. 50-171 Replace the following page of the Facility Operating License with the attached revised page.

The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert License DPR-12 License DPR-12 Page 3 (unnumbered)

Page 3 (unnumbered)

Amendment No. 16 (5)

Deleted.

(6)

Deleted.

8 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 333 Subsequent Renewed License No. DPR-44

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Subsequent Renewed Facility Operating License No. DPR-44 is hereby amended by deleting paragraphs 2.C.(5)(a), 2.C.(5)(b), 2.C.(7), 2.C.(8), and 2.C.(9).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Subsequent Renewed Facility Operating License Date of Issuance: April 6, 2020

9 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 336 Subsequent Renewed License No. DPR-56

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Subsequent Renewed Facility Operating License No. DPR-56 is hereby amended by deleting paragraphs 2.C.(5)(a), 2.C.(5)(b), 2.C.(7), 2.C.(8), and 2.C.(9).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Subsequent Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 333 AND 336 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NOS. DPR-44 AND DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-277 AND 50-278 Replace the following pages of the Subsequent Renewed Facility Operating Licenses 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 4 Page 4 Page 5 Page 5 Page 6 Page 6 (pagination)

Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

Page 9 Page 9 (pagination)

Page 10 Page 10 (pagination)

Page 11 Page 11 (pagination)

Page 12 Page 12 (pagination)

Page 13 Page 13 (pagination)

Page 14 Page 14 (pagination)

Page 15 Page 15 (pagination)

Page 16 Page 17 License DPR-56 License DPR-56 Page 4 Page 4 Page 5 Page 5 Page 6 Page 6 (pagination)

Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

Page 9 Page 9 (pagination)

Page 10 Page 10 (pagination)

Page 11 Page 11 (pagination)

Page 12 Page 12 (pagination)

Page 13 Page 13 (pagination)

Page 14 Page 14 (pagination)

Page 15 Page 15 (pagination)

Page 16

Page 4 Subsequent Renewed License No. DPR-44 Amendment No. 333 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1, submitted by letter dated May 17, 2006, is entitled:

"Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 281 and modified by Amendment No. 301.

(4)

Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report (SER) dated May 23, 1979, and Supplements dated August 14, September 15, October 10 and November 24, 1980, and in the NRC SERs dated September 16, 1993, and August 24, 1994, subject to the following provision:

The Exelon Generation Company may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(5)

Public Service Electric & Gas Company (PSE&G) to PSEG Nuclear License Transfer Conditions (a)

Deleted.

(b)

Deleted.

(c)

PSEG Nuclear shall not take any action that would cause PSEG Power LLC or its parent companies to void, cancel, or diminish the commitment to fund an extended plant shutdown as represented in the application for approval of the transfer of this license from PSE&G to PSEG Nuclear.

(6)

Exelon Generation Company shall provide to the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Page 5 Subsequent Renewed License No. DPR-44 Amendment No. 333 (10%) of Exelon Generation Company's consolidated net utility plant, as recorded on Exelon Generation Company's books of account.

(7)

Deleted.

(8)

Deleted.

(9)

Deleted.

(10) Additional Conditions of the Renewed License (a)

Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement, as revised on January 31, 2003, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following the issuance of the renewed license. Until that update is complete, the Exelon Generation Company may make changes to the programs described in the supplement without prior Commission approval, provided that the Exelon Generation Company evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(b)

Future Inspection Activities The Exelon Generation Company Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on January 31, 2003, describes certain future inspection activities to be completed before the period of extended operation.

The Exelon Generation Company shall complete these activities no later than August 8, 2013, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(c)

Integrated Surveillance Program The Exelon Generation Company shall implement an NRC staff-approved reactor vessel integrated surveillance program for the extended period of operation which satisfies the requirements of 10 CFR Part 54. Such a program will be implemented through a staff-approved Boiling Water Reactor Vessel and Internals Project program or through a staff-approved plant-specific program. Before August 8, 2013, the licensee will notify the NRC of its decision to implement the integrated surveillance program or a plant-specific program, and provide the appropriate revisions to the Updated Final Safety Analysis Report Supplement summary descriptions of the vessel surveillance material testing program.

Page 6 Subsequent Renewed License No. DPR-44 Amendment No. 333 (d)

Core Shroud Inspection and Evaluation Guidelines Program The Exelon Generation Company shall implement an NRC staff-approved core shroud inspection and evaluation guidelines program for the extended period of operation which satisfies the requirements of 10 CFR Part 54. Such a program will be implemented through a staff-approved Boiling Water Reactor Vessel and Internals Project program or through a staff-approved plant-specific program. Before August 8, 2013, the licensee will notify the NRC of its decision to implement the core shroud inspection and evaluation guidelines program or a plant-specific program and provide the appropriate revisions to the Updated Final Safety Analysis Report Supplement summary descriptions of the core shroud inspection and evaluation guidelines program.

(11) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (12) The licensee shall implement and maintain all Actions required by to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(13) Deleted

Page 7 Subsequent Renewed License No. DPR-44 Amendment No. 333 (14) Spent Fuel Pool Criticality Considerations (a)

Use of spent fuel pool storage cells without NETCO-SNAP-IN rack inserts shall be restricted as follows:

1)

Minimum panel Boron-10 areal density of a storage cell shall be greater than or equal to 0.014 grams per square centimeter to store fuel assemblies with the maximum in-core cold k-infinity of up to 1.235. The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

2)

A storage cell shall not contain any fuel assembly if the minimum panel Boron-10 areal density of a storage cell is less than 0.014 grams per square centimeter. The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

(b)

Until the installation of NETCO-SNAP-IN rack inserts are completed in the Peach Bottom Unit 2 spent fuel pool, Boraflex degradation shall be monitored analytically every 6 months.

(c)

Boraflex degradation shall be monitored by in-situ testing in the Peach Bottom Unit 2 spent fuel pool no later than December 31, 2014, unless installation of the NETCO-SNAP-IN rack inserts for Unit 2 have been completed prior to this date.

(d)

Installation of NETCO-SNAP-IN rack inserts shall be completed by December 31, 2016.

(15) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.C(1) of Renewed Facility Operating License No. DPR-44, for Peach Bottom Unit 2, to reflect the new maximum licensed reactor core power level of 3951 megawatts thermal (MWt), the license is also amended to add the following license condition. This license condition provides for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer). This license condition is applicable to the initial power ascension from 3514 MWt to the extended power uprate (EPU) power level of 3951 MWt:

(a)

The following requirements are placed on the initial operation of the facility, above the thermal power level of 3514 MWt, for the power ascension to 3951 MWt. These conditions are applicable until the first time full EPU conditions (3951 MWt) are achieved. If the number of active main steam line (MSL) strain gauges is less than two strain

Page 8 Subsequent Renewed License No. DPR-44 Amendment No. 333 gauges (180 degrees apart) at any of the eight MSL locations, Exelon Generation Company will stop power ascension and repair/replace the damaged strain gauges and only then resume power ascension.

In addition, sufficient on-dryer strain gauges must remain in working order to monitor all dryer peak stress locations with a minimum alternating stress ratio (MASR) less than 1.5. In the event there are no working on-dryer strain gauges, with coherence of greater than 0.5 with any peak stress location, Exelon Generation Company will:

(1) stop power ascension; (2) evaluate the dryer MASR at the current power level and at the projected EPU power level; and (3) provide the results to the NRC Project Manager via e-mail. Exelon Generation Company shall not resume power ascension for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the NRC Project Manager confirms receipt of the MASR results unless, prior to the expiration of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension. Furthermore, power ascension may only resume if Exelon Generation Company determines that the dryer MASR will remain greater than 1.0.

1.

Exelon Generation Company shall provide a brief stress summary report for the replacement steam dryer (RSD) based on MSL strain gauge and on-dryer instrument data collected at or near 3514 MWt for NRC review before increasing power above 3514 MWt. Exelon Generation Company shall also provide a brief vibration summary report for piping and valve vibration data collected at or near 3514 MWt for NRC review before increasing power above 3514 MWt. Both summary reports shall be provided by e-mail to the NRC Project Manager. Exelon Generation Company shall not increase power above 3514 MWt for at least 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> after the NRC Project Manager confirms receipt of the reports unless, prior to expiration of the 240 hour0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension. The stress summary report shall include the information in items a through f, and the vibration summary report shall include the information in items g through i, as follows:

a.

A comparison of predicted and measured pressure spectra plots on the RSD.

b.

A comparison of predicted and measured root mean square (RMS) strains and spectra plots on the RSD.

c.

End-to-end bias errors and uncertainties (B/Us) for RSD strains, along with a demonstration that the application of these B/Us leads to RSD strain simulations that bound the measured spectra at dominant frequencies and RMS strains at all active strain gauge locations.

Page 9 Subsequent Renewed License No. DPR-44 Amendment No. 333

d.

RSD strain gauge limits based on benchmarking performed near 3514 MWt. This will include the predicted RSD strains at each measured location and the corresponding updated MASR near 3514 MWt.

e.

Predicted (extrapolated) strains at the active RSD strain gauge locations at 104% of 3514 MWt and an evaluation against acceptance limits.

f.

Predicted RSD stresses and MASRs at EPU.

g.

Vibration data for piping and valve locations deemed prone to vibration and vibration monitoring locations identified in 3 to the EPU application dated September 28, 2012, and Supplement 16 dated December 20, 2013, including the following locations: MSLs (including those in the drywell, turbine building and in the steam tunnel), Feedwater Lines (including those in the drywell and turbine building), Safety Relief Valves (SRVs) and Main Steam Isolation Valves in the drywell.

h.

An evaluation of the measured vibration data collected in item 1.g above compared against acceptance limits.

i.

Predicted vibration values and associated acceptance limits at approximately 104 percent, 108 percent, and 112.4 percent of 3514 MWt using the data collected in item 1.g above.

2.

Exelon Generation Company shall monitor the RSD strain gauges during power ascension above 3514 MWt for increasing strain fluctuations. Upon the initial increase of power above 3514 MWt until reaching 3951 MWt, Exelon Generation Company shall collect data from the RSD strain gauges at nominal 2 percent thermal power increments and evaluate steam dryer stress ratios based on these data.

Summaries of the results shall be provided via e-mail to the NRC Project Manager at approximately 104 percent and 108 percent of 3514 MWt.

3.

Exelon Generation Company shall monitor the MSL strain gauges during power ascension above 3514 MWt for increasing pressure fluctuations in the main steam lines. Upon the initial increase of power above 3514 MWt until reaching 3951 MWt, Exelon Generation Company shall collect data from the MSL strain gauges and on-dryer instruments at nominal 2 percent thermal power increments.

Page 10 Subsequent Renewed License No. DPR-44 Amendment No. 333

4.

Exelon Generation Company shall hold the facility at approximately 104 percent and 108 percent of 3514 MWt to perform the following:

a.

Collect strain data from the MSL strain gauges and collect data from on-dryer instruments (accelerometers, strain gauges, and pressure transducers).

b.

Collect vibration data for the locations included in the vibration summary report discussed above.

c.

Evaluate steam dryer performance based on RSD strain gauge data.

d.

Evaluate the measured vibration data (collected in item 4.b above) at that power level, data projected to EPU conditions, trends, and comparison with the acceptance limits.

e.

Provide the steam dryer evaluation and the vibration evaluation, including the data collected, via e-mail to the NRC Project Manager, upon completion of the evaluation for each of the two hold points.

f.

Exelon Generation Company shall submit a comparison of predicted and measured pressures and strains (RMS and spectra) on the RSD at 104% of 3514 MWt and 108% of 3514 MWt during power ascension.

g.

Exelon Generation Company shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the evaluations unless, prior to the expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension.

5.

If any RMS level measured by the active RSD strain gauges exceeds allowable Level 1 limits, Exelon Generation Company shall return the facility to a power level at which the limit(s) is not exceeded. Exelon Generation Company shall resolve the discrepancy, evaluate and document the continued structural integrity of the steam dryer, and provide that documentation to the NRC Project Manager via e-mail prior to further increases in reactor power. If a revised stress analysis is performed and new RSD strain limits are developed, then Exelon Generation Company shall not further increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the documentation or until the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension, whichever comes first. Additional detail is provided in paragraph (b)1 below.

Page 11 Subsequent Renewed License No. DPR-44 Amendment No. 333 (b)

Exelon Generation Company shall implement the following actions for the initial power ascension from 3514 MWt to 3951 MWt condition:

1.

In the event that RMS strain levels for active RSD strain gauges are identified to exceed the allowable Level 1 limits during power ascension above 3514 MWt, Exelon Generation Company shall re-evaluate dryer loads and stresses, and re-establish updated MASRs and RSD strain gauge RMS limits. In the event that stress analyses are re-performed based on new strain gauge data to address paragraph (a)5 above, the revised load definition, stress analysis, and limits shall include:

a.

Determination of end-to-end B/Us and their application in determining maximum alternating stress intensities.

b.

Use of bump-up factors associated with all of the SRV acoustic resonances, as determined from the scale model test results or in-plant data acquired during power ascension.

2.

After reaching 3951 MWt, Exelon Generation Company shall obtain measurements from the MSL strain gauges and establish the steam dryer flow-induced vibration load fatigue margin for the facility, update the dryer stress report, and re-establish the RSD strain gauge limits based on the updated load definition. These data will be provided to the NRC staff as described below in paragraph (e).

(c)

Exelon Generation Company shall prepare the EPU power ascension test procedure to include:

1.

The stress limits and the corresponding RSD strain limits to be applied for evaluating steam dryer performance.

2.

Specific hold points and their durations during EPU power ascension.

3.

Activities to be accomplished during the hold points.

4.

Plant parameters to be monitored.

5.

Inspections and walkdowns to be conducted for steam, feedwater, and condensate systems and components during the hold points.

6.

Methods to be used to trend plant parameters.

7.

Acceptance criteria for monitoring and trending plant parameters, and conducting the walkdowns and inspections.

Page 12 Subsequent Renewed License No. DPR-44 Amendment No. 333

8.

Actions to be taken if acceptance criteria are not satisfied.

9.

Verification of the completion of commitments and planned actions specified in the application and all supplements to the application in support of the EPU license amendment request pertaining to the steam dryer prior to power increase above 3514 MWt. Exelon Generation Company shall provide the related EPU startup test procedure sections to the NRC Project Manager via e-mail prior to increasing power above 3514 MWt.

(d)

The following key attributes of the program for verifying the continued structural integrity of the steam dryer shall not be made less restrictive without prior NRC approval:

1.

During initial power ascension testing above 3514 MWt, each of the two hold points shall be at increments of 4 percent of 3514 MWt.

2.

Level 1 performance criteria.

3.

The methodology for establishing the RSD strain limits used for the Level 1 and Level 2 performance.

(e)

The results of the power ascension testing to verify the continued structural integrity of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall include a final load definition and stress report of the steam dryer, including the results of a complete re-analysis using the end-to-end B/Us determined at EPU conditions and a comparison of predicted and measured pressures and strains (RMS levels and spectra) on the RSD. The report shall be submitted within 90 days of the completion of EPU power ascension testing for Peach Bottom Unit 2.

(f)

During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be conducted of the steam dryer as described in the inspection guidelines contained in WCAP-17635-P.

(g)

The results of the visual inspections of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.

(h)

Within 6 months following completion of the second refueling outage, after the implementation of the EPU, the licensee shall submit a long-term steam dryer inspection plan based on industry operating experience along with the baseline inspection results.

The license condition described above shall expire: (1) upon satisfaction of the requirements in paragraphs (f) and (g), provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw(s) or

Page 13 Subsequent Renewed License No. DPR-44 Amendment No. 333 unacceptable flaw growth that is due to fatigue, and; (2) upon satisfaction of the requirements specified in paragraph (h).

(16) Maximum Extended Load Line Limit Analysis Plus (MELLLA+) Special Consideration The licensee shall not operate the facility within the MELLLA+ operating domain with a feedwater heater out of service resulting in more than a 10°F reduction in feedwater temperature below the design feedwater temperature.

(17) Adoption of 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants In support of implementing License Amendment No. 321 permitting the adoption of the provisions of 10 CFR 50.69 for Renewed Facility Operating License No. DPR-44 for Peach Bottom Unit 2, the license is amended to add the following license condition:

(a)

Exelon is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using: Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (ANO-2) passive categorization method to assess passive component risk for Class 2 and Class 3 SSCs and their associated supports; and the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e., seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in Unit 2 License Amendment No. 321 dated October 25, 2018.

Exelon will complete the implementation items listed in Attachment 2 of Exelon's letter to the NRC dated June 6, 2018, prior to implementation of 10 CFR 50.69. All issues identified in the attachment will be addressed and any associated changes will be made, focused-scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2), and any findings will be resolved and reflected in the PRA of record prior to implementation of the 10 CFR 50.69 categorization process.

Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment approach).

Page 14 Subsequent Renewed License No. DPR-44 Amendment No. 333 (18) This subsequent renewed license is subject to the following conditions for the protection of the environment:

(a)

To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Power Station Unit No. 2 will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended. Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Permit issuing or enforcement authority, as appropriate.

(b)

In the event of any modification of the NPDES Permit related to thermal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to Section 316 of the Federal Water Pollution Control Act, the Exelon Generation Company shall inform the NRC and analyze any associated changes in or to the Station, its components, its operation or in the discharge of effluents therefrom. If such change would entail any modification to this license, or any Technical Specifications which are part of this license, or require NRC approval pursuant to 10 CFR 50.59 or involve an environmental impact different than analyzed in the Final Environmental Statement, the Exelon Generation Company shall file with the NRC, as applicable, an appropriate analysis of any such change on facility safety, and/or an analysis of any such change on the environmental impacts and on the overall cost-benefit balance for facility operation set forth in the Final Environmental Statement and a request for an amendment to the operating license, if required by the Commission's regulations. As used in this Condition (18)(b), Final Environmental Statement (FES) means the NRC Staff Final Environmental Statement related to Operation of Peach Bottom Atomic Power Station Units Nos. 2 and 3 dated April 1973, as modified by (1) the Initial Decision of the Atomic Safety and Licensing Board dated September 14, 1973, (2) the Supplemental Initial Decision of the Atomic Safety and Licensing Board dated June 14, 1974, (3) the Decision of the Atomic Safety and Licensing Appeal Board dated July 5, 1974, (4) the Memorandum and Order of the Commission dated August 8, 1974, (5) any further modification resulting from further review by the Appeal Board and by the Commission, if any, and (6) any Environmental Impact Appraisal which has been or may be issued by the NRC since the FES was published in April 1973.

(19) Subsequent Renewed License Conditions.

(a)

The information in the Updated Final Safety Analysis Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d), as revised during the subsequent license renewal application review process, and Exelon Generation Company commitments as listed in Appendix A of the Safety Evaluation Report Related to the Subsequent License Renewal of Peach Bottom Atomic Power Station, Units 2 and 3, dated February 2020, are collectively the Subsequent License Renewal UFSAR Supplement. This

Page 15 Subsequent Renewed License No. DPR-44 Amendment No. 333 Supplement is henceforth part of the UFSAR, which will be updated in accordance with 10 CFR 50.71(e). As such, Exelon Generation Company may make changes to the programs, activities, and commitments described in the Subsequent License Renewal UFSAR Supplement, provided Exelon Generation Company evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59, Changes, Tests, and Experiments, and otherwise complies with the requirements in that section.

(b)

The Subsequent License Renewal UFSAR Supplement, as defined in subsequent renewed license condition (19)(a) above, describes programs to be implemented and activities to be completed prior to the subsequent period of extended operation, which is the period following the August 8, 2033, expiration of the initial renewed license.

1.

Exelon Generation Company shall implement those new programs and enhancements to existing programs no later than 6 months before the subsequent period of extended operation.

2.

Exelon Generation Company shall complete those activities by the 6-month date prior to the subsequent period of extended operation or by the end of the last refueling outage before the subsequent period of extended operation, whichever occurs later.

3.

Exelon Generation Company shall notify the NRC in writing within 30 days after having accomplished item (b)1 above and include the status of those activities that have been or remain to be completed in item (b)2 above.

3.

This subsequent renewed license is effective as of the date of issuance and shall expire at midnight on August 8, 2053.

FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION

/RA/

Ho K. Nieh, Director Office of Nuclear Reactor Regulation Attachments:

Appendix A - Technical Specifications Peach Bottom Atomic Power Station Unit 2 Appendix B - Environmental Protection Plan Date of Issuance: March 5, 2020

Page 4 Subsequent Renewed License No. DPR-56 Amendment No. 336 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans1 submitted by letter dated May 17, 2006, is entitled:

"Peach Bottom Atomic Power Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 3." The set contains Safeguards Information protected under 10 CFR 73.21.

Exelon Generation Company 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 Exelon Generation Company CSP was approved by License Amendment No. 283 and modified by Amendment No. 304.

(4)

Fire Protection The Exelon Generation Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility, and as approved in the NRC Safety Evaluation Report (SER) dated May 23, 1979, and Supplements dated August 14, September 15, October 10 and November 24, 1980, and in the NRC SERs dated September 16, 1993, and August 24, 1994, subject to the following provision:

The Exelon Generation Company may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(5)

Public Service Electric & Gas Company (PSE&G) to PSEG Nuclear License Transfer Conditions (a)

Deleted.

(b)

Deleted.

(c)

PSEG Nuclear, shall not take any action that would cause PSEG Power, LLC or its parent companies to void, cancel, or diminish the commitment to fund an extended plant shutdown as represented in the application for approval of the transfer of this license from PSE&G to PSEG Nuclear.

(6)

Exelon Generation Company shall provide to the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from Exelon Generation Company to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent 1 The Training and Qualification Plan and Safeguards Contingency Plan and Appendices to the Security Plan.

Page 5 Subsequent Renewed License No. DPR-56 Amendment No. 336 (10%) of Exelon Generation Company's consolidated net utility plant, as recorded on Exelon Generation Company's books of account.

(7)

Deleted.

(8)

Deleted.

(9)

Deleted.

(10) Additional Conditions of the Renewed License (a)

Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement, as revised on January 31, 2003, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following the issuance of this renewed license. Until that update is complete, the Exelon Generation Company may make changes to the programs described in the supplement without prior Commission approval, provided that the Exelon Generation Company evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(b)

Future Inspection Activities The Exelon Generation Company Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on January 31, 2003, describes certain future inspection activities to be completed before the period of extended operation.

The Exelon Generation Company shall complete these activities no later than July 2, 2014, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(c)

Integrated Surveillance Program The Exelon Generation Company shall implement an NRC staff-approved reactor vessel integrated surveillance program for the extended period of operation which satisfies the requirements of 10 CFR Part 54. Such a program will be implemented through a staff-approved Boiling Water Reactor Vessel and Internals Project program or through a staff-approved plant-specific program. Before July 2, 2014, the licensee will notify the NRC of its decision to implement the integrated surveillance program or a plant-specific program, and provide the appropriate revisions to the Updated Final Safety Analysis Report Supplement summary descriptions of the vessel surveillance material testing program.

Page 6 Subsequent Renewed License No. DPR-56 Amendment No. 336 (d)

Core Shroud Inspection and Evaluation Guidelines Program The Exelon Generation Company shall implement an NRC staff-approved core shroud inspection and evaluation guidelines program for the extended period of operation which satisfies the requirements of 10 CFR Part 54. Such a program will be implemented through a staff-approved Boiling Water Reactor Vessel and Internals Project program or through a staff-approved, plant-specific program. Before July 2, 2014, the licensee will notify the NRC of its decision to implement the core shroud inspection and evaluation guidelines program or a plant-specific program, and provide the appropriate revisions to the Updated Final Safety Analysis Report Supplement summary descriptions of the core shroud inspection and evaluation guidelines program.

(11) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders (12) The licensee shall implement and maintain all Actions required by to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(13) Deleted

Page 7 Subsequent Renewed License No. DPR-56 Amendment No. 336 (14) Spent Fuel Pool Criticality Considerations (a)

Use of spent fuel pool storage cells without NETCO-SNAP-IN rack inserts shall be restricted as follows:

1)

Minimum panel Boron-10 areal density of a storage cell shall be greater than or equal to 0.014 grams per square centimeter to store fuel assemblies with the maximum in-core cold k-infinity of up to 1.235 (except as noted in a.3 below for restricted cells). The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

2)

A storage cell shall not contain any fuel assembly if the minimum panel Boron-10 areal density of a storage cell is less than 0.014 grams per square centimeter (except as noted in a.3 below for restricted cells). The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

3)

For the period up to December 31, 2013, cells whose minimum panel Boron-10 areal density is between 0.014 grams per square centimeter and 0.0112 grams per square centimeter may be used as restricted cells. Restricted cells will only contain Peach Bottom Unit 3 GE14 fuel assemblies with an assembly average burnup of greater than 47,400 megawatt days per metric ton. The minimum panel Boron-10 areal density shall be evaluated by assuming that the panel areal density was initially equal to a value of 0.0235 grams per square centimeter.

(b)

Until the installation of NETCO-SNAP-IN rack inserts are completed in the Peach Bottom Unit 3 spent fuel pool, Boraflex degradation shall be monitored analytically every 6 months.

(c)

Boraflex degradation shall be monitored by in-situ testing in the Peach Bottom Unit 3 spent fuel pool no later than December 31, 2013, unless installation of the NETCO-SNAP-IN rack inserts for Unit 3 have been completed prior to this date.

(d)

Installation of NETCO-SNAP-IN rack inserts shall be completed by December 31, 2016.

(15) Potential Adverse Flow Effects In conjunction with the license amendment to revise paragraph 2.C(1) of Renewed Facility Operating License No. DPR-56, for Peach Bottom Unit 3, to reflect the new maximum licensed reactor core power level of 3951 megawatts thermal (MWt), the license is also amended to add the following

Page 8 Subsequent Renewed License No. DPR-56 Amendment No. 336 license condition. This license condition provides for monitoring, evaluating, and taking prompt action in response to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structural integrity of the steam dryer). This license condition is applicable to the initial power ascension from 3514 MWt to the extended power uprate (EPU) power level of 3951 MWt:

(a)

The following requirements are placed on the initial operation of the facility, above the thermal power level of 3514 MWt, for the power ascension to 3951 MWt. These conditions are applicable until the first time full EPU conditions (3951 MWt) are achieved. If the number of active main steam line (MSL) strain gauges is less than two strain gauges (180 degrees apart) at any of the eight MSL locations, Exelon Generation Company will stop power ascension and repair/replace the damaged strain gauges and only then resume power ascension.

1.

At least 30 days prior to the start of the Peach Bottom Unit 3 EPU outage, Exelon Generation Company shall revise the Peach Bottom Unit 3 replacement steam dryer (RSD) analysis utilizing the Unit 2 on-dryer strain gauge based end-to-end Bias errors and Uncertainties (B/Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for Unit 3, to the NRC as a report in accordance with 10 CFR 50.4.

2.

Exelon Generation Company shall evaluate the Unit 3 limit curves prepared in (a)1 above based on new MSL strain gauge data collected following the Unit 3 EPU outage at or near 3514 MWt. If the limit curves change, the new post-EPU outage limit curves shall be provided by e-mail to the NRC Project Manager. Exelon Generation Company shall not increase power above 3514 MWt for at least 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the reports unless, prior to expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension.

3.

Exelon Generation Company shall provide a brief vibration summary report, for piping and valves vibration data collected at or near 3514 MWt, for NRC review before increasing power above 3514 MWt. The summary report shall be provided by e-mail to the NRC Project Manager. Exelon Generation Company shall not increase power above 3514 MWt for at least 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the report unless, prior to expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension. The vibration summary report shall include the information in items a through c, as follows:

Page 9 Subsequent Renewed License No. DPR-56 Amendment No. 336

a.

Vibration data for piping and valve locations deemed prone to vibration and vibration monitoring locations identified in Attachment 13 to the EPU application dated September 28, 2012, and Supplement 16 dated December 20, 2013, including the following locations:

MSLs (including those in the drywell, turbine building and in the steam tunnel), Feedwater Lines (including those in the drywell and turbine building), Safety Relief Valves (SRVs) and the Main Steam Isolation Valves in the drywell.

b.

An evaluation of the measured vibration data collected in item 3.a above compared against acceptance limits.

c.

Predicted vibration values and associated acceptance limits at approximately 104 percent, 108 percent and 112.4 percent of 3514 MWt using the data collected in item 3.a above.

4.

Exelon Generation Company shall monitor the MSL strain gauges during power ascension above 3514 MWt for increasing pressure fluctuations in the steam lines. Upon the initial increase of power above 3514 MWt until reaching 3951 MWt, Exelon Generation Company shall collect data from the MSL strain gauges at nominal 2 percent thermal power increments and evaluate steam dryer performance based on this data.

5.

During power ascension at each nominal 2 percent power level above 3514 MWt, Exelon Generation Company shall compare the MSL data to the approved limit curves based on end-to-end B/Us from the Peach Bottom Unit 2 benchmarking at EPU conditions and determine the minimum alternating stress ratio (MASR). A summary of the results shall be provided for NRC review at approximately 104 percent and 108 percent of 3514 MWt. The summary report shall be provided to the NRC Project Manager via e-mail.

6.

Exelon Generation Company shall hold the facility at approximately 104 percent and 108 percent of 3514 MWt to perform the following:

a.

Collect strain data from the MSL strain gauges.

b.

Collect vibration data for the locations included in the vibration summary report discussed above.

c.

Evaluate steam dryer performance based on MSL strain gauge data.

Page 10 Subsequent Renewed License No. DPR-56 Amendment No. 336

d.

Evaluate the measured vibration data (collected in item 6.b above) at that power level, data projected to EPU conditions, trends, and comparison with the acceptance limits.

e.

Provide the steam dryer evaluation and the vibration evaluation, including the data collected, via e-mail to the NRC Project Manager, upon completion of the evaluation for each of the hold points.

f.

Exelon Generation Company shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the evaluations unless, prior to the expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension.

7.

If any frequency peak from the MSL strain gauge data exceeds the Level 1 limit curves, Exelon Generation Company shall return the facility to a power level at which the limit curve is not exceeded. Exelon Generation Company shall resolve the discrepancy, evaluate and document the continued structural integrity of the steam dryer, and provide that documentation to the NRC Project Manager via e-mail prior to further increases in reactor power. If a revised stress analysis is performed and new limit curves are developed, then Exelon Generation Company shall not further increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the documentation or until the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension, whichever comes first. Additional detail is provided in paragraph (b)1 below.

(b)

Exelon Generation Company shall implement the following actions for the initial power ascension from 3514 MWt to 3951 MWt condition:

1.

In the event that acoustic signals (in MSL strain gauge signals) are identified that exceed the Level 1 limit curves during power ascension above 3514 MWt, Exelon Generation Company shall re-evaluate dryer loads and stresses, and re-establish the limit curves. In the event that stress analyses are reperformed based on new strain gauge data to address paragraph (a)7 above, the revised load definition, stress analysis, and limit curves shall include:

a.

Application of end-to-end B/Us as determined from Peach Bottom Unit 2 EPU measurements.

b.

Use of bump-up factors associated with all of the SRV acoustic resonances as determined from the scale model

Page 11 Subsequent Renewed License No. DPR-56 Amendment No. 336 test results or in-plant data acquired during power ascension.

2.

After reaching 3951 MWt, Exelon Generation Company shall obtain measurements from the MSL strain gauges and establish the steam dryer flow-induced vibration load fatigue margin for the facility, update the dryer stress report, and re-establish the limit curves with the updated load definition.

These data will be provided to the NRC staff as described below in paragraph (e).

(c)

Exelon Generation Company shall prepare the EPU power ascension test procedure to include:

1.

The MSL strain gage limit curves to be applied for evaluating steam dryer performance, based on end-to-end B/Us from Peach Bottom Unit 2 benchmarking at EPU conditions.

2.

Specific hold points and their durations during EPU power ascension.

3.

Activities to be accomplished during the hold points.

4.

Plant parameters to be monitored.

5.

Inspections and walkdowns to be conducted for steam, feedwater, and condensate systems and components during the hold points

6.

Methods to be used to trend plant parameters.

7.

Acceptance criteria for monitoring and trending plant parameters, and conducting the walkdowns and inspections.

8.

Actions to be taken if acceptance criteria are not satisfied.

9.

Verification of the completion of commitments and planned actions specified in the application and all supplements to the application in support of the EPU license amendment request pertaining to the steam dryer prior to power increase above 3514 MWt. Exelon Generation Company shall provide the related EPU startup test procedure sections to the NRC Project Manager via e-mail prior to increasing power above 3514 MWt.

(d)

The following key attributes of the program for verifying the continued structural integrity of the steam dryer shall not be made less restrictive without prior NRC approval:

1.

During initial power ascension testing above 3514 MWt, each of the two hold points shall be at increments of approximately 4 percent of 3514 MWt.

Page 12 Subsequent Renewed License No. DPR-56 Amendment No. 336

2.

Level 1 performance criteria.

3.

The methodology for establishing the limit curves used for the Level 1 and Level 2 performance.

(e)

The results of the power ascension testing to verify the continued structural integrity of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall include a final load definition and stress report of the steam dryer, including the results of a complete re-analysis using the end-to-end B/Us from Peach Bottom Unit 2 benchmarking at EPU conditions.

The report shall be submitted within 90 days of the completion of EPU power ascension testing for Peach Bottom Unit 3.

(f)

During the first two scheduled refueling outages after reaching EPU conditions, a visual inspection shall be conducted of the steam dryer as described in the inspection guidelines contained in WCAP-17635-P.

(g)

The results of the visual inspections of the steam dryer shall be submitted to the NRC staff in a report in accordance with 10 CFR 50.4. The report shall be submitted within 90 days following startup from each of the first two respective refueling outages.

(h)

Within 6 months following completion of the second refueling outage, after the implementation of the EPU, the licensee shall submit a long-term steam dryer inspection plan based on industry operating experience along with the baseline inspection results.

The license condition described above shall expire: (1) upon satisfaction of the requirements in paragraphs (f) and (g), provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw(s) or unacceptable flaw growth that is due to fatigue, and; (2) upon satisfaction of the requirements specified in paragraph (h).

(16) Maximum Extended Load Line Limit Analysis Plus (MELLLA+) Special Consideration The licensee shall not operate the facility within the MELLLA+ operating domain with a feedwater heater out of service resulting in more than a 10°F reduction in feedwater temperature below the design feedwater temperature.

(17) Adoption of 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants In support of implementing License Amendment No. 324 permitting the adoption of the provisions of 10 CFR 50.69 for Renewed Facility Operating License No. DPR-56 for Peach Bottom Unit 3, the license is amended to add the following license condition:

Page 13 Subsequent Renewed License No. DPR-56 Amendment No. 336 (a)

Exelon is approved to implement 10 CFR 50.69 using the processes for categorization of Risk-Informed Safety Class (RISC)-1, RISC-2, RISC-3, and RISC-4 structures, systems, and components (SSCs) using: Probabilistic Risk Assessment (PRA) models to evaluate risk associated with internal events, including internal flooding, and internal fire; the shutdown safety assessment process to assess shutdown risk; the Arkansas Nuclear One, Unit 2 (AN0-2) passive categorization method to assess passive component risk for Class 2 and Class 3 SSCs and their associated supports; and the results of non-PRA evaluations that are based on the IPEEE Screening Assessment for External Hazards, i.e., seismic margin analysis (SMA) to evaluate seismic risk, and a screening of other external hazards updated using the external hazard screening significance process identified in ASME/ANS PRA Standard RA-Sa-2009; as specified in Unit 3 License Amendment No. 324 dated October 25, 2018.

Exelon will complete the implementation items listed in Attachment 2 of Exelon's letter to the NRC dated June 6, 2018, prior to implementation of 10 CFR 50.69. All issues identified in the attachment will be addressed and any associated changes will be made, focused-scope peer reviews will be performed on changes that are PRA upgrades as defined in the PRA standard (ASME/ANS RA-Sa-2009, as endorsed by RG 1.200, Revision 2), and any findings will be resolved and reflected in the PRA of record prior to implementation of the 10 CFR 50.69 categorization process.

Prior NRC approval, under 10 CFR 50.90, is required for a change to the categorization process specified above (e.g., change from a seismic margins approach to a seismic probabilistic risk assessment approach).

(18) This subsequent renewed license is subject to the following conditions for the protection of the environment:

(a)

To the extent matters related to thermal discharges are treated therein, operation of Peach Bottom Atomic Power Station, Unit No. 3, will be governed by NPDES Permit No. PA 0009733, as now in effect and as hereafter amended. Questions pertaining to conformance thereto shall be referred to and shall be determined by the NPDES Permit issuing or enforcement authority, as appropriate.

(b)

In the event of any modification of the NPDES Permit related to thermal discharges or the establishment (or amendment) of alternative effluent limitations established pursuant to Section 316 of the Federal Water Pollution Control Act, the Exelon Generation Company shall inform the NRC and analyze any associated changes in or to the Station, its components, its operation or in the discharge of effluents therefrom. If such change would entail any modification to this license, or any Technical Specifications which are part of this license, or require NRC approval pursuant to 10 CFR 50.59 or

Page 14 Subsequent Renewed License No. DPR-56 Amendment No. 336 involve an environmental impact different than analyzed in the Final Environmental Statement, the Exelon Generation Company shall file with the NRC, as applicable, an appropriate analysis of any such change on facility safety, and/or an analysis of any such change on the environmental impacts and on the overall cost-benefit balance for facility operation set forth in the Final Environmental Statement and a request for an amendment to the operating license, if required by the Commission's regulations. As used in this Condition (18)(b), Final Environmental Statement (FES) means the NRC Staff Final Environmental Statement related to Operation of Peach Bottom Atomic Power Station, Units Nos. 2 and 3, dated April 1973, as modified by (1) the Initial Decision of the Atomic Safety and Licensing Board dated September 14, 1973, (2) the Supplemental Initial Decision of the Atomic Safety and Licensing Board dated June 14, 1974, (3) the Decision of the Atomic Safety and Licensing Appeal Board dated July 5, 1974, (4) the Memorandum and Order of the Commission dated August 8, 1974, (5) any further modification resulting from further review by the Appeal Board and by the Commission, if any, and (6) any Environmental Impact Appraisal which has been or may be issued by the NRC since the FES was published in April 1973.

(19) Subsequent Renewed License Conditions (a)

The information in the Updated Final Safety Analysis Report (UFSAR) supplement submitted pursuant to 10 CFR 54.21(d), as revised during the subsequent license renewal application review process, and Exelon Generation Company commitments as listed in Appendix A of the Safety Evaluation Report Related to the Subsequent License Renewal of Peach Bottom Atomic Power Station, Units 2 and 3, dated February 2020, are collectively the Subsequent License Renewal UFSAR Supplement. This Supplement is henceforth part of the UFSAR, which will be updated in accordance with 10 CFR 50.71(e). As such, Exelon Generation Company may make changes to the programs, activities, and commitments described in the Subsequent License Renewal UFSAR Supplement, provided Exelon Generation Company evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59, Changes, Tests, and Experiments, and otherwise complies with the requirements in that section.

(b)

The Subsequent License Renewal UFSAR Supplement, as defined in subsequent renewed license condition (19)(a) above, describes programs to be implemented and activities to be completed prior to the subsequent period of extended operation, which is the period following the July 2, 2034, expiration of the initial renewed license.

1.

Exelon Generation Company shall implement those new programs and enhancements to existing programs no later than 6 months before the subsequent period of extended operation.

Page 15 Subsequent Renewed License No. DPR-56 Amendment No. 336

2.

Exelon Generation Company shall complete those activities by the 6-month date prior to the subsequent period of extended operation or by the end of the last refueling outage before the subsequent period of extended operation, whichever occurs later.

3.

Exelon Generation Company shall notify the NRC in writing within 30 days after having accomplished item (b)1 above and include the status of those activities that have been or remain to be completed in item (b)2 above.

3.

This subsequent renewed license is effective as of the date of issuance and shall expire at midnight on July 2, 2054.

FOR THE UNITED STATES NUCLEAR REGULATORY COMMISSION

/RA/

Ho K. Nieh, Director Office of Nuclear Reactor Regulation Attachments:

Appendix A - Technical Specifications Peach Bottom Atomic Power Station Unit No. 3 Appendix B - Environmental Protection Plan Date of Issuance: March 5, 2020

0 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 280 Renewed License No. DPR-29

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. DPR-29 is hereby amended by deleting paragraphs 3.P, 3.Q, and 3.R.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

1 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 275 Renewed License No. DPR-30

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. DPR-30 is hereby amended by deleting paragraph 3.O, 3.P, and 3.Q.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NOS. 280 AND 275 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 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 5 Page 5 Page 6 Page 6 Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

License DPR-30 License DPR-30 Page 5 Page 5 Page 6 Page 6 Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

Renewed License No. DPR-29 Amendment No. 280 February 12, 1981; December 30, 1982; December 1, 1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G.

Deleted H.

Deleted by incorporation into 3.E above, per Amendment No. 64 dated March 19, 1981.

I.

(Open)

J.

Deleted K.

Deleted by Amendment No. 103 dated December 15, 1987.

L.

Deleted M.

Deleted N.

Deleted O.

EGC shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from EGC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of EGCs consolidated net utility plant, as recorded on EGCs books of account.

P.

Deleted.

Q.

Deleted.

Renewed License No. DPR-29 Amendment No. 280 R.

Deleted.

S.

EGG shall relocate certain Technical Specification requirements to EGG-controlled documents upon implementation of Amendment No. 199.

The items and appropriate documents are as described in Table LA, Removal of Details Matrix, and Table R, Relocated Specifications, that are attached to the NRCs Safety Evaluation enclosed with Amendment No. 199.

T.

The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 199 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of Amendment No. 199.

For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of Amendment No. 199.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of Amendment No. 199.

For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of Amendment No. 199.

U.

Deleted Renewed License No. DPR-29 Amendment No. 280 V.

The license is amended to authorize changing the UFSAR to allow credit for containment overpressure as detailed below, to assure adequate Net Positive Suction Head is available for low pressure Emergency Core Cooling System pumps following a design-basis accident.

From (sec)

Accident start To (sec) 290 Credit (psig) 8.0 290 5,000 4.8 5,000 44,500 6.7 44,500 52,500 6.0 52,500 60,500 5.5 60,500 75,000 4.7 75,000 95,000 3.8 95,000 115,000 3.0 115,000 155,000 2.3 155,000 Accident end 1.8 W.

Updated Final Safety Analysis Report The Exelon Generation Company, LLC Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21(d), describes certain future activities to be completed prior to the period of extended operation. The Exelon Generation Company, LLC shall complete these activities no later than December 14, 2012, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following issuance of this renewed license. Until that update is complete, Exelon Generation Company, LLC may make changes to the programs and activities described in the supplement without prior Commission approval, provided that Exelon Generation Company, LLC evaluates such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed License No. DPR-29 Amendment No. 280 X.

All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion.

Y.

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders Z.

The licensee shall implement and maintain all Actions required by to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

Renewed License No. DPR-30 Amendment No. 275 November 5, 1980, and February 12, 1981; December 30, 1982; December 1, 1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G.

Deleted by incorporation into 3.E above, per Amendment No. 58 dated March 19, 1981.

H.

Deleted I.

Deleted J.

Deleted K.

Deleted L.

Deleted M.

Deleted N.

EGC shall provide the Director of the Office of Nuclear Reactor Regulation a copy of any application, at the time it is filed, to transfer (excluding grants of security interests or liens) from EGC to its direct or indirect parent, or to any other affiliated company, facilities for the production, transmission, or distribution of electric energy having a depreciated book value exceeding ten percent (10%) of EGCs consolidated net utility plant, as recorded on EGCs books of account.

O.

Deleted.

P.

Deleted.

Renewed License No. DPR-30 Amendment No. 275 Q.

Deleted.

R.

EGC shall relocate certain Technical Specification requirements to EGG-controlled documents upon implementation of Amendment No. 195.

The items and appropriate documents are as described in Table LA, Removal of Details Matrix, and Table R, Relocated Specifications, that are attached to the NRCs Safety Evaluation enclosed with Amendment No. 195.

S.

The schedule for performing Surveillance Requirements (SRs) that are new or revised in Amendment No. 195 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of Amendment No. 195.

For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of Amendment No. 195.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of Amendment No. 195.

For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of Amendment No. 195.

T.

Deleted Renewed License No. DPR-30 Amendment No. 275 U.

The license is amended to authorize changing the UFSAR to allow credit for containment overpressure as detailed below, to assure adequate Net Positive Suction Head is available for low pressure Emergency Core Cooling System pumps following a design-basis accident.

From (sec)

Accident start To (sec) 290 Credit (psig) 8.0 290 5,000 4.8 5,000 44,500 6.7 44,500 52,500 6.0 52,500 60,500 5.5 60,500 75,000 4.7 75,000 95,000 3.8 95,000 115,000 3.0 115,000 155,000 2.3 155,000 Accident end 1.8 V.

Updated Final Safety Analysis Report The Exelon Generation Company, LLC Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21(d), describes certain future activities to be completed prior to the period of extended operation. The Exelon Generation Company, LLC shall complete these activities no later than December 14, 2012, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following issuance of this renewed license. Until that update is complete, Exelon Generation Company, LLC may make changes to the programs and activities described in the supplement without prior Commission approval, provided that Exelon Generation Company, LLC evaluates such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed License No. DPR-30 Amendment No. 275 W.

All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion.

X.

Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders

2 R. E. GINNA NUCLEAR POWER PLANT, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 140 Renewed License No. DPR-18

1.

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

A.

The application for amendment by Exelon Generation Company, LLC dated August 28, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

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

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

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

2.

Accordingly, Renewed Facility Operating License No. DPR-18 is hereby amended by deleting paragraph 2.C.(7).

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 180 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/ Scott P. Wall for Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License Date of Issuance: April 6, 2020

ATTACHMENT TO LICENSE AMENDMENT NO. 140 RENEWED FACILITY OPERATING LICENSE NO. DPR-18 R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 Replace the following pages of the Renewed Facility Operating License 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-18 License DPR-18 Page 6 Page 6 Page 7 Page 7 (pagination)

Page 8 Page 8 (pagination)

Page 9 Page 9 (pagination)

R. E. Ginna Nuclear Power Plant Amendment No. 140

3.

The licensee shall complete the implementation items listed in LAR Attachment S, Table S-3, Implementation Items, of Exelon Generation letter dated June 11, 2015, as modified by Exelon Generation letter dated June 30, 2017, except Implementation Items 9, 10, 11, 12, 13, 14, 15, 19, 21, 23, and 24, by 180 days after NRC approval unless that date falls within a scheduled refueling outage, then implementation will occur 60 days after startup from that scheduled refueling outage. Implementation Items 9, 10, 11, 12, 13, 14, 15, 19, 21, 23, and 24 are associated with modifications described in Table S-2 and will be completed once the related modifications are installed and validated in the PRA model.

(4)

Deleted (5)

Deleted (6)

Deleted (7)

Deleted (8)

Mitigation Strategy Exelon Generation shall develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(a)

Fire fighting response strategy with the following elements:

1.

Pre-defined coordinated fire response strategy and guidance

2.

Assessment of mutual aid fire fighting assets

3.

Designated staging areas for equipment and materials

4.

Command and control

5.

Training of response personnel (b)

Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets

2.

Communications

3.

Minimizing fire spread

4.

Procedures for implementing integrated fire response strategy

5.

Identification of readily-available pre-staged equipment

6.

Training on integrated fire response strategy

7.

Spent fuel pool mitigation measures (c)

Actions to minimize release to include consideration of:

1.

Water spray scrubbing

2.

Dose to onsite responders R. E. Ginna Nuclear Power Plant Amendment No. 140 (9)

Control Room Envelope Habitability Upon implementation of Amendment No. 105 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by SR 3.7.9.4, in accordance with TS 5.5.16.c.i and the assessment of CRE habitability as required by 5.5.16.c.ii, shall be considered met. Following implementation:

(a)

The first performance of SR 3.7.9.4 in accordance with Specification 5.5.16.c.i shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from February 8, 2005, the date of the most recent successful tracer gas test, as-stated in the April 6, 2007 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent tracer gas test is greater than 6 years.

(b)

The first performance of the periodic assessment of CRE habitability, Specification 5.5.16.c.ii, shall be within 3 years, plus the 9-month allowance of SR 3.0.2 as measured from February 8, 2005, the date of the most recent successful tracer gas test, as stated in-the April 6, 2007 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(10)

The existing E.D.F. International S.A.S. Support Agreement of approximately $145 million, dated November 6, 2009, may not be amended or modified without 30 days prior written notice to the Director of the Office of Nuclear Reactor Regulation or his designee. R. E. Ginna Nuclear Power Plant, LLC, CENG, or Exelon Generation shall not take any action to cause E.D.F. International S.A.S., or its successors and assigns, to void, cancel, or materially modify the E.D.F. International S.A.S. Support Agreement or cause it to fail to perform, or impair its performance under the E.D.F. International S.A.S. Support Agreement, without the prior written consent of the NRC. Exelon Generation shall inform the NRC in writing no later than 14 days after any funds are provided to or for the CENG subsidiary licensee under the E.D.F.

International S.A.S. Support Agreement.

R. E. Ginna Nuclear Power Plant Amendment No. 140 (11)

Exelon Corporation shall, no later than the time the license transfers occur, enter into a Support Agreement of approximately $245 million with the licensee. The Exelon Corporation Support Agreement shall supersede the Support Agreement provided by Exelon Generation, dated March 12, 2012, in all respects and shall be consistent with the representations contained in the August 6, 2013 transfer application.

R. E. Ginna Nuclear Power Plant, LLC, CENG, or Exelon Generation shall not take any action to cause Exelon Corporation, or its successors and assigns, to void, cancel, or materially modify the Exelon Corporation Support Agreement or cause it to fail to perform, or impair its performance under the Exelon Corporation Support Agreement, without the prior written consent of the NRC. The Exelon Corporation Support Agreement may not be amended or modified without 30 days prior written notice to the Director of the Office of Nuclear Reactor Regulation or his designee. An executed copy of the Exelon Corporation Support Agreement shall be submitted to the NRC no later than 30 days after the completion of the proposed transaction and license transfers. Exelon Generation shall inform the NRC in writing no later than 14 days after any funds are provided to or for the licensee under the Exelon Corporation Support Agreement.

(12)

Exelon Corporation shall, no later than the time the license transfers occur, provide a parent guarantee in the amount of $165 million to ensure a source of funds for the facility in the event that the existing cash pool between the licensee and CENG is insufficient to cover operating costs. The existing CENG cash pool arrangement shall be consistent with the representations contained in the 2009 Transfer Application dated January 22, 2009 (ADAMS Accession No. ML090290101).

R. E. Ginna Nuclear Power Plant, LLC, CENG, or Exelon Generation shall not take any action to cause Exelon Corporation, or its successors and assigns, to void, cancel or materially modify the parent guarantee or cause it to fail to perform, or impair its performance under the parent guarantee without the prior written consent of the NRC.

(13)

Within 14 days of the license transfers, Exelon Generation shall submit to the NRC the Nuclear Operating Services Agreement reflecting the terms set forth in the application dated August 6, 2013. Section 7.1 of the Nuclear Operating Services Agreement may not be modified in any material respect related to financial arrangements that would adversely impact the ability of the licensee to fund safety-related activities authorized by the license without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.

(14)

Within 10 days of the license transfers, Exelon Generation shall submit to the NRC the amended CENG Operating Agreement reflecting the terms set forth in the application dated August 6, 2013. The amended and restated Operating Agreement may not be modified in any material respect concerning decision-making authority over safety, security and reliability without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.

R. E. Ginna Nuclear Power Plant Amendment No. 140 (15)

At least half the members of the CENG Board of Directors must be U.S.

citizens.

(16)

The CENG Chief Executive Officer, Chief Nuclear Officer, and Chairman of the CENG Board of Directors must be U.S. citizens. These individuals shall have the responsibility and exclusive authority to ensure and shall ensure that the business and activities of CENG with respect to the facilitys license are at all times conducted in a manner consistent with the public health and safety and common defense and security of the United States.

(17)

Deleted (18)

Deleted D.

The facility requires an exemption from certain requirements of 10 CFR 50.46(a)(1). This includes an exemption from 50.46(a)(1), that emergency core cooling system (ECCS) performance be calculated in accordance with an acceptable calculational model which conforms to the provisions in Appendix K (SER dated April 18, 1978). The exemption will expire upon receipt and approval of revised ECCS calculations. The aforementioned exemption is authorized by law and will not endanger life property or the common defense and security and is otherwise in the public interest. Therefore, the exemption is hereby granted pursuant to 10 CFR 50.12.

E.

Exelon Generation 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 27827 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: R. E. Ginna Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, submitted by letter dated May 15, 2006.

Exelon Generation 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 licensee's CSP was approved by License Amendment No. 113 and modified by License Amendment No. 117. The licensee has obtained Commission authorization to use Section 161A preemption authority under 42 U.S.C. 2201a for weapons at its facility.

3 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 208 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 208 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 214 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 214 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-66, AMENDMENT NO. 230 TO FACILITY OPERATING LICENSE NO. NPF-62, AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO. DPR-2, AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19, AMENDMENT NO. 260 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25, AMENDMENT NO. 334 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-59, AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-11, AMENDMENT NO. 229 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-18, AMENDMENT NO. 244 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-39, AMENDMENT NO. 207 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-85, AMENDMENT NO. 242 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-63, AMENDMENT NO. 180 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-69, AMENDMENT NO. 16 TO FACILITY OPERATING LICENSE NO. DPR-12, AMENDMENT NO. 333 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-44, AMENDMENT NO. 336 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-56, AMENDMENT NO. 280 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29, AMENDMENT NO. 275 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30, AND AMENDMENT NO. 140 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-18 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 1, 2, AND 3 JAMES A. FITZPATRICK NUCLEAR POWER PLANT LASALLE COUNTY STATION, UNITS 1 AND 2 LIMERICK GENERATING STATION, UNITS 1 AND 2 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 1, 2, AND 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 R. E. GINNA NUCLEAR POWER PLANT DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461,50-010, 50-237, 50-249, 50-333, 50-373, 50-374, 50-352, 50-353, 50-220, 50-410, 50-171, 50-277, 50-278, 50-254, 50-265, AND 50-244

1.0 INTRODUCTION

By application dated August 28, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19240B609), Exelon Generation Company, LLC (Exelon) submitted a license amendment request (LAR) for Braidwood Station (Braidwood), Units 1 and 2; Byron Station (Byron), Unit Nos. 1 and 2; Clinton Power Station (Clinton), Unit No. 1; Dresden Nuclear Power Station (Dresden), Units 1, 2, and 3; James A. FitzPatrick Nuclear Power Plant (FitzPatrick); LaSalle County Station (LaSalle), Units 1 and 2; Limerick Generating Station (Limerick), Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2 (NMP-1 and NMP-2, respectively); Peach Bottom Atomic Power Station (Peach Bottom), Units 1, 2, and 3; Quad Cities Nuclear Power Station (Quad Cities), Units 1 and 2; and R. E. Ginna Nuclear Power Plant (Ginna) (collectively, the facilities). The amendments would delete certain license conditions that specify requirements for decommissioning trust agreements for these facilities.

The amendments would also delete some obsolete license conditions associated with completed license transfers for these facilities. Upon the implementation of the amendments, the decommissioning trust fund requirements in Sections 50.75(h)(1) and (3) of Title 10 of the Code of Federal Regulations (10 CFR) would apply to Exelon; PSEG Nuclear LLC (PSEG Nuclear); Nine Mile Point Nuclear Station, LLC (NMP LLC); and R. E. Ginna Nuclear Power Plant, LLC (Ginna LLC).

2.0 REGULATORY EVALUATION

2.1 Description of Proposed Changes In its application, Exelon proposes to delete certain license conditions that specify requirements for decommissioning trust agreements for its facilities. The amendments would also delete some obsolete license conditions associated with completed license transfers for its facilities.

The specific license conditions to be deleted are listed in Table 1 below. The table lists the applicable licensee for each license condition. The table also lists the page in the attachment to this safety evaluation where the full text for the license conditions are provided.

Table 1: License Conditions to be Deleted Reactor Unit License Conditions Applicable Licensee Attachment Page Braidwood, Unit 1 2.C.(9) through 2.C.(11)

Exelon A-1 Braidwood, Unit 2 2.C.(8) through 2.C.(10)

Exelon A-2 Byron, Unit No. 1 2.C.(19) through 2.C.(21)

Exelon A-3 Byron, Unit No. 2 2.C.(8) through 2.C.(10)

Exelon A-4 Clinton 2.C.(15) through 2.C.(20)

Exelon A-5 Dresden, Unit 1 2.C.(8) through 2.C.(10)

Exelon A-6 Dresden, Unit 2 2.C.(11) through 2.C.(13)

Exelon A-7 Dresden, Unit 3 3.S through 3.U Exelon A-8 FitzPatrick 2.P and 2.Q Exelon A-9 LaSalle, Unit 1 2.C.(39) through 2.C.(41)

Exelon A-10 LaSalle, Unit 2 2.C.(23) through 2.C.(25)

Exelon A-11 Limerick, Unit 1 2.C.(18) through 2.C.(20)

Exelon A-12 Limerick, Unit 2 2.C.(6) through 2.C.(8)

Exelon A-13 NMP-1 2.D.(9) through 2.D.(12)

NMP LLC A-14 NMP-2 2.C.(12) through 2.C.(15)

NMP LLC A-16 Peach Bottom, Unit 1 2.C.(5) and 2.C.(6)

Exelon A-18 Peach Bottom, Unit 2 2.C.(5)(a) and 2.C.(5)(b)

PSEG Nuclear A-19 2.C.(7) through 2.C.(9)

Exelon Peach Bottom, Unit 3 2.C.(5)(a) and 2.C.(5)(b)

PSEG Nuclear A-21 2.C.(7) through 2.C.(9)

Exelon Quad Cities, Unit 1 3.P though 3.R Exelon A-23 Quad Cities, Unit 2 3.O through 3.Q Exelon A-24 Ginna 2.C.(7)

Ginna LLC A-25 Ownership of Peach Bottom, Units 2 and 3, is shared by Exelon and PSEG Nuclear. For each unit, license conditions 2.C.(5)(a) and 2.C.(5)(b) specify requirements for PSEG Nuclear regarding the decommissioning trust for the unit. These conditions were added to the licenses on August 21, 2000 (ADAMS Package Accession No. ML003744784), by conforming amendments for the transfer of Peach Bottom, Units 2 and 3, to PSEG Nuclear. The LAR states that PSEG Nuclear concurred on the proposed deletion of these license conditions.

On January 12, 2001, the NRC staff issued conforming amendments for the transfer of the licenses for Braidwood, Byron, Dresden, LaSalle, Limerick, Peach Bottom, and Quad Cities to Exelon.1 These amendments added the license conditions listed in Table 1 for each of these units, except for conditions 2.C.(5)(a) and 2.C.(5)(b) for Peach Bottom, Units 2 and 3. Editorial changes were made to license condition 2.C.(5) for Peach Bottom, Unit 1, by amendment dated December 26, 2002 (ADAMS Accession No. ML023650129). The license conditions specify requirements for Exelon regarding the decommissioning trusts for each unit, including the minimum funds required at the time of the license transfer.

Clinton license conditions 2.C.(15) through 2.C.(20) were originally added by a conforming amendment issued on December 15, 1999 (ADAMS Package Accession No. ML993550164),

for the transfer of the license to AmerGen Energy Company, LLC. Subsequently, the license was transferred from AmerGen Energy Company, LLC to Exelon and these license conditions were revised by the associated conforming amendment on January 8, 2009 (ADAMS Accession No. ML082770568). These license conditions specify requirements for Exelon regarding the decommissioning trust for Clinton.

FitzPatrick license conditions 2.P and 2.Q were originally added by a conforming amendment issued on November 21, 2000 (ADAMS Accession No. ML003776144), for the transfer of the license to Entergy Nuclear FitzPatrick, LLC (ENF) and Entergy Nuclear Operations, Inc.

(Entergy). These conditions were revised on January 30, 2017 (ADAMS Accession No. ML17025A288), by a conforming amendment associated with the transfer of the master decommissioning trust from the Power Authority of the State of New York (PASNY) to Entergy.

These conditions were further revised on March 31, 2017 (ADAMS Accession No. ML17082A283), by a conforming amendment associated with the transfer of the FitzPatrick license from ENF and Entergy to Exelon. On November 30, 2017 (ADAMS Accession No. ML17313A077), editorial changes to these conditions were made by a conforming amendment associated with the transfer of ownership of FitzPatrick to Exelon FitzPatrick, LLC.

With this last transfer, Exelon retained responsibility for decommissioning the facility and the associated decommissioning trust fund. These license conditions specify requirements for Exelon regarding the decommissioning trust for FitzPatrick.

NMP-1 is owned by NMP LLC, and NMP-2 is owned by NMP LLC and Long Island Lighting Company. Exelon operates both plants and is authorized to act for both owners. The conditions listed in Table 1 for NMP-1 and NMP-2 were added to the licenses on November 7, 2001 (ADAMS Accession No. ML011780405), by conforming amendments associated with the transfer of the licenses for these units to NMP LLC. For each unit, three license conditions specify requirements for NMP LLC regarding the associated decommissioning trust. The fourth license condition for each unit required NMP LLC to have an intercompany credit agreement with its ultimate parent company by the time the 2001 license transfer was completed. The changes proposed in the LAR do not affect any requirements for the Long Island Lighting Company.

Ginna is owned by Ginna LLC, but Exelon is authorized to act for Ginna LLC. Ginna license condition 2.C.(7) was originally added by a conforming amendment issued on June 10, 2004 (ADAMS Accession No. ML041600248), for the transfer of the license to Ginna LLC. This license condition was modified by a conforming amendment issued on April 1, 2014 (ADAMS 1 ADAMS Accession Nos. ML010190298 (Braidwood and Byron), ML010190290 (Dresden),

ML010190287 (LaSalle), ML010160221 (Limerick), ML010100250 (Peach Bottom), and ML010190295 (Quad Cities).

Accession No. ML14091A366), associated with the transfer of the operating authority for Ginna from Ginna LLC to Exelon. The license condition specifies requirements for Ginna LLC regarding the decommissioning trust for Ginna.

2.2 Regulatory Requirements On December 24, 2002, the U.S. Nuclear Regulatory Commission (NRC) issued a final rule (67 FR 78332) promulgating new regulatory provisions at 10 CFR 50.75(h) that govern decommissioning financial assurance mechanisms for licensees that are not electric utilities.2 These provisions include, at 10 CFR 50.75(h)(1) and (3), decommissioning trust requirements for licensees that are not electric utilities that are similar to those found in pre-existing license conditions for Exelons facilities. In establishing these requirements, the NRC stated that it has always believed that it is preferable and more efficient to adopt standard rules, as opposed to applying specific license conditions on a case-by-case basis (67 FR 78334). In the final rule, the NRC also addressed several comments regarding potential conflicts or inconsistencies between the provisions of 10 CFR 50.75(h)(1)-(3) and a licensees pre-existing license conditions related to decommissioning trust agreements. The NRC explained that licensees will have the option of maintaining their existing license conditions or submitting to the new requirements and will be able to decide for themselves whether they prefer to keep or eliminate their specific license conditions (67 FR 78335, 78339).

After the promulgation of 10 CFR 50.75(h) in 2002, the NRC received a comment that the rule language did not sufficiently reflect the NRCs intent that individual licensees should have the option of retaining their existing license conditions. In response, the NRC promulgated 10 CFR 50.75(h)(5) on November 20, 2003 (68 FR 65386), which explicitly allowed licensees to either retain their existing facility-specific decommissioning trust agreement license conditions or eliminate them, in favor of complying with the generic decommissioning trust agreement regulatory requirements. Specifically, 10 CFR 50.75(h)(5) states:

The provisions of paragraphs (h)(1) through (h)(3) of this section do not apply to any licensee that as of December 24, 2003, has existing license conditions relating to decommissioning trust agreements, so long as the licensee does not elect to amend those license conditions. If a licensee with existing license conditions relating to decommissioning trust agreements elects to amend those conditions, the license amendment shall be in accordance with the provisions of paragraph (h) of this section.

Exelon, PSEG Nuclear, NMP LLC, and Ginna LLC, are not electric utilities as defined in 10 CFR 50.2. Consistent with 10 CFR 50.75(h)(5), Exelon has elected to adopt the requirements of 10 CFR 50.75(h) for its facilities and has, accordingly, requested the deletion of existing license conditions relating to decommissioning trust agreements. Therefore, Exelon, PSEG Nuclear, NMP LLC, and Ginna LLC, as applicable, must comply with the provisions in 10 CFR 50.75(h)(1) and (3) upon the implementation of the proposed amendments.

2 The term electric utility is defined in 10 CFR 50.2, Definitions, as any entity that generates or distributes electricity and which recovers the cost of this electricity, either directly or indirectly, through rates established by the entity itself or by a separate regulatory authority. Investor-owned utilities, including generation or distribution subsidiaries, public utility districts, municipalities, rural electric cooperatives, and State and Federal agencies, including associations of any of the foregoing, are included within the meaning of electric utility.

3.0 TECHNICAL EVALUATION

3.1 Condition 1: Decommissioning Trust Agreements On January 12, 2001, the NRC staff issued conforming amendments for the transfer of the licenses for each unit at Braidwood, Byron, Dresden, LaSalle, Limerick, Peach Bottom, and Quad Cities to Exelon. These amendments all included license conditions equivalent to Condition 1 below. The primary difference between the license conditions for each of these units is the reactor unit listed in brackets below.

The conforming amendments for the 2000 license transfer of Peach Bottom, Units 2 and 3, to PSEG Nuclear added condition 2.C.(5)(b) to the licenses for both units; this condition is similar to Condition 1 except that it is applicable to PSEG Nuclear. Clinton has separate license conditions that are equivalent to each paragraph of Condition 1, but the Clinton license does not include an introductory clause for these conditions.

Condition 1 The decommissioning trust agreement for [Braidwood, Unit 1,] at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for [Braidwood, Unit 1,] must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

3.1.1 Condition 1a Condition 1a states that the decommissioning trust agreement must be in a form acceptable to the NRC. Exelon proposes to delete the license conditions listed in Table 2 below, which are equivalent to Condition 1a. The NRC staff finds that these license conditions are related to decommissioning trust agreements and are implicit in the regulations at 10 CFR 50.75(e) and (h). Thus, the decommissioning trust requirements in 10 CFR 50.75(h), consistent with 10 CFR 50.75(h)(5), would apply to Exelon and NMP LLC with the deletion of these license conditions. Therefore, the NRC staff finds Exelons request to delete the license conditions listed in Table 2 acceptable.

Table 2: License Conditions Equivalent to Condition 1a Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(10)(a)

Limerick, Unit 1 2.C.(19)(a)

Braidwood, Unit 2 2.C.(9)(a)

Limerick, Unit 2 2.C.(7)(a)

Byron, Unit No. 1 2.C.(20)(a)

NMP-1 2.D.(10)a Byron, Unit No. 2 2.C.(9)(a)

NMP-2 2.C.(13)a Clinton 2.C.(15)

Peach Bottom, Unit 1 2.C.(5)(a)

Dresden, Unit 1 2.C.(9)(a)

Peach Bottom, Unit 2 2.C.(8)(a)

Dresden, Unit 2 2.C.(12)(a)

Peach Bottom, Unit 3 2.C.(8)(a)

Dresden, Unit 3 3.T.(1)

Quad Cities, Unit 1 3.Q.(1)

FitzPatrick N/A Quad Cities, Unit 2 3.P.(1)

LaSalle, Unit 1 2.C.(40)(a)

Ginna 2.C.(7)(b)

LaSalle, Unit 2 2.C.(24)(a) 3.1.2 Condition 1b Condition 1b states:

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

Exelon proposes to delete the license conditions listed in Table 3 below. Clinton license condition 2.C.(16) refers to both Exelon Corporation and Exelon Generation Company. The NMP-1 and NMP-2 license conditions listed in Table 3 refer to Constellation Energy Group, Inc.,

and New Controlled instead of Exelon Corporation. The Peach Bottom, Units 2 and 3, license conditions applicable to PSEG Nuclear refer to the Public Service Electric & Gas Company (PSE&G) instead of Exelon Corporation. Aside from the references to different entities, the license conditions in Table 3 are equivalent to Condition 1b.

Table 3: License Conditions Equivalent to Condition 1b Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(10)(b)

Limerick, Unit 1 2.C.(19)(b)

Braidwood, Unit 2 2.C.(9)(b)

Limerick, Unit 2 2.C.(7)(b)

Byron, Unit No. 1 2.C.(20)(b)

NMP-1 2.D.(10)b Byron, Unit No. 2 2.C.(9)(b)

NMP-2 2.C.(13)b Clinton 2.C.(16)

Peach Bottom, Unit 1 2.C.(5)(b)

Dresden, Unit 1 2.C.(9)(b)

Peach Bottom, Unit 2 2.C.(5)(b)(2) and 2.C.(8)(b)

Dresden, Unit 2 2.C.(12)(b)

Peach Bottom, Unit 3 2.C.(5)(b)(2) and 2.C.(8)(b)

Dresden, Unit 3 3.T.(2)

Quad Cities, Unit 1 3.Q.(2)

FitzPatrick N/A Quad Cities, Unit 2 3.P.(2)

LaSalle, Unit 1 2.C.(40)(b)

Ginna N/A LaSalle, Unit 2 2.C.(24)(b)

The license conditions listed in Table 3 are addressed in 10 CFR 50.75(h)(1)(i)(A). Based on this information, the NRC staff finds that these license conditions are related to decommissioning trust agreements. Thus, the decommissioning trust requirements in 10 CFR 50.75(h), consistent with 10 CFR 50.75(h)(5), would apply to Exelon, NMP LLC, and PSEG Nuclear with the deletion of these license conditions. Therefore, the staff finds Exelons request to delete the license conditions listed in Table 3 acceptable.

3.1.3 Condition 1c Condition 1c states:

The decommissioning trust agreement for [Braidwood, Unit 1,] must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

Exelon proposes to delete the license conditions listed in Table 4 below. The primary difference between the license conditions is the plant name listed in the brackets. Some license conditions refer to the NRC instead of the Director of the Office of Nuclear Reactor Regulation, and vice-versa. The Peach Bottom, Unit 1, license condition requires notification be given to the Director of the Office of Nuclear Material Safety and Safeguards instead of the Director of the Office of Nuclear Reactor Regulation. The license conditions listed in Table 4 for NMP-1 and NMP-2 also clarify that ordinary administrative expenses associated with the decommissioning trust do not require prior NRC notification. The Peach Bottom, Units 2 and 3, license conditions applicable to PSEG Nuclear have some editorial differences from Condition 1c. Aside from these differences, the license conditions listed in Table 4 are equivalent to Condition 1c.

Table 4: License Conditions Equivalent to Condition 1c Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(10)(c)

Limerick, Unit 1 2.C.(19)(c)

Braidwood, Unit 2 2.C.(9)(c)

Limerick, Unit 2 2.C.(7)(c)

Byron, Unit No. 1 2.C.(20)(c)

NMP-1 2.D.(10)c Byron, Unit No. 2 2.C.(9)(c)

NMP-2 2.C.(13)c Clinton 2.C.(17)

Peach Bottom, Unit 1 2.C.(5)(c)

Dresden, Unit 1 2.C.(9)(c)

Peach Bottom, Unit 2 2.C.(5)(b)(3) and 2.C.(8)(c)

Dresden, Unit 2 2.C.(12)(c)

Peach Bottom, Unit 3 2.C.(5)(b)(3) and 2.C.(8)(c)

Dresden, Unit 3 3.T.(3)

Quad Cities, Unit 1 3.Q.(3)

FitzPatrick N/A Quad Cities, Unit 2 3.P.(3)

LaSalle, Unit 1 2.C.(40)(c)

Ginna N/A LaSalle, Unit 2 2.C.(24)(c)

The license conditions listed in Table 4 are addressed in 10 CFR 50.75(h)(1)(iv). Based on this information, the NRC staff finds that these license conditions are related to decommissioning trust agreements. Thus, the decommissioning trust requirements in 10 CFR 50.75(h),

consistent with 10 CFR 50.75(h)(5), would apply to Exelon, NMP LLC, and PSEG Nuclear with the deletion of these license conditions. Therefore, the staff finds Exelons request to delete the license conditions listed in Table 4 acceptable.

3.1.4 Condition 1d Condition 1d states:

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

Exelon proposes to delete the license conditions listed in Table 5 below. The Peach Bottom, Unit 1, license condition requires notification of the Director of the Office of Nuclear Material Safety and Safeguards instead of the Director of the Office of Nuclear Reactor Regulation. The Peach Bottom, Units 2 and 3, license conditions applicable to PSEG Nuclear do not specify a timeframe for the notification. Aside from these differences, the license conditions listed in Table 5 are equivalent to Condition 1d.

Table 5: License Conditions Equivalent to Condition 1d Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(10)(d)

Limerick, Unit 1 2.C.(19)(d)

Braidwood, Unit 2 2.C.(9)(d)

Limerick, Unit 2 2.C.(7)(d)

Byron, Unit No. 1 2.C.(20)(d)

NMP-1 2.D.(10)d Byron, Unit No. 2 2.C.(9)(d)

NMP-2 2.C.(13)d Clinton 2.C.(18)

Peach Bottom, Unit 1 2.C.(5)(d)

Dresden, Unit 1 2.C.(9)(d)

Peach Bottom, Unit 2 2.C.(5)(b)(4) and 2.C.(8)(d)

Dresden, Unit 2 2.C.(12)(d)

Peach Bottom, Unit 3 2.C.(5)(b)(4) and 2.C.(8)(d)

Dresden, Unit 3 3.T.(4)

Quad Cities, Unit 1 3.Q.(4)

FitzPatrick N/A Quad Cities, Unit 2 3.P.(4)

LaSalle, Unit 1 2.C.(40)(d)

Ginna N/A LaSalle, Unit 2 2.C.(24)(d)

The license conditions listed in Table 5 are addressed in 10 CFR 50.75(h)(1)(iii). Based on this information, the NRC staff finds that these license conditions are related to decommissioning trust agreements. Thus, the decommissioning trust requirements in 10 CFR 50.75(h),

consistent with 10 CFR 50.75(h)(5), would apply to Exelon, NMP LLC, and PSEG Nuclear with the deletion of these license conditions. Therefore, the staff finds Exelons request to delete the license conditions listed in Table 5 acceptable.

3.1.5 Condition 1e Condition 1e states:

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

Exelon proposes to delete the license conditions listed in Table 6 below, which are equivalent to Condition 1e. The Peach Bottom, Units 2 and 3, license conditions applicable to PSEG Nuclear incorrectly refer to 18 CFR 35.32(3), which does not exist, instead of 18 CFR 35.32(a)(3).

Table 6: License Conditions Equivalent to Condition 1e Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(10)(e)

Limerick, Unit 1 2.C.(19)(e)

Braidwood, Unit 2 2.C.(9)(e)

Limerick, Unit 2 2.C.(7)(e)

Byron, Unit No. 1 2.C.(20)(e)

NMP-1 2.D.(10)e Byron, Unit No. 2 2.C.(9)(e)

NMP-2 2.C.(13)e Clinton 2.C.(19)

Peach Bottom, Unit 1 2.C.(5)(e)

Dresden, Unit 1 2.C.(9)(e)

Peach Bottom, Unit 2 2.C.(5)(b)(5) and 2.C.(8)(e)

Dresden, Unit 2 2.C.(12)(e)

Peach Bottom, Unit 3 2.C.(5)(b)(5) and 2.C.(8)(e)

Dresden, Unit 3 3.T.(5)

Quad Cities, Unit 1 3.Q.(5)

FitzPatrick N/A Quad Cities, Unit 2 3.P.(5)

LaSalle, Unit 1 2.C.(40)(e)

Ginna N/A LaSalle, Unit 2 2.C.(24)(e)

The license conditions listed in Table 6 are addressed in 10 CFR 50.75(h)(1)(i)(B). Based on this information, the NRC staff finds that these license conditions are related to decommissioning trust agreements. Thus, the decommissioning trust requirements in 10 CFR 50.75(h), consistent with 10 CFR 50.75(h)(5), would apply to Exelon, NMP LLC, and PSEG Nuclear with the deletion of these license conditions. Therefore, the staff finds Exelons request to delete the license conditions listed in Table 6 acceptable.

3.1.6 Conclusion for Condition 1 As noted in Section 3.1 of this safety evaluation, each unit at Braidwood, Byron, Dresden, LaSalle, Limerick, Peach Bottom, and Quad Cities includes a license condition equivalent to Condition 1 that is applicable to Exelon. In addition, NMP-1 and NMP-2 each include a license condition equivalent to Condition 1 that is applicable to NMP LLC. These license conditions are listed in Table 7 below.

Table 7: License Conditions Equivalent to Condition 1 Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(10)

Limerick, Unit 1 2.C.(19)

Braidwood, Unit 2 2.C.(9)

Limerick, Unit 2 2.C.(7)

Byron, Unit No. 1 2.C.(20)

NMP-1 2.D.(10)

Byron, Unit No. 2 2.C.(9)

NMP-2 2.C.(13)

Clinton N/A Peach Bottom, Unit 1 2.C.(5)

Dresden, Unit 1 2.C.(9)

Peach Bottom, Unit 2 2.C.(8)

Dresden, Unit 2 2.C.(12)

Peach Bottom, Unit 3 2.C.(8)

Dresden, Unit 3 3.T Quad Cities, Unit 1 3.Q FitzPatrick N/A Quad Cities, Unit 2 3.P LaSalle, Unit 1 2.C.(40)

Ginna N/A LaSalle, Unit 2 2.C.(24)

Exelon proposes to delete the license conditions listed in Table 7 in their entirety. As discussed above, the NRC staff found it acceptable to delete each paragraph under these license conditions. Therefore, the staff finds it acceptable to delete the license conditions listed in Table 7 in their entirety. In addition, as discussed above, the staff found it acceptable to delete license conditions 2.C.(15) through (19) for Clinton, license conditions 2.C.(5)(b)(2) through (b)(5) for Peach Bottom, Units 2 and 3, and license condition 2.C.(7)(b) for Ginna.

3.2 Condition 2: Maintenance of the Decommissioning Trust The license for each facility includes one or two license conditions equivalent to Condition 2 below. The primary difference between the license conditions for each of these units is the reactor unit listed in brackets below and the applicable licensee. The FitzPatrick license condition also requires Exelon to ensure that the decommissioning trust is maintained in accordance with the order approving the transfer of decommissioning funds from PASNY to Entergy, and consistent with the safety evaluation supporting this order.

Condition 2 Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the [Braidwood, Unit 1,] license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

Table 8: License Conditions Equivalent to Condition 2 Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(11)

Limerick, Unit 1 2.C.(20)

Braidwood, Unit 2 2.C.(10)

Limerick, Unit 2 2.C.(8)

Byron, Unit No. 1 2.C.(21)

NMP-1 2.D.(11)

Byron, Unit No. 2 2.C.(10)

NMP-2 2.C.(14)

Clinton 2.C.(20)

Peach Bottom, Unit 1 2.C.(6)

Dresden, Unit 1 2.C.(10)

Peach Bottom, Unit 2 2.C.(5)(a) and 2.C.(9)

Dresden, Unit 2 2.C.(13)

Peach Bottom, Unit 3 2.C.(5)(a) and 2.C.(9)

Dresden, Unit 3 3.U Quad Cities, Unit 1 3.R FitzPatrick 2.Q Quad Cities, Unit 2 3.Q LaSalle, Unit 1 2.C.(41)

Ginna 2.C.(7)(c)

LaSalle, Unit 2 2.C.(25)

Consistent with 10 CFR 50.75(h)(5), Exelon proposes to delete the license conditions listed in Table 8. Aside from the differences noted above, these license conditions are equivalent to Condition 2. Upon the deletion of these license conditions, the provisions of 10 CFR 50.75(h) that specify the regulatory requirements for decommissioning trusts will apply to Exelon, PSEG Nuclear, NMP LLC, and Ginna LLC. As noted in Section 2.2 of this safety evaluation, 10 CFR 50.75(h)(5) provides licensees with the option of retaining their existing license conditions relating to decommissioning trust agreements or eliminating them in favor of complying with the generic requirements for decommissioning trust agreements in 10 CFR 50.75(h). Therefore, the staff finds it acceptable to delete the license conditions listed in Table 8.

3.3 Condition 3: Minimum Decommissioning Trust Funds for the License Transfer On January 12, 2001, the NRC staff issued conforming amendments for the transfer of the licenses for each unit at Braidwood, Byron, Dresden, LaSalle, Limerick, Peach Bottom, and Quad Cities to Exelon. For each unit, the conforming amendment included a license condition specifying the minimum funds Exelon was required to have in the decommissioning trust at the time the license transfer was completed. The minimum funds condition for Peach Bottom, Unit 1, was deleted by amendment dated December 26, 2002 (ADAMS Accession No. ML023650129). The remaining license conditions are listed in Table 9.

On November 7, 2001, the NRC staff issued conforming amendments for the transfer of the NMP-1 and NMP-2 licenses to NMP LLC. For each unit, the conforming amendment included a license condition requiring NMP LLC to obtain all the funds in the decommissioning trust and a parent company guarantee on the closing date of the transfer. These license conditions are listed in Table 9.

On June 10, 2004, the NRC staff issued a conforming amendment for the transfer of the Ginna license to Ginna LLC. The conforming amendment included a license condition that specified the minimum funds which Ginna LLC was to receive and deposit in the decommissioning trust for Ginna on the closing date of the license transfer. This license condition is listed in Table 9.

Exelon proposes to delete the license conditions listed in Table 9. The actions required by these license conditions were to be completed when the associated license transfers were completed. The NRC staff finds it acceptable to delete the license conditions listed in Table 9 because the associated license transfers have been completed.

Table 9: Minimum Funds License Conditions Reactor Unit License Conditions Reactor Unit License Conditions Braidwood, Unit 1 2.C.(9)

Limerick, Unit 1 2.C.(18)

Braidwood, Unit 2 2.C.(8)

Limerick, Unit 2 2.C.(6)

Byron, Unit No. 1 2.C.(19)

NMP-1 2.D.(9)

Byron, Unit No. 2 2.C.(8)

NMP-2 2.C.(12)

Clinton N/A Peach Bottom, Unit 1 N/A Dresden, Unit 1 2.C.(8)

Peach Bottom, Unit 2 2.C.(7)

Dresden, Unit 2 2.C.(11)

Peach Bottom, Unit 3 2.C.(7)

Dresden, Unit 3 3.S Quad Cities, Unit 1 3.P FitzPatrick N/A Quad Cities, Unit 2 3.O LaSalle, Unit 1 2.C.(39)

Ginna 2.C.(7)(a)

LaSalle, Unit 2 2.C.(23) 3.4 FitzPatrick License Condition 2.P Exelon proposes to delete FitzPatrick license condition 2.P, which states:

For purposes of ensuring public health and safety, Exelon Generation Company, upon the transfer of this license to it, and upon transfer of decommissioning funds from ENF to Exelon Generation Company shall provide decommissioning funding assurance for the facility, to be held in a decommissioning trust fund for the facility by the prepayment or equivalent method, of no less than the amount required under NRC regulations at 10 CFR 50.75. Any amount held in any decommissioning trust maintained by Exelon Generation Company for the facility after the transfer of the facility license to Exelon Generation Company may be credited towards the amount required under this paragraph.

The NRC staff finds that this license condition is related to decommissioning trust agreements.

The transfers mentioned in the license condition have been completed. Although Exelon transferred ownership of FitzPatrick to Exelon FitzPatrick, LLC in 2017, Exelon is responsible for the decommissioning of the facility and the associated decommissioning trust fund. Thus, the decommissioning trust requirements in 10 CFR 50.75(h), consistent with 10 CFR 50.75(h)(5),

would apply to Exelon with the deletion of this license condition. Therefore, the staff finds Exelons request to delete FitzPatrick license condition 2.P acceptable.

3.5 Peach Bottom, Units 2 and 3, License Condition 2.C.(5)(b)

For both Peach Bottom, Units 2 and 3, Exelon proposes to delete license condition 2.C.(5)(b),

which is applicable to PSEG Nuclear, in its entirety. As discussed in Section 3.1 of this safety evaluation, the NRC staff found it acceptable to delete paragraphs (2) through (5) of license condition 2.C.(5)(b). Paragraph (1) of license condition 2.C.(5)(b) states that the decommissioning trust agreement shall provide that:

The use of assets in both the qualified and nonqualified funds shall be limited to expenses related to decommissioning of the unit as defined by the NRC in its regulations and issuances, and as provided in the units license and any amendments thereto. However, upon completion of decommissioning, as defined above, the assets may be used for any purpose authorized by law.

This license condition is addressed in 10 CFR 50.75(h)(1)(iv). Based on this information, the NRC staff finds that this license condition is related to decommissioning trust agreements.

Thus, the decommissioning trust requirements in 10 CFR 50.75(h), consistent with 10 CFR 50.75(h)(5), would apply to PSEG Nuclear with the deletion of this license condition.

Therefore, the staff finds it acceptable to delete license condition 2.C.(5)(b)(1) for Peach Bottom, Units 2 and 3. Since it is acceptable to delete each paragraph of license condition 2.C.(5)(b), the staff also finds it acceptable to delete license condition 2.C.(5)(b), in its entirety, for Peach Bottom, Units 2 and 3.

3.6 NMP-1 and NMP-2 License Conditions for Intercompany Credit Agreement On November 7, 2001, the NRC staff issued conforming amendments for the transfer of the NMP-1 and NMP-2 licenses to NMP LLC. NMP-1 license condition 2.D.(12) and NMP-2 license condition 2.C.(15) required NMP LLC to enter into an intercompany credit agreement with its ultimate parent company by the time these license transfers were completed. These license conditions were superseded with the completion of an indirect license transfer of these units to EDF Development, Inc. on November 6, 2009.3 Therefore, the NRC staff finds it acceptable to delete NMP-1 license condition 2.D.(12) and NMP-2 license condition 2.C.(15).

3 See the November 13, 2009, confirmation letter and corrected order issued November 30, 2009 (ADAMS Accession Nos. ML093210182 and ML093310365, respectively).

3.7 Ginna License Condition 2.C.(7)

Exelon proposes to delete Ginna license condition 2.C.(7) in its entirety. As discussed in Sections 3.1.1, 3.2, and 3.3 of this safety evaluation, the NRC staff found it acceptable to delete each paragraph of Ginna license condition 2.C.(7). Therefore, the staff finds it acceptable to delete Ginna license condition 2.C.(7) in its entirety.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Illinois, Pennsylvania, and New York State officials were notified of the proposed issuance of the amendments on December 9, 2019.

The State officials had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments relate to changes in surety, recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

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

Principal Contributor: B. Purnell, NRR Date of issuance: April 6, 2020

Attachment:

License Conditions to be Deleted

A-1 Attachment BRAIDWOOD STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-72 LICENSE CONDITIONS TO BE DELETED Exelon Generation Company, LLC (Exelon) has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-72:

(9)

Exelon Generation Company shall have decommissioning trust funds for Braidwood, Unit 1, in the following minimum amount, when Braidwood, Unit 1, is transferred to Exelon Generation Company:

Braidwood Unit 1

$154,273,345 (10)

The decommissioning trust agreement for Braidwood, Unit 1, at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Braidwood, Unit 1, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(11)

Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Braidwood, Unit 1, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-2 BRAIDWOOD STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-77 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-77:

(8)

Exelon Generation Company, LLC, shall have decommissioning trust funds for Braidwood, Unit 2, in the following minimum amount, when Braidwood, Unit 2, is transferred to Exelon Generation Company, LLC:

Braidwood Unit 2

$154,448,967 (9)

The decommissioning trust agreement for Braidwood, Unit 2, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Braidwood, Unit 2, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(10)

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Braidwood, Unit 2, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-3 BYRON STATION, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-37 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-37:

(19)

Exelon Generation Company, LLC, shall have decommissioning trust funds for Byron, Unit 1, in the following minimum amount, when Byron, Unit 1, is transferred to Exelon Generation Company, LLC:

Byron Unit 1

$169,659,917 (20)

The decommissioning trust agreement for Byron, Unit 1, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Byron, Unit 1 must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(21)

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Byron, Unit 1, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-4 BYRON STATION, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-66 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-66:

(8)

Exelon Generation Company, LLC, shall have decommissioning trust funds for Byron, Unit 2, in the following minimum amount, when Byron, Unit 2, is transferred to Exelon Generation Company, LLC:

Byron Unit 2

$156,560,489 (9)

The decommissioning trust agreement for Byron, Unit 2, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Byron, Unit 2 must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation, 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(10)

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Byron, Unit 2, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-5 CLINTON POWER STATION, UNIT NO. 1 FACILITY OPERATING LICENSE NO. NPF-62 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Facility Operating License No. NPF-62:

(15)

The decommissioning trust agreement for CPS must be in a form acceptable to the NRC.

(16)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation, Exelon Generation Company or affiliates thereof, or their successors or assigns shall be prohibited. Except for investments tied to market indexes or other nonnuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(17)

The decommissioning trust agreement for CPS must provide that no disbursements or payments from the trust shall be made by the trustee until the trustee has first given the NRC 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the Director, Office of Nuclear Reactor Regulation.

(18)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without the prior written consent of the Director, Office of Nuclear Reactor Regulation.

(19)

The appropriate section of the decommissioning trust agreement shall reflect that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a) (3) of the Federal Energy Regulatory Commissions regulations.

(20)

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Clinton license to it and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-6 DRESDEN NUCLEAR POWER STATION, UNIT 1 FACILITY OPERATING LICENSE NO. DPR-2 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Facility Operating License No. DPR-2:

(8)

Exelon Generation Company, LLC shall have decommissioning trust funds for Dresden, Unit 1, in the following minimum amount, when Dresden, Unit 1, is transferred to Exelon Generation Company, LLC:

Dresden Unit 1

$92,836,082 (9)

The decommissioning trust agreement for Dresden, Unit 1, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Dresden, Unit 1, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation, 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(10)

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Dresden, Unit 1, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-7 DRESDEN NUCLEAR POWER STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-19 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. DPR-19:

(11)

Exelon Generation Company, LLC shall have decommissioning trust funds for Dresden, Unit 2, in the following minimum amount, when Dresden, Unit 2, is transferred to Exelon Generation Company, LLC:

Dresden, Unit 2

$288,233,336 (12)

The decommissioning trust agreement for Dresden, Unit 2, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Dresden, Unit 2, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(13)

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Dresden, Unit 2, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-8 DRESDEN NUCLEAR POWER STATION, UNIT 3 RENEWED FACILITY OPERATING LICENSE NO. DPR-25 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 3 of Renewed Facility Operating License No. DPR-25:

S.

Exelon Generation Company, LLC shall have decommissioning trust funds for Dresden.

Unit 3, in the following minimum amount, when Dresden, Unit 3, is transferred to Exelon Generation Company, LLC:

Dresden, Unit 3

$262,231,719 T.

The decommissioning trust agreement for Dresden, Unit 3, at the time the transfer of the unit to Exelon Generation Company, LLC is effected and thereafter, is subject to the following:

(1) The decommissioning trust agreement must be in a form acceptable to the NRC.

(2)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(3) The decommissioning trust agreement for Dresden, Unit 3, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(4) The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(5) The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

U.

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Dresden, Unit 3, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-9 JAMES A. FITZPATRICK NUCLEAR POWER PLANT RENEWED FACILITY OPERATING LICENSE NO. DPR-59 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2 of Renewed Facility Operating License No. DPR-59:

P.

For purposes of ensuring public health and safety, Exelon Generation Company, upon the transfer of this license to it, and upon transfer of decommissioning funds from ENF to Exelon Generation Company shall provide decommissioning funding assurance for the facility, to be held in a decommissioning trust fund for the facility by the prepayment or equivalent method, of no less than the amount required under NRC regulations at 10 CFR 50.75. Any amount held in any decommissioning trust maintained by Exelon Generation Company for the facility after the transfer of the facility license to Exelon Generation Company may be credited towards the amount required under this paragraph.

Q.

Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for the transfer of this license to Exelon Generation Company, and the requirements of the order approving the transfer and order approving the transfer of decommissioning funds from PASNY to Entergy Nuclear Operations, Inc., and consistent with the safety evaluations supporting such orders.

A-10 LASALLE COUNTY STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-11 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-11:

(39)

Exelon Generation Company, LLC shall have decommissioning trust funds, for LaSalle Unit 1, in the following minimum amount, when LaSalle, Unit 1, is transferred to Exelon Generation Company, LLC:

LaSalle, Unit 1

$226,262,522 (40)

The decommissioning trust agreement for LaSalle, Unit 1, at the time the transfer of the unit to Exelon Generation Company (EGC), LLC is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for LaSalle, Unit 1, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation, 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(41)

Exelon Generation Company, LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the LaSalle, Unit 1, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-11 LASALLE COUNTY STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-18 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-18:

(23)

EGC shall have decommissioning trust funds for LaSalle, Unit 2, in the following minimum amount, when LaSalle, Unit 2, is transferred to EGC:

LaSalle, Unit 2

$221,885,059 (24)

The decommissioning trust agreement for LaSalle, Unit 2, at the time the transfer of the unit to EGC is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for LaSalle, Unit 2, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation, 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(25)

EGC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the LaSalle, Unit 2, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-12 LIMERICK GENERATING STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. NPF-39 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-39:

(18)

Exelon Generation Company shall have decommissioning trust funds for Limerick, Unit 1, in the following minimum amount, when Limerick, Unit 1, is transferred to Exelon Generation Company:

Limerick, Unit 1

$94,127,446 (19)

The decommissioning trust agreement for Limerick, Unit 1, at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Limerick, Unit 1, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(20)

Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of Limerick, Unit 1, renewed license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-13 LIMERICK GENERATING STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-85 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-85:

(6)

Exelon Generation Company shall have decommissioning trust funds for Limerick, Unit 2, in the following minimum amount, when Limerick, Unit 2, is transferred to Exelon Generating Company:

Limerick, Unit 2

$59,687,081 (7)

The decommissioning trust agreement for Limerick, Unit 2, at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:

(a)

The decommissioning trust agreement must be in a form acceptable to the NRC.

(b)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c)

The decommissioning trust agreement for Limerick, Unit 2, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(8)

Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of Limerick, Unit 2, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-14 NINE MILE POINT NUCLEAR STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-63 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.D of Renewed Facility Operating License No. DPR-63:

(9)

On the closing date of the transfer of Nine Mile Point Nuclear Station, Unit No. 1 (NMP-1) to it, NMP LLC shall: (1) obtain from the transferor all of its accumulated decommissioning trust funds for NMP-1, and (2) receive a parent company guarantee pursuant to 10 CFR 50.75(e)(1) (iii)(B) (to be updated annually) in a form acceptable to the NRC and in an amount which, when combined with the decommissioning trust funds for NMP-1, equals or exceeds the total amount required for NMP-1 pursuant to 10 CFR 50.75(b) and (c).

(10)

The decommissioning trust agreement for NMP-1, at the time any subject direct transfer is effected and thereafter, is subject to the following:

a.

The decommissioning trust agreement must be in a form acceptable to the NRC.

b.

With respect to the decommissioning trust funds, investments in the securities or other obligations of Constellation Energy Group, Inc., New Controlled, or their affiliates, successors, or assigns, are and shall be prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are and shall be prohibited.

c.

The decommissioning trust agreement must provide that no disbursements or payments from the trusts, other than for ordinary administrative expenses, shall be made by the trustee unless the trustee has first given the NRC 30 days prior written notice of the payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trusts shall be made if the trustee receives prior written notice of objection from the Director of the Office of Nuclear Reactor Regulation.

d.

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

e.

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trusts shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(11)

NMP LLC shall take all necessary steps to ensure that the decommissioning trusts are maintained in accordance with the Application for approval of the transfer of the NMP-1 license to NMP LLC (Application), the requirements of the Order approving the transfer, and the related safety evaluation.

A-15 (12)

At the time of the transfer of NMP-1 to NMP LLC, NMP LLC shall enter or shall have entered into an intercompany credit agreement with Constellation Energy Group (CEG),

Inc. or New Controlled, whichever entity is the ultimate parent of NMP LLC at that time, in the form and on the terms represented in the Application for license transfer. Should New Controlled become the ultimate parent of NMP LLC following the direct transfer of the license to NMP LLC, NMP LLC shall enter or shall have entered into a substantially identical intercompany credit agreement with New Controlled at the time New Controlled becomes the ultimate parent; in such case, any existing intercompany credit agreement with CEG, Inc. may be canceled once the intercompany credit agreement with New Controlled is established. Except as otherwise provided above, NMP LLC shall take no action to void, cancel, or modify any intercompany credit agreement referenced above, without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.

A-16 NINE MILE POINT NUCLEAR STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-69 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. NPF-69:

(12)

On the closing date(s) of the transfer of the NMPC, RG&E, CHGEC, and NYSEG interests in NMP-2 to it, Nine Mile Point Nuclear Station, LLC shall: (1) obtain from the transferors then transferring their interests all of their accumulated decommissioning trust funds for NMP-2, and (2) receive a parent company guarantee pursuant to 10 CFR 50.75(e)(1)(iii)(B) (to be updated annually) in a form acceptable to the NRC and in an amount which, when combined with the decommissioning trust funds for NMP-2 that have been transferred, equals or exceeds the total amounts for NMP LLCs then resulting total ownership share of NMP-2, respectively, pursuant to 10 CFR 50.75(b) and (c).

(13)

The decommissioning trust agreement for NMP-2, at the time any subject direct transfer is effected and thereafter, is subject to the following:

a.

The decommissioning trust agreement must be in a form acceptable to the NRC.

b.

With respect to the decommissioning trust funds, investments in the securities or other obligations of Constellation Energy Group, Inc., New Controlled, or their affiliates, successors, or assigns, are and shall be prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are and shall be prohibited[.]

c.

The decommissioning trust agreement must provide that no disbursements of payments from the trusts, other than for ordinary administrative expenses, shall be made by the trustee unless the trustee has given the NRC 30 days prior written notice of the payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trusts shall be made if the trustee receives prior written notice of objection from the Director of the Office of Nuclear Reactor Regulation.

d.

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

e.

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trusts shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

A-17 (14)

NMP LLC shall take all necessary steps to ensure that the decommissioning trusts are maintained in accordance with the Application for approval of the transfer of the Unit 2 license to NMP LLC (Application), the requirements of the Order approving the transfer, and the related safety evaluation.

(15)

At the time any subject direct transfer is effected, NMP LLC shall enter or shall have entered into an intercompany credit agreement with Constellation Energy Group (CEG),

Inc., or New Controlled, whichever entity is the ultimate parent of NMP LLC at that time, in the form and on the terms represented in the Application for license transfer. Should New Controlled become the ultimate parent of NMP LLC following the direct transfer of the license to NMP LLC, NMP LLC shall enter or shall have entered into a substantially identical intercompany credit agreement with New Controlled at the time New Controlled becomes the ultimate parent; in such case, any existing intercompany credit agreement with CEG, Inc. may be canceled once the intercompany credit agreement with New Controlled is established. Except as otherwise provided above, NMP LLC shall take no action to void, cancel, or modify any intercompany credit agreement referenced above, without the prior written consent of the Director of the Office of Nuclear Reactor Regulation.

A-18 PEACH BOTTOM ATOMIC POWER STATION, UNIT 1 FACILITY OPERATING LICENSE NO. DPR-12 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Facility Operating License No. DPR-12:

(5)

The decommissioning trust agreement for Peach Bottom, Unit 1 at the time the transfer of the unit to Exelon Generation Company, LLC is effected and, thereafter, is subject to the following:

(a) The decommissioning trust agreement must be in a form acceptable to the NRC.

(b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(c) The decommissioning trust agreement for Peach Bottom, Unit 1, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Material Safety and Safeguards 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objections from the NRC.

(d) The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Material Safety and Safeguards.

(e) The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(6)

Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Peach Bottom, Unit 1, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-19 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-44 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Subsequent Renewed Facility Operating License No. DPR-44:

(5)(a) PSEG Nuclear shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application, the requirements of the Order Approving Transfer of License and Conforming Amendment, dated August 21, 2000, and the related Safety Evaluation dated February 16, 2000.

(5)(b) The decommissioning trust agreement shall provide that:

1)

The use of assets in both the qualified and nonqualified funds shall be limited to expenses related to decommissioning of the unit as defined by the NRC in its regulations and issuances, and as provided in the units license and any amendments thereto. However, upon completion of decommissioning, as defined above, the assets may be used for any purpose authorized by law.

2)

Investments in the securities or other obligations of PSE&G or affiliates thereof, or their successors or assigns, shall be prohibited. In addition, except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants shall be prohibited.

3)

No disbursements or payments from the trust shall be made by the trustee until the trustee has first given the NRC 30 days notice of the payment. In addition, no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the Director, Office of Nuclear Reactor Regulation.

4)

The trust agreement shall not be modified in any material respect without prior written notification to the Director, Office of Nuclear Reactor Regulation.

5)

The trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(3) of the Federal Energy Regulatory Commissions regulations.

(7)

Exelon Generation Company shall have decommissioning trust funds for Peach Bottom, Unit 2, in the following minimum amount, when Peach Bottom, Unit 2, is transferred to Exelon Generation Company:

Peach Bottom, Unit 2

$71,250,231

A-20 (8)

The decommissioning trust agreement for Peach Bottom, Unit 2, at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:

(a) The decommissioning trust agreement must be in a form acceptable to the NRC.

(b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns shall be prohibited. Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants shall be prohibited.

(c) The decommissioning trust agreement for Peach Bottom, Unit 2, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director, Office of Nuclear Reactor Regulation, 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d) The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e) The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(9)

Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Peach Bottom, Unit 2, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-21 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-56 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Subsequent Renewed Facility Operating License No. DPR-56:

(5)(a) PSEG Nuclear, shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application, the requirements of the Order Approving Transfer of License and Conforming Amendment, dated August 21, 2000, and the related Safety Evaluation dated February 16, 2000.

(5)(b) The decommissioning trust agreement shall provide that:

1)

The use of assets in both the qualified and nonqualified funds shall be limited to expenses related to decommissioning of the unit as defined by the NRC in its regulations and issuances, and as provided in the units license and any amendments thereto. However, upon completion of decommissioning, as defined above, the assets may be used for any purpose authorized by law.

2)

Investments in the securities or other obligations of PSE&G or affiliates thereof, or their successors or assigns, shall be prohibited. In addition, except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants shall be prohibited.

3)

No disbursements or payments from the trust shall be made by the trustee until the trustee has first given the NRC 30 days notice of the payment. In addition, no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the Director, Office of Nuclear Reactor Regulation.

4)

The trust agreement shall not be modified in any material respect without prior written notification to the Director, Office of Nuclear Reactor Regulation.

5)

The trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(3) of the Federal Energy Regulatory Commissions regulations.

(7)

Exelon Generation Company shall have decommissioning trust funds for Peach Bottom, Unit No. 3, in the following minimum amount, when Peach Bottom, Unit No. 3, is transferred to Exelon Generation Company:

Peach Bottom, Unit No. 3

$73,497,654

A-22 (8)

The decommissioning trust agreement for Peach Bottom, Unit No. 3, at the time the transfer of the unit to Exelon Generation Company is effected and thereafter, is subject to the following:

(a) The decommissioning trust agreement must be in a form acceptable to the NRC.

(b) With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns shall be prohibited. Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants shall be prohibited.

(c) The decommissioning trust agreement for Peach Bottom, Unit No. 3, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(d) The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(e) The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

(9)

Exelon Generation Company shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Peach Bottom, Unit No. 3, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-23 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-29 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 3 of Renewed Facility Operating License No. DPR-29:

P.

EGC shall have decommissioning trust funds for Quad Cities, Unit 1, in the following minimum amount, when Quad Cities, Unit 1, is transferred to EGC:

Quad Cities, Unit 1

$192,149,504 Q.

The decommissioning trust agreement for Quad Cities, Unit 1, at the time of the transfer of the unit to EGC is effected and thereafter, is subject to the following:

(1) The decommissioning trust agreement must be in a form acceptable to the U.S. Nuclear Regulatory Commission (NRC).

(2) With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(3)

The decommissioning trust agreement for Quad Cities, Unit 1, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(4)

The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(5)

The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

R.

EGC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Quad Cities, Unit 1, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-24 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 RENEWED FACILITY OPERATING LICENSE NO. DPR-30 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 3 of Renewed Facility Operating License No. DPR-30:

O.

EGC shall have decommissioning trust funds for Quad Cities, Unit 2, in the following minimum amount, when Quad Cities, Unit 2, is transferred to EGC:

Quad Cities, Unit 2

$193,209,439 P.

The decommissioning trust agreement for Quad Cities, Unit 2, at the time of the transfer of the unit to EGC is effected and thereafter, is subject to the following:

(1) The decommissioning trust agreement must be in a form acceptable to the U.S. Nuclear Regulatory Commission (NRC).

(2)

With respect to the decommissioning trust fund, investments in the securities or other obligations of Exelon Corporation or affiliates thereof, or their successors or assigns are prohibited. Except for investments tied to market indexes or other non-nuclear sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.

(3) The decommissioning trust agreement for Quad Cities, Unit 2, must provide that no disbursements or payments from the trust shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.

(4) The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.

(5) The appropriate section of the decommissioning trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commissions regulations.

Q.

EGC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application for approval of the transfer of the Quad Cities, Unit 2, license and the requirements of the Order approving the transfer, and consistent with the safety evaluation supporting the Order.

A-25 R. E. GINNA NUCLEAR POWER PLANT RENEWED FACILITY OPERATING LICENSE NO. DPR-18 LICENSE CONDITIONS TO BE DELETED Exelon has requested the deletion of the following license conditions from Section 2.C of Renewed Facility Operating License No. DPR-18:

(7)

License Transfer (a) On the closing date of the transfer of the facility, Ginna LLC shall obtain from RG&E the greater of (1) $200,791,928 or (2) the amount necessary to meet the minimum formula amount under 10 CFR 50.75 calculated as of the date of closing for decommissioning funding assurance for the facility, and ensure the deposit of such funds into a decommissioning trust for the facility established by Ginna LLC.

(b) The decommissioning trust agreement must be in a form acceptable to the NRC.

(c) Ginna LLC shall take all necessary steps to ensure that the decommissioning trust is maintained in accordance with the application and the requirements of the Order approving license transfer, and shall be consistent with the Safety Evaluation supporting that Order.

ML20021A070

• by email OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NMSS/REFS/FAB/BC*

OGC NLO*

NAME BPurnell SRohrer (JBurkhardt for) FMiller JWachutka DATE 03/23/2020 02/20/2020 01/16/2020 03/06/2020 OFFICE NMSS/DUWP/RDB/BC NRR/DORL/LPL3/BC*

NRR/DORL/LPL3/PM NAME BWatson NSalgado (SWall for)

BPurnell DATE 03/10/2020 03/20/2020 04/06/2020