Text

2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements
	ML18304A365
Person / Time
Site:	Dresden, Peach Bottom, Nine Mile Point, Limerick, Clinton, Quad Cities, FitzPatrick, LaSalle
Issue date:	01/16/2019
From:	Blake Purnell; Plant Licensing Branch III
To:	Bryan Hanson; Exelon Generation Co, Exelon Nuclear
	Purnell B
References
	EPID L-2018-LLA-0167
	Download: ML18304A365 (93)
	v • d • e

Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 16, 2019 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; JAMES A. FITZPATRICK NUCLEAR POWER PLANT; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; PEACH BOTIOM ATOMIC POWER STATION, UNITS 2 AND 3; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO REVISE THE AVERAGE POWER RANGE MONITOR REQUIREMENTS (EPID L-2018-LLA-0167)

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, the licensee) application dated June 15, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18166A197):

1.

Amendment No. 222 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No. 1;

2.

Amendment No. 260 to Renewed Facility Operating License No. DPR-19 and Amendment No. 253 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, respectively;

3.

Amendment No. 324 to Renewed Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant;

4.

Amendment No. 234 to Renewed Facility Operating License No. NPF-11 and Amendment No. 220 to Renewed Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2, respectively;

5.

Amendment No. 233 to Renewed Facility Operating License No. NPF-39 and Amendment No. 196 to Renewed Facility Operating License No. NPF-85 for the Limerick Generating Station, Units 1 and 2, respectively;

6.

Amendment No. 235 to Renewed Facility Operating License No. DPR-63 and Amendment No. 175 to Renewed Facility Operating License No. NPF-69 for the Nine Mile Point Nuclear Station, Units 1 and 2, respectively;

7.

Amendment No. 322 to Renewed Facility Operating License No. DPR-44 and Amendment No. 325 to Renewed Facility Operating License No. DPR-56 for the Peach Bottom Atomic Power Station, Units 2 and 3, respectively; and

8.

Amendment No. 272 to Renewed Facility Operating License No. DPR-29 and Amendment No. 267 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendments revise the average power range monitor requirements in the technical specifications for each facility.

A copy of the NRC staff's Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Docket Nos. 50-461, 50-237, 50-249, 50-333, 50-373, 50-37 4, 50-352, 50-353, 50-220, 50-410, 50-277, 50-278, 50-254, and 50-265

Enclosures:

1. Amendment No. 222 to NPF-62

2. Amendment No. 260 to DPR-19

3. Amendment No. 253 to DPR-25

4. Amendment No. 324 to DPR-59

5. Amendment No. 234 to NPF-11

6. Amendment No. 220 to NPF-18

7. Amendment No. 233 to NPF-39

8. Amendment No. 196 to NPF-85

9. Amendment No. 235 to DPR-63

10. Amendment No. 175 to NPF-69

11. Amendment No. 322 to DPR-44

12. Amendment No. 325 to DPR-56

13. Amendment No. 272 to DPR-29

14. Amendment No. 267 to DPR-30

15. Safety Evaluation cc: Listserv Sincerely,

!!/,

Blake Purnell, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY. LLC DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 222 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2.

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

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 222, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 0~.

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David J. Wrona, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance: January 1 6, 2 O 1 9

ATIACHMENT TO LICENSE AMENDMENT NO. 222 FACILITY OPERATING LICENSE NO. NPF-62 CLINTON POWER STATION, UNIT NO. 1 DOCKET NO. 50-461 Replace the following pages of the Facility Operating License and Appendix A, Technical Specifications (TSs ), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License NPF-62 Page 3 TSs 3.3-1 3.3-3 License NPF-62 Page 3 TSs 3.3-1 3.3-3 (4)

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

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

Exelon Generation Company, pursuant to the Act and 1 O CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation; and (7)

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

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 O CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

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

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 222, are hereby incorporated into this license.

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

Amendment No. 222

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO

3. 3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS

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

1.

Separate Condition entry is allowed for each Function. *

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at A.

B.

C.

D.

2 21.6% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION REQUIRED ACTION COMPLETION TIME One or more Functions A. l Place one channel in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months with one channel affected Function in inoperable.

trip.

One or more Functions B.l Place one channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with two channels affected Function in inoperable.

trip.

One or more Functions C. l Restore two channels 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with three or more in affected Function channels inoperable.

to OPERABLE status.

Required Action and D.l Enter the Condition Immediately associated Completion referenced in Time of Condition A, Table 3.3.1.1-1 for B, or C not met.

the channel.

(continued)

CLINTON 3.3-1 Amendment No. 222

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SR 3.3.1.1.1 SR 3. 3. 1. 1. 2 SR 3.3.1.1.3 SR 3.3.1.1.4 CLINTON SURVEILLANCE Perform CHANNEL CHECK.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER~ 21.6% RTP.

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at~ 21.6% RTP.

Adjust the channel to conform to a calibrated flow signal.

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

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

3.3-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Amendment No. 222

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 260 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

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

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 260, are hereby incorporated into this renewed operating license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION C)cC 9 n/_

David J. Wrona, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

Janu3.ry 1 6, 201 9

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 253 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended {the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2.

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

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 253, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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~id J. Wrona, 9/a~ch Chi~------*

Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 1 6, 201 9

ATTACHMENT TO LICENSE AMENDMENT NOS. 260 AND 253 RENEWED FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 DOCKET NOS. 50-237 AND 50-249 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License DPR-19 Page 3 License DPR-25 Page 4 TSs 3.3.1.1-1 3.3.1.1-4 License DPR-19 Page 3 License DPR-25 Page 4 TSs 3.3.1.1-1 3.3.1.1-4 (2)

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

Exelon Generation Company, LLC, pursuant to the Act and 1 O CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

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

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

C.

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

(1)

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

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 260, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3)

Operation in the coastdown mode is permitted to 40% power.

Renewed License No. DPR-19 Amendment No. 260

f.

Surveillance Requirement 4.9.A.10 - Diesel Storage Tank Cleaning (Unit 3 and Unit 2/3 only)

Each of the above Surveillance Requirements shall be successfully demonstrated prior to entering into MODE 2 on the first plant startup following the fourteenth refueling outage (D3R14).

3.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

A.

Maximum Power Level The licensee is authorized to operate the facility at steady state power levels not in excess of 2957 megawatts (thermal), except that the licensee shall not operate the facility at power levels in excess of five (5) megawatts (thermal), until satisfactory completion of modifications and final testing of the station output transformer, the auto-depressurization interlock, and the feedwater system, as described in the licensee's telegrams; dated February 26, 1971, have been verified in writing by the Commission.

B.

Technical Specifications C.

The Technical Specifications contained in Appendix A, as revised through Amendment No. 253, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.

D.

Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.

E.

Restrictions Operation in the coastdown mode is permitted to 40% power.

Renewed License No. DPR-25 Amendment No. 253

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS

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

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at A.

B.

~ 25% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION REQUIRED ACTION COMPLETION TIME One or more required A.l Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

trip.

OR A.2 Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

One or more Functions B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more trip system in trip.

required channels inoperable in both OR trip systems.

B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

(continued)

Dresden 2 and 3 3.3.1.1-1 Amendment No. 260/253

SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 Dresden 2 and 3 SURVEILLANCE Perform CHANNEL CHECK.

FREQUENCY In accordance with the Surveillance Frequency Control Program

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

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

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at~ 25% RTP.

Adjust the channel to conform to a calibrated flow signal.

3.3.1.1-4 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Amendment No. 260/253

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 324 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-59 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 324, are hereby incorporated in the renewed operating license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION C,t-1 n_ n1_.

David J. Wrona, i~ch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 1 6, 201 9

ATTACHMENT TO LICENSE AMENDMENT NO. 324 RENEWED FACILITY OPERATING LICENSE NO. DPR-59 JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License DPR-59 Page 3 TSs 3.3.1.1-1 3.3.1.1-3 License DPR-59 Page 3 TSs 3.3.1.1-1 3.3.1.1-3 (4)

Exelon Generation Company pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use, at any time, any byproduct, source and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration; or associated with radioactive apparatus, components or tools.

(5)

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

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Exelon Generation Company is authorized to operate the facility at steady state reactor core power levels not in excess of 2536 megawatts (thermal).

(2)

Technical Specifications (3)

The Technical Specifications contained in Appendix A, as revised through Amendment No. 324, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

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

135 (dated September 5, 1989), 142 (dated October 23, 1989), 164 (dated August 10, 1990), 176 (dated January 16, 1992), 177 (dated February 10, 1992), 186 (dated February 19, 1993), 190 (dated June 29, 1993), 191 (dated July 7, 1993), 206 (dated February 28, 1994), and 214 (dated June 27, 1994); and NRC Exemptions and associated safety evaluations dated April 26, 1983, July 1, 1983, January 11, 1985, Amendment 324 Renewed License No. DPR-59

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO

3. 3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS

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

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at A.

B.

~ 25% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION REQUIRED ACTION COMPLETION TIME One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

trip.

OR A.2 Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

One or more Functions B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more trip system in trip.

required channels inoperable in both OR trip systems.

B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

(continued)

JAFNPP 3.3.1.1-1 Amendment 324

SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performanceof required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE SR 3.3.1.1.1 Perform CHANNEL CHECK.

SR 3.3.1.1.2

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

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

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at~ 25% RTP.

SR 3.3.1.1.3

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

Not required to be performed when entering MODE 2 from MODE luntil 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.1.1.4 Perform a functional test of each RPS automatic scram contactor.

JAFNPP 3.3.1.1-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Survei 11 ance Frequency Control Program (continued)

Amendment 324

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY. LLC DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 234 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2.

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

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 234, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

./-)

~

' 2 /

i

. l '

() /

L-L~

1 ----

David J. Wrona, B ~ch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 1 6, 201 9

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 220 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2.

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

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 220, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION QkL. ~~ch rt--

Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

ATTACHMENT TO LICENSE AMENDMENT NOS. 234 AND 220 RENEWED FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-37 4 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications {TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License NPF-11 Page 3 License NPF-18 Page 3 TSs 3.3.1.1-1 3.3.1.1-3 License NPF-11 Page 3 License NPF-18 Page 3 TSs 3.3.1.1-1 3.3.1.1-3

Am. 146 01/12/01 Am. 202 07/21/11 Am. 198 09/16/10 Renewed License No. NPF-11 (3)

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

(5)

Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class Band Class Clow-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 1 O CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

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

Am. 234 01/16/19 (2)

Technical Specifications and Environmental Protection Plan Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 (3)

(4)

(5)

The Technical Specifications contained in Appendix A, as revised through Amendment No. 234, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

DELETED DELETED DELETED Amendment No. 234

Am. 189 07/21/11 Am. 185 09/16/10 Renewed License No. NPF-18 (2)

Pursuant to the Act and 1 O CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)

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

Pursuant to the Act and 1 O CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

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

C.

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

(1)

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

Am. 220 01/16/19 (2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 220, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 220

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS NOTES - - -- - - - - - - - - - - -- - -- - - - -- - - -- - - - - - - - -

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at A.

B.

~ 25% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION REQUIRED ACTION COMPLETION TIME One*or more required A.l Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

trip.

OR A.2 Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

One or more Functions B.l Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more trip system in trip.

required channels inoperable in both OR trip systems.

B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

(continued)

LaSalle 1 and 2 3.3.1.1-1 Amendment No. 234/220

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS NOTES - - - - - - - - -- - - - - - - - - - - -- - - -- - - - - - - - - - -

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 LaSalle 1 and 2 SURVEILLANCE FREQUENCY Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program

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

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

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at~ 25% RTP.

Adjust the channel to conform to a calibrated flow signal.

3.3.1.1-3 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Amendment No. 234/220

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 233 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-39 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 233, are hereby incorporated into this renewed license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION C\\ )L_l 9 o/_

David J. Wrona, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

ATTACHMENT TO LICENSE AMENDMENT NO. 233 RENEWED FACILITY OPERATING LICENSE NO. NPF-39 LIMERICK GENERATING STATION, UNIT 1 DOCKET NO. 50-352 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications {TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License NPF-39 Page 3 TSs 3/4 3-1 3/4 3-8 License NPF-39 Page 3 TSs 3/4 3-1 3/4 3-8 (2)

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

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

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

Pursuant to the Act and 1 O CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

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

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 233, are hereby incorporated into this renewed license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. NPF-39 Amendment No. 233

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY:

As shown in Table 3.3.1-1.

ACTION:

Note:

Separate condition entry is allowed for each channel.

Note:

When Functional Unit 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% of RATED THERMAL POWER while operating at~ 25% of RATED THERMAL POWER, entry into the associated Actions may be delayed up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

a.

With the number of OPERABLE channels in either trip system for one or more Functional Units less than the Minimum OPERABLE Channels per Trip System required by Table 3.3.1-1, within one hour for each affected functional unit either verify that at least one* channel in each trip system is OPERABLE or tripped or that the trip system is tripped, or place either the affected trip system or at least one inoperable channel in the affected trip system in the tripped condition.

b.

With the number of OPERABLE channels in either trip system less than the Minimum OPERABLE Channels per Trip System required by Table 3.3.1-1, place either the inoperable channel (s) or the affected trip system** in the tripped conditions within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the number of OPERABLE channels in both trip systems for one or more Functional Units less than the Minimum OPERABLE Channels per Trip System required by Table 3.3.1-1, place either the inoperable channel(s) in one trip system or one trip system in the tripped condition within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s**.

d.

lf within the allowable time allocated by Actions a, b or c, it is not desired to place the inoperable channel or trip system in trip (e.g., full scram would occur), Then no later than expiration of that allowable time initiate the action identified in Table 3.3.1-1 for the applicable Functional Unit.

For Functional Units 2.a, 2.b, 2.c, 2.d, and 2.f, at least two channels shall be OPERABLE or tripped.

For Functional Unit 5, both trip systems shall have each channel associated with the MSIVs in three main steam lines (not necessarily the same main steam lines for both trip systems) OPERABLE or tripped.

For Function 9, at least three channels per trip system shall be OPERABLE or tripped.

- For Functional Units 2.a, 2.b, 2.c, 2.d, and 2.f, inoperable channels shall be placed in the tripped condition to comply with Action b.

Action c does not apply for these Functional Units.

LIMERICK - UNIT 1 3/4 3-1 Amendment No. ~. A-, +/-4+-, 1-7+-, 200, 219, 233 I

TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UN IT

9.

10.

11.

12.

Turbine Stop Valve - Closure Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Reactor Mode Switch Shutdown Position Manual Scram CHANNEL CHECK(n)

N.A.

CHANNEL FUNCTIONAL TEST(n)

(a)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

CHANNEL CALIBRATION(a)(n)

N.A.

OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED 1

1 1, 2, 3, 4, 5 1, 2, 3, 4, 5 (b)

The IRM and SRM channels shall be determined to overlap for at least 1/2 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 1/2 decades during each controlled shutdown, if not performed within the previous 7 days.

(c)

Calibration includes verification that the OPRM Upscale trip auto-enable (not-bypass) setpoint for APRM Simulated Thermal Power is~ 29.5% and for recirculation drive flow is< 60%.

(d)

The more frequent calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER ~25% of RATED THERMAL POWER.

Verify the calculated power does not exceed the APRM channels by greater than 2% of RATED THERMAL POWER.

(e)

CHANNEL FUNCTIONAL TEST shall include the flow input function, excluding the flow transmitter.

(f)

The LPRMs shall be calibrated at least once per 2000 effective full power hours (EFPH).

(g)

The less frequent calibration includes the flow input function.

(h)

This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(i)

With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(j)

If the RPS shorting links are required to be removed per Specification 3.9.2, they may be reinstalled for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance.

During this time, CORE ALTERATIONS shall be suspended, and no control rod shall be moved from its existing position.

( k)

DELETED (1)

Not required to be performed when entering OPERATIONAL CONDITION 2 from OPERATIONAL CONDITION 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2.

(m)

With THERMAL POWER~ 25% of RATED THERMAL POWER.

(n)

Frequencies are specified in the Surveillance Frequency Control Program unless otherwise noted in the table.

LIMERICK - UNIT 1 3/4 3-8 N

29 H 53 '66' Amendment77 °igi:iQs.. 2Ql.233 ll~all7.l~lzl41,l I

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 196 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-85 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 196, are hereby incorporated into this renewed license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Ou 2 o/_

David J. Wrona, Br ch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 1 6, 201 9

ATTACHMENT TO LICENSE AMENDMENT NO. 196 RENEWED FACILITY OPERATING LICENSE NO. NPF-85 LIMERICK GENERATING STATION, UNIT 2 DOCKET NO. 50-353 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License NPF-85 Page 3 TSs 3/4 3-1 3/4 3-8 License NPF-85 Page 3 TSs 3/4 3-1 3/4 3-8 (2)

Pursuant to the Act and 1 O CFR Part 70, to receive, possess and to use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3)

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

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

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility, and to receive and possess, but not separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Exelon Generation Company is authorized to operate the facility at reactor core power levels of 3515 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 196, are hereby incorporated into this renewed license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. NPF-85 Amendment No. 196

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY:

As shown in Table 3.3.1-1.

ACTION:

Note:

Separate condition entry is allowed for each channel.

Note:

When Functional Unit 2.b and 2.c channels are inoperable due the calculated power exceeding the APRM output by more than 2% of RATED THERMAL POWER while operating at~ 25% of RATED THERMAL POWER, entry into the associated Actions may be delayed up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

a.

With the number of OPERABLE channels in either trip system for one or more Functional Units less than the Minimum OPERABLE Channels per Trip System required by Table 3.3.1-1, within one hour for each affected functional unit either verify that at least one* channel in each trip system is OPERABLE or tripped or that the trip system is tripped, or place either the affected trip system or at least one inoperable channel in the affected trip system in the tripped condition.

b.

With the number of OPERABLE channels in either trip system less than the Minimum OPERABLE Channels per Trip System required by Table 3.3.1-1, place either the inoperable channel(s) or the affected trip system** in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the number of OPERABLE channels in both trip systems for one or more Functional Units less than the Minimum OPERABLE Channels per Trip System required by Table 3.3.1-1, place either the inoperable channel(s) in one trip system or one trip system in the tripped condition within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s**.

d.

lf within the allowable time allocated by Actions a, b or c, it is not desired to place the inoperable channel or trip system in trip (e.g., full scram would occur), Then no later than expiration of that allowable time initiate the action identified in Table 3.3.1-1 *for the applicable Functional Unit.

For Functional Units 2.a, 2.b, 2.c, 2.d, and 2.f, at least two channels shall be OPERABLE or tripped.

For Functional Unit 5, both trip systems shall have each channel associated with the MSIVs in three main steam lines (not necessarily the same main steam lines for both trip systems) OPERABLE or tripped.

For Function 9, at least three channels per trip system shall be OPERABLE or tripped.

- For Functional Units 2.a, 2.b, 2.c, 2.d, and 2.f, inoperable channels shall be placed in the tripped condition to comply with Action b.

Action c does not apply for these Functional Units.

LIMERICK - UNIT 2 3/4 3-1 Amendment No. 17,a4,109,la9,lgl,l96

TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUN CTI ONA L UN IT CHANNEL CHECK Cn)

CHANNEL FUNCTIONAL TEST Cn)

CHANNEL CALIBRATIONCa)Cn)

OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED

9.

10.

11.

12.

(a)

(b)

( C)

(d)

(e)

(f)

(g)

( h)

( i )

( j)

( k)

( l )

(m)

( n)

Turbine Stop Valve - Closure Turbine Control Valve Fast Closure, Trip Oil Pressure - Low Reactor Mode Switch Shutdown Position Manual Scram N.A.

N.A.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

N.A.

1 1

l, 2, 3, 4, 5 1, 2, 3, 4, 5 The IRM and SRM channels shall be determined to overlap for at least 1/2 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for a least 1/2 decades during each controlled shutdown, if not performed within the previous 7 days.

Calibration includes verification that the OPRM Upscale trip auto-enable (not-bypass) setpoint for APRM Simulated Thermal Power is~ 29.5% and for recirculation drive flow is< 60%.

The more frequent calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER~ 25% of RATED THERMAL POWER.

Verify the calculated power does not exceed the APRM channels by greater than 2% of RATED THERMAL POWER.

CHANNEL FUNCTIONAL TEST shall include the flow input function, excluding the flow transmitter.

The LPRMs shall be calibrated at least once per 2000 effective full power hours (EFPH).

The less frequent calibration includes the flow input function.

This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

If the RPS shorting links are required to be removed per Specification 3.9.2, they may be reinstalled for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance.

During this time, CORE ALTERATIONS shall be suspended, and no control rod shall be moved from its existing position.

DELETED Not required to be performed when entering OPERATIONAL CONDITION 2 from OPERATIONAL CONDITION 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering OPERATIONAL CONDITION 2.

With THERMAL POWER~ 25% of RATED THERMAL POWER.

Frequencies are specified in the Surveillance Frequency Control Program unless otherwise noted in the table.

LIMERICK - UNIT 2 3/4 3-8 Amendment No. 7,17,4g,J5,79,92,1Q9,1~9.147,15e,le~.196

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 235 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-63 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 235, is hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~,

~ 0J2 (y ___ _

David J. Wrona, ranch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

ATTACHMENT TO LICENSE AMENDMENT NO. 235 RENEWED FACILITY OPERATING LICENSE NO. DPR-63 NINE MILE POINT NUCLEAR STATION, UNIT 1 DOCKET NO. 50-220 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License DPR-63 Page 3 TSs 197 203 Insert License DPR-63 Page 3 TSs 197 203 (2)

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

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

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

(5)

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

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 235, is hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications.

(3)

Deleted Renewed License No. DPR-63 Amendment No. 191 tl'lFe1:1~1'l 210,211,213,214,215,216,217,218,222,223,224,225,227,229,231,233,234,235 GeFfeetieA Letter Detea A1:1~1:1st 7, 2012 GerreetieA Letter Datea Merel'! 17, 2015 GerreetieA Letter Jatea ch:tly 29, 2016

LIMITING CONDITION FOR OPERATION

b.

During operation with the Core Maximum Fraction of Limiting Power Density (CMFLPD) greater than the Fraction of Rated Thermal Power (FRTP), either:

(1) The APRM scram and rod block settings shall be reduced to the values given by the equations in Specification 2.1.2a; or (2) Action shall be taken within two (2) hours to adjust the APRM gain in accordance with Specification 2.1.2a; or (3) The power distribution shall be changed such that the CMFLPD no longer exceeds FRTP.

AMENDMENT NO. 142, 14a, 222, 235 CorreetioA letter of 1 O 4 oa SURVEILLANCE REQUIREMENT

c.

During reactor power operation at :?:25 percent rated thermal power, the Core Maximum Fraction of Limiting Power Density (CMFLPD) shall be checked in accordance with the Surveillance Frequency Control Program and the flow-referenced APRM scram and rod block signals shall be adjusted, if necessary, as specified by Specification 2.1.2a.

197

(a)

(b)

(c)

(d)

(e)

(f)

(g)

(h)

(i)

(j)

(k)

(I)

(m)

(n)

NOTES FOR TABLES 3.6.2a and 4.6.2a May be bypassed when necessary for containment inerting.

May be bypassed in the refuel and shutdown positions of the reactor mode switch with a keylock switch.

May be bypassed in the refuel and startup positions of the reactor mode switch when reactor pressure is less than 600 psi, or for the purpose of performing reactor coolant system pressure testing and/or control rod scram time testing with the reactor mode switch in the refuel position.

No more than one of the four IRM inputs to each trip system shall be bypassed.

No more than two C or D level LPRM inputs to an APRM shall be bypassed and only four LPRM inputs to an APRM shall be bypassed in order for the APRM to be considered operable. No more than one of the four APRM inputs to each trip system shall be bypassed provided that the APRM in the other instrument channel in the same core quadrant is not bypassed. A Traversing In-Core Probe (TIP) chamber may be used as a substitute APRM input if the TIP is positioned in close proximity to the failed LPRM it is replacing.

Verify SRM/IRM channels overlap during startup after the mode switch has been placed in startup. Verify IRM/APRM channels overlap at least 1/2 decade during entry into startup from run (normal shutdown) if not performed within the previous 7 days.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before startup, if not performed within the previous 7 days. Not required to be performed during shutdown until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering startup from run.

Each of the four isolation valves has two limit switches. Each limit switch provides input to one of two instrument channels in a single trip system.

May be bypassed when reactor power level is below 45%.

Trip upon loss of oil pressure to the acceleration relay.

May be bypassed when placing the reactor mode switch in the SHUTDOWN position and all control rods are fully inserted.

The trip circuit will be calibrated and tested in accordance with the Surveillance Frequency Control Program, the primary sensor will be calibrated and tested in accordance with the Surveillance Frequency Control Program.

This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during reactor operation when thermal power ~ 25% of rated thermal power. Verify the calculated power does not exceed the APRM channels by greater than 2% of rated thermal power. Any APRM channel gain adjustment made in compliance with Specification 2.1.2a shall not be included in determining the difference.

Neutron detectors are excluded.

AMENDMENT NO. 142, 143, 153, 168,186,222,235 203

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 175 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.

Enclosure.10

2.

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

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 175, are hereby incorporated into this license.

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

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~--\\

r

"\\

l~ ) J u 1,;/, ___ _

David J. Wrona, srl-ch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

ATTACHMENT TO LICENSE AMENDMENT NO. 175 RENEWED FACILITY OPERATING LICENSE NO. NPF-69 NINE MILE POINT NUCLEAR STATION, UNIT 2 DOCKET NO. 50-410 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License NPF-69 Page 4 TSs 3.3.1.1-1 3.3.1.1-4 License NPF-69 Page 4 TSs 3.3.1.1-1 3.3.1.1-4

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

(2)

Technical Specifications and Environmental Protection Plan (3)

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 175, are hereby incorporated into this license. Exelon Generation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

a.

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

b.

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

c.

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

d.

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

(4)

Turbine System Maintenance Program (Section 3.5.1.3.10, SER)

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

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

Lawrence Burkhardt, 111).

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

Renewed License No. NPF-69 Amendment 117 tRFeli~R 149,141, 143, 144, 146, 146, 147, 169, 161, 162, 164,166,167,168,169,169, 161, 163,164,166,166, 167, 168, 169, 179, 172, 174, 175

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS

NO TES-----------------------------------------------------------

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at ~ 23% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

trip.

OR A.2 Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

B.

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

Not applicable for Functions 2.a, 2.b, 2.c, 2.d, and 2.e.

One or more Functions B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more trip system in trip.

required channels inoperable in both OR trip systems.

B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

(continued)

NMP2 3.3.1.1-1 Amendment Q1, Q2, 175

SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function Maintains RPS trip capability.

SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.4 NMP2 SURVEILLANCE Perform CHANNEL CHECK.

Perform CHANNEL CHECK.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER;::,: 23% RTP.

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at

,

23% RTP.

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

For Functions 1.a and 1.b, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued) 3.3.1.1-4 Amendment 91, 92, 12~. 14Q, 151,152,175

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 322 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied. 1

2.

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

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 322, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/"\\

r,. 2

/I U

f)

/;/'~ --

(.__ _ _1 David J. Wrona, B ch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

ATTACHMENT TO LICENSE AMENDMENT NO. 322 RENEWED FACILITY OPERATING LICENSE NO. DPR-44 PEACH BOTTOM ATOMIC POWER STATION. UNIT 2 DOCKET NO. 50-277 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License DPR-44 Page 3 TSs 3.3-1 3.3-2 3.3-3 3.3-3a License DPR-44 Page 3 TSs 3.3-1 3.3-2 3.3-3 3.3-3a 3.3-3b

(5)

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

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1)

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

(2)

Technical Specifications (3)

(4)

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 322, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

Physical Protection 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, 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.

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:

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

Renewed License No. DPR-44 Revised by letter dated October 28, 2004 Revised by letter dated May 29, 2007 Amendment No. 322 Page 3

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS

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

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at

~ 22.6% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION A.

One or more required channels inoperable.

PBAPS UN IT 2 A.l A.2 REQUIRED ACTION Pl ace channel in trip.

NOTE---------

Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

Place associated trip system in trip.

3.3-1 COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 12 hours (continued)

Amendment No. 322

ACTIONS (continued)

CONDITION B.

NOTE---------

Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

One or more Functions with one or more required channels inoperable in both trip systems.

C.

One or more automatic Functions with RPS trip capability not maintained.

Two or more manual Functions with RPS trip capability not maintained.

D.

Required Action and associated Completion Time of Condition A, B, or C not met.

E.

As required by Required Action D.l and referenced in Table 3.3.1.1-1.

PBAPS UN IT 2 B.l B.2 C.l D.l E. 1 REQUIRED ACTION Pl ace channel in one trip system in trip.

RPS Instrumentation 3.3.1.1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

Restore RPS trip capability.

Enter the Condition referenced in Table 3.3.1.1-1 for the channel.

Reduce THERMAL POWER to< 26.3% RTP.

3.3-2 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Immediately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

Amendment No. 322

ACTIONS (Continued)

CONDITION F.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

G.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

H.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

I.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

PBAPS UN IT 2 F. 1 G.1 H.1 I.1 AND I. 2 AND REQUIRED ACTION RPS Instrumentation 3.3.1.1 COMPLETION TIME Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Initiate action to Immediately implement the Manual Backup Stability Protection (BSP)

Regions defined in the COLR.

Implement the Automated BSP Scram Region using the modified APRM Simulated Thermal Power-High scram setpoints defined in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I.3 Initiate action to Immediately submit an OPRM report in accordance with Specification 5.6.8.

(continued) 3.3-3 Amendment No. 322

ACTIONS (continued)

CONDITION J.

Required Action and associated Completion J. 1 Time of Condition I not met.

AND J.2 AND J.3 K.

Required Action and associated Completion K.1 Time of Condition J not met.

PBAPS UN IT 2 REQUIRED ACTION Initiate action to implement the Manual RPS Instrumentation 3.3.1.1 COMPLETION TIME Immediately BSP Regions defined in the COLR.

Reduce operation to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months below the BSP Boundary defined in the COLR.

NOTE--------

LCO 3.0.4 is not applicable.

Restore required 120 days channel to OPERABLE.

Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to< 17.6% RTP.

3.3-3a Amendment No. 322

SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SR 3.3.1.1.1 SR 3.3.1.1.2 PBAPS UN IT 2 SURVEILLANCE Perform CHANNEL CHECK.

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

Not required to be performed unti 1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER~ 22.6% RTP.

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at~ 22.6% RTP.

3.3-3b FREQUENCY In accordance with the Surveillance Frequency Control Program.

In accordance with the Surveillance Frequency Control Program.

(continued)

Amendment No. 322

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 EXELON GENERATION COMPANY, LLC PSEG NUCLEAR LLC DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 325 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied. 2

2.

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

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 325, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION CA_J 9 o/ __

David J. Wrona, Branch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

ATTACHMENT TO LICENSE AMENDMENT NO. 325 RENEWED FACILITY OPERATING LICENSE NO. DPR-56 PEACH BOTTOM ATOMIC POWER STATION, UNIT 3 DOCKET NO. 50-278 Replace the following pages of the Renewed Facility Operating License and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License DPR-56 Page 3 TSs 3.3-1 3.3-2 3.3-3 3.3-3a License DPR-56 Page 3 TSs 3.3-1 3.3-2 3.3-3 3.3-3a 3.3-3b

(5)

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

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1)

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

(2)

Technical Specifications (3)

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 325, are hereby incorporated in the license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications.

Physical Protection 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, 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 1 O 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.

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

Renewed License No. DPR-56 Revised by letter dated October 28, 2004 Revised by letter dated November 5, 2004 Revised by letter dated May 29, 2007 Amendment No. 325 Page 3

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 sha 11 be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS

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

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at

~ 22.6% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION A.

One or more required channels inoperable.

PBAPS UN IT 3 A.l REQUIRED ACTION Pl ace channel in trip.

COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months A.2

NOTE---------

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

Place associated trip system in trip.

(continued) 3.3-1 Amendment No. 325

ACTIONS (continued)

CONDITION B.

NOTE---------

B.l Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2f.

OR One or more Functions with one or more required channels inoperable in both trip systems.

B.2 C.

One or more automatic C.l Functions with RPS trip capability not maintained.

Two or more manual Functions with RPS trip capability not maintained.

D.

Required Action and associated Completion Time of Condition A, B, or C not met.

E.

As required by Required Action 0.1 and referenced in Table 3.3.1.1-1.

PBAPS UN IT 3 0.1 E. 1 REQUIRED ACT ION Pl ace channel in one trip system in trip.

RPS Instrumentation 3.3.1.1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Pl ace one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

Restore RPS trip capability.

Enter the Condition referenced in Table 3.3.1.1-1 for the channel.

Reduce THERMAL POWER to< 26.3% RTP.

3.3-2 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Immediately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

Amendment No. 325

ACTIONS (continued)

CONDITION F.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

G.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

H.

As required by Required Action D.1 and referenced in Table 3.3.1.1-1.

I.

As required by Required Action D.l and referenced in Table 3.3.1.1-1.

PBAPS UN IT 3 F.l G.1 H.l I.1 AND I. 2 AND I. 3 REQUIRED ACTION Be in MODE 2.

Be in MODE 3.

Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Initiate action to implement the Manual Backup Stability Protection (BSP)

RPS Instrumentation 3.3.1.1 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours Immediately Immediately Regions defined in the COLR.

Implement the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Automated BSP Scram Region using the modified APRM Simulated Thermal Power-High scram setpoints defined in the COLR.

Initiate action to Immediately submit an OPRM report in accordance with Specification 5.6.8.

(continued) 3.3-3 Amendment No. 325

ACTIONS (continued)

CONDITION J.

Required Action and J.1 associated Completion Time of Condition I not met.

AND J.2 AND J.3 K.

Required Action and K.l associated Completion Time of Condition J not met.

PBAPS UN IT 3 REQUIRED ACTION Initiate action to implement the Manual RPS Instrumentation 3.3.1.1 COMPLETION TIME Immediately BSP Regions defined in the COLR.

Reduce operation to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months below the BSP Boundary defined in the COLR.

NOTE----------

LCO 3.0.4 is not applicable.

Restore required 120 days channel to OPERABLE.

Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to< 17.6% RTP.

3.3-3a Amendment No. 325

SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1

-- -- - - - - -- - - - - -- - - - - - - - - - - - - - - -- - - - -*-NOTES -- - - - - - - - -- - -- - - -- - - - - - -- - -- - - - - - - - -

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SR 3.3.1.1.1 SR 3.3.1.1.2 PBAPS UN IT 3 SURVEILLANCE Perform CHANNEL CHECK.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER~ 22.6% RTP.

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at~ 22.6% RTP.

3.3-3b FREQUENCY In accordance with the Surveillance Frequency Control Program.

In accordance with the Surveillance Frequency Control Program.

(continued)

Amendment No. 325

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 272 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act}, and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied. 3

2.

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

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 272, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION CJcJ! o,1;/

Dav;d J. Wro~a, s/a~ch Chief ------*

Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 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. 267 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 (Exelon, the licensee) dated June 15, 2018, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied. 4

2.

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

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 150 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

_'::>h,

,r

\\

L/ ) j/ (;) 0r/

/ '-

I, Da~id J. ;rona,ls'r~nch Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Renewed Facility Operating License Date of Issuance:

January 16, 2019

ATTACHMENT TO LICENSE AMENDMENT NOS. 272 AND 267 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A, Technical Specifications (TSs), with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License DPR-29 Page4 License DPR-30 Page4 TSs 3.3.1.1-1 3.3.1.1-3 License DPR-29 Page 4 License DPR-30 Page 4 TSs 3.3.1.1-1 3.3.1.1-3 B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 272, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

The licensee shall maintain the commitments made in response to the March D.

14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 1 O CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

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

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 1 O CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

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. 249 as modified by License Amendment No. 259.

F.

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 July 27, 1979 with supplements dated November 5, 1980, and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-29 Amendment No. 272 B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

The license shall maintain the commitments made in response to the D.

March 14, 1983, NUREG-0737 Order, subject to the following provision:

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

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

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 1 O CFR 73.55 (51 FR 27817 and 27822), and the authority of 1 O CFR 50.90 and 1 O CFR 50.54(p). The combined set of plans1, which contain Safeguards Information protected under 1 O CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

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 1 O CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 244 and modified by License Amendment No. 254.

F.

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 July 27, 1979 with supplements dated 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.

Renewed License No. DPR-30 Amendment No. 267

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation RPS Instrumentation 3.3.1.1 LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS NOTES - - - - -- - - - - - - - - - - - - - -- - - -- - - - - - - - - - - -

1.

Separate Condition entry is allowed for each channel.

2.

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at A.

B.

~ 25% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

CONDITION REQUIRED ACTION COMPLETION TIME One or more required A.l Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

trip.

OR A.2 Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

One or more Functions B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more trip system in trip.

required channels inoperable in both OR trip systems.

B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

(continued)

Quad Cities 1 and 2 3.3.1.1-1 Amendment No. 272/267

SURVEILLANCE REQUIREMENTS RPS Instrumentation 3.3.1.1 NOTES - - - - - - - - - - - - - - - -- - - -- - - - - - - - - - - - - - - -

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE SR 3.3.1.1.1 Perform CHANNEL CHECK.

FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.2

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

SR 3.3.1.1.3 Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER~ 25% RTP.

Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at~ 25% RTP.

Adjust the channel to conform to a calibrated flow signal.

Quad Cities 1 and 2 3.3.1.1-3 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Amendment No. 272/267

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555..()001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 222 TO FACILITY OPERATING LICENSE NO. NPF-62, AMENDMENT NO. 260 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19, AMENDMENT NO. 253 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25, AMENDMENT NO. 324 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-59, AMENDMENT NO. 234 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-11, AMENDMENT NO. 220 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-18, AMENDMENT NO. 233 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-39, AMENDMENT NO. 196 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-85, AMENDMENT NO. 235 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-63, AMENDMENT NO. 175 TO RENEWED FACILITY OPERA TING LICENSE NO. NPF-69, AMENDMENT NO. 322 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-44, AMENDMENT NO. 325 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-56, AMENDMENT NO. 272 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29, AND AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 EXELON GENERATION COMPANY, LLC CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 JAMES A. FITZPATRICK NUCLEAR POWER PLANT LASALLE COUNTY STATION, UNITS 1 AND 2 LIMERICK GENERATING STATION, UNITS 1 AND 2 5 NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-461, 50-237, :50-249, 50-333, 50-373, 50-374, 50-352, 50-353, 50-220, 50-410, 50-277, 50-278, 50-254, AND 50-265

1.0 INTRODUCTION

By application dated June 15, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18166A197), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request for Clinton Power Station, Unit No. 1 (Clinton); Dresden Nuclear Power Station, Units 2 and 3 (Dresden); James A. FitzPatrick Nuclear Power Plant (FitzPatrick); LaSalle County Station, Units 1 and 2 (LaSalle); Limerick Generating Station, Units 1 and 2 (Limerick);; Nine Mile Point Nuclear Station, Units 1 and 2 (NMP-1 and NMP-2, respectively); Peach Bottom Atomic Power Station, Units 2 and 3 (Peach Bottom); and Quad Cities Nuclear Power Station, Units 1 and 2 (Quad Cities) (the facilities).

The amendments would revise the average power range monitor (APRM) requirements in the technical specifications (TSs) for each facility.

2.0

2.1 REGULATORY EVALUATION

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System Description===

The APRM system is a safety-related system with two purposes. One purpose is to monitor neutron flux within the core to provide an indication of core power. The other purpose is to provide reactor scram and control rod block signals to preserve the fuel cladding integrity. The APRM channels receive input signals from the local power range monitors located in diverse axial and radial locations within the reactor core to provide an indication of the power distribution and local power changes. The APRM channels average the local power range monitor inputs, and each APRM provides a continuous indication of average reactor power from a small percentage of rated thermal power (RTP) to greater than RTP. A gain adjustment can be made to each APRM channel output allowing it to be calibrated to the calculated core thermal power.

Currently, the TS allowable absolute difference between calculated core thermal power and the APRM channel output is 2 percent for each of the facilities.

2.2 Description of the Proposed Changes The licensee's proposed changes are based on Technical Specifications Task Force (TSTF) traveler TSTF-546, Revision 0, "Revise APRM Channel Adjustment Surveillance Requirement,"

dated April 21, 2016 (ADAMS Accession No. ML16112A208). The U.S. Nuclear Regulatory Commission (NRC, the Commission) approved TSTF-546, Revision 0, by letter dated August 31, 2017 (ADAMS Accession No. ML17206A431 ). The application states that the proposed changes align with the intent of TSTF-546, but implements the change in a different manner.

TSTF-546 proposed changes to the Standard Technical Specifications {STS) and STS Bases for boiling-water reactors (BWRs). 1 The proposed changes in TSTF-546 would revise the BWR STS Surveillance Requirement (SR) 3.3.1.1.2 for APRMs, which is associated with the STS limiting conditions for operation (LCOs) for reactor protection system (RPS) instrumentation.

Currently, STS SR 3.3.1.1.2 states (bracketed information is considered plant-specific):

Verify the absolute difference between the average power range monitor (APRM) channels and the calculated power is s 2% RTP [plus any gain adjustment required by LCO 3.2.4, "Average Power Range Monitor (APRM) Setpoints"] while operating at~ 25% RTP.

TSTF-546 proposed to revise STS SR 3.3.1.1.2 to state:

Compare the average power range monitor (APRM) channels to the calculated power. Adjust the APRM channels if the calculated power exceeds the APRM output by more than 2% RTP while operating at~ 25% RTP.

The proposed STS Bases changes in TSTF-546 provide the following clarification regarding the revised STS SR 3.3.1.1.2:

If the heat balance calculated reactor power exceeds the APRM channel output by more than 2% RTP, the APRM is not declared inoperable, but must be adjusted consistent with the heat balance calculated power. If the APRM channel output cannot be properly adjusted, the channel is declared inoperable.

Similar to TSTF-546, the licensee's proposed changes would revise the TSs for each facility to only require adjustment of the APRM channels if the calculated reactor power exceeds the APRM channel output by more than 2 percent of RTP. However, the licensee's proposed changes do not include adding a requirement to adjust the APRM channels. Instead, the licensee proposes to either add or retain a 2-hour delay period in the TSs before entry into the associated conditions and required actions for an inoperable APRM would be required. The delay period is intended to allow sufficient time to adjust the APRM channels such that the APRM SR and associated LCO could be met. What follows is a detailed description of the plant-specific proposed TS changes.

APRM SRs Table 1 lists the relevant part of the current APRM SRs and the proposed changes to these SRs for each facility. Each SR is only performed when the power level is at or above a plant-specific threshold value, specified as a percentage of RTP, which ranges from 21.6-25 percent of RTP for the facilities. These threshold values would not be changed by the proposed amendments.

The APRM SRs for Clinton, Dresden, FitzPatrick, LaSalle, NMP-2, Peach Bottom, and Quad Cities also include a note (not shown in Table 1) stating that the SR is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after thermal power is greater than or equal to the specified percentage of RTP. These notes would also not be changed by the proposed amendments.

1 NUREG-1433, "Standard Technical Specifications, General Electric BWR/4 Plants," Volumes 1 and 2, Revision 4.0, April 2012 (ADAMS Accession Nos. ML12104A192 and ML12104A193, respectively); and NUREG-1434, "Standard Technical Specifications, General Electric BWR/6 Plants," Volumes 1 and 2, Revision 4.0, April 2012 (ADAMS Accession Nos. ML12104A195 and ML12104A196, respectively).

Table 1: Current requirements and proposed revisions to the APRM SRs.

TS Reference Current Requirement (in part)

Proposed Revised Requirement Clinton Verify the absolute difference Verify the calculated power does SR 3.3.1.1.2 between the average power range not exceed the average power monitor (APRM) channels and the range monitor (APRM) channels by calculated power s 2% RTP while greater than 2% RTP while operatinq at~ 21.6% RTP.

operatinq at~ 21.6% RTP.

Dresden Verify the absolute difference Verify the calculated power does SR 3.3.1.1.2 between the average power range not exceed the average power monitor (APRM) channels and the range monitor (APRM) channels by calculated power is s 2% RTP.

greater than 2% RTP while operating at ~ 25% RTP.

FitzPatrick Verify the absolute difference Verify the calculated power does SR 3.3.1.1.2 between the average power range not exceed the average power monitor (APRM) channels and the range monitor (APRM) channels by calculated power s. 2% RTP while greater than 2% RTP while operating at~ 25% RTP.

operating at ~ 25% RTP.

LaSalle Verify the absolute difference Verify the calculated power does SR 3.3.1.1.2 between the average power range not exceed the average power monitor (APRM) channels and the range monitor (APRM) channels by calculated power s 2% RTP while greater than 2% RTP while operating at~ 25% RTP.

operating at~ 25% RTP.

Limerick TS The more frequent calibration shall The more frequent calibration shall Table 4.3.1.1-1, consist of the adjustment of the consist of the adjustment of the footnote (d)

APRM channel to conform to the APRM channel to conform to the power values calculated by a heat power values calculated by a heat balance during OPERATIONAL balance during OPERATIONAL CONDITION 1 when THERMAL CONDITION 1 when THERMAL POWER ~25% of RATED THERMAL POWER ~25% of RA TED POWER. Adjust the APRM channel THERMAL POWER. Verify the if the absolute difference is greater calculated power does not exceed than 2% of RATED THERMAL the APRM channels by greater POWER.

than 2% of RATED THERMAL POWER.

NMP-1 TS This calibration shall consist of the This calibration shall consist of the Table 4.6.2a, adjustment of the APRM channel to adjustment of the APRM channel to footnote ( m) conform to the power values conform to the power values calculated by a heat balance during calculated by a heat balance during reactor operation when THERMAL reactor operation when thermal POWER ~ 25% of RA TED power ~ 25% of rated thermal THERMAL POWER. Adjust the power. Verify the calculated power APRM channel if the difference is does not exceed the APRM greater than +2.0/-1.9% of RATED channels by greater than 2% of THERMAL POWER. Any APRM rated thermal power. Any APRM channel gain adjustment made in channel gain adjustment made in compliance with Specification 2.1.2a compliance with Specification shall not be included in determining 2.1.2a shall not be included in the difference.

determininq the difference.

TS Reference Current Requirement (in part)

Prooosed Revised Requirement NMP-2 Verify the absolute difference Verify the calculated power does SR 3.3.1.1.3 between the average power range not exceed the average power monitor (APRM) channels and the range monitor (APRM) channels by calculated power s 2% RTP while greater than 2% RTP while operating at ~ 23% RTP.

ooeratina at~ 23% RTP.

Peach Bottom Verify the absolute difference Verify the calculated power does SR 3.3.1.1.2 between the average power range not exceed the average power monitor (APRM) channels and the range monitor (APRM) channels by calculated power is s 2% RTP while greater than 2% RTP while operating at~ 22.6% RTP.

operatina at~ 22.6% RTP.

Quad Cities Verify the absolute difference Verify the calculated power does SR 3.3.1.1.2 between the average power range not exceed the average power monitor (APRM) channels and the range monitor (APRM) channels by calculated power is s 2% RTP.

greater thar;i 2% RTP while operating at~ 25% RTP.

Delay Period for Inoperable APRM For Dresden, LaSalle, and Quad Cities, note 2 for TS 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," currently states:

When Functions 2.b and 2.c channels are inoperable due to the APRM indication not within limits, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if the APRM is indicating a lower power value than the calculated power, and for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the APRM is indicating a higher power value than the calculated power.

The licensee proposed to revise this note to state:

When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at ~ 25%

RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

The licensee also proposed to add a similar note to the Clinton, FitzPatrick, Limerick, NMP-2, and Peach Bottom TSs, which currently do not have an equivalent delay period in their TSs.

For Clinton, FitzPatrick, NMP-2, and Peach Bottom, the licensee proposed to add the new note to TS 3.3.1.1, "Reactor Protection System (RPS) Instrumentation," number the existing note as note 1, and change "NOTE" to "NOTES" in the header. For Limerick, the license proposed to add a new note to TS 3/4.3.1, "Reactor Protection System Instrumentation." The proposed new note text for these facilities is listed in Table 2.

Table 2: Proposed new TS note for APRMs.

TS Reference Proposed New Note Clinton When Functions 2.b and 2.c channels are inoperable due to the calculated TS 3.3.1.1 power exceeding the APRM output by more than 2% RTP while operating at 2! 21.6% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

FitzPatrick When Functions 2.b and 2.c channels are inoperable due to the calculated TS 3.3.1.1 power exceeding the APRM output by more than 2% RTP while operating at 2! 25% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Limerick When Functional Unit 2.b and 2.c channels are inoperable due to the TS 3/4.3.1 calculated power exceeding the APRM output by more than 2% of RA TED THERMAL POWER while operating at 2! 25% of RA TED THERMAL POWER, entrv into the associated Actions may be delayed up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

NMP-2 When Functions 2.b and 2.c channels are inoperable due to the calculated TS 3.3.1.1 power exceeding the APRM output by more than 2% RTP while operating at 2! 23% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Peach Bottom When Functions 2.b and 2.c channels are inoperable due to the calculated TS 3.3.1.1 power exceeding the APRM output by more than 2% RTP while operating at 2! 22.6% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

For NMP-1, LCO 3.6.2(b)(2) currently states: "The APRM gain shall be adjusted in accordance with Specification 2.1.2a." The licensee proposed to revise LCO 3.6.2(b)(2) to state: "Action shall be taken within two (2) hours to adjust the APRM gain in accordance with Specification 2.1.2a." A note would not be added to the NMP-1 TSs.

2.3 Regulatory Requirements and Guidance Title 1 O of the Code of Federal Regulations (10 CFR) 50.36, "Technical specifications,"

establishes the regulatory requirements related to the content of TSs. Paragraph 50.36(a)(1) requires an application for an operating license to include proposed TSs. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the TSs.

Pursuant to 10 CFR 50.36, TSs for operating reactors are required to include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) SRs; (4) design features; and (5) administrative controls. In accordance with 10 CFR 50.36(c)(2), LCOs are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When an LCO is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met. In accordance with 1 O CFR 50.36(c)(3), SRs are requirements relating to test, calibration, or inspection, to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.

The NRC staff's guidance for the review of TSs is in Chapter 16, "Technical Specifications,"

Revision 3, dated March 2010 (ADAMS Accession No. ML100351425), of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants:

LWR [Light-Water Reactor] Edition."

3.0 TECHNICAL EVALUATION

3.1 APRM Requirements For each facility, the current APRM SR requires periodic verification that the absolute difference between the APRM channels and the calculated power is less than or equal to 2 percent of RTP. The APRM SR is only performed when the power level is at or above a plant-specific threshold value, which ranges from 21.6-25 percent of RTP for the facilities (Table 1, above, shows the plant-specific values). If the absolute difference is greater than 2 percent of RTP, the APRM channel is declared inoperable. An acceptable way to restore operability of the APRM is to adjust the gain for the APRM channel to restore the absolute difference to less than or equal to 2 percent of RTP. If the APRM channel is reading higher than the calculated thermal power, this adjustment would be nonconservative with respect to the RPS trip setpoint. If the APRM channel is reading lower than the calculated thermal power, this adjustment would be conservative with respect to the RPS trip setpoint.

With the proposed changes, the APRM for each facility would only be considered inoperable if the calculated power exceeded the APRM channels by greater than 2 percent of RTP. Thus, the APRM would no longer be considered inoperable if the APRM channel exceeded the calculated power by greater than 2 percent of RTP. If the APRM signal is reading higher than the calculated thermal power, the initiation of a reactor trip would occur at an actual power level lower than the trip setpoint. Therefore, eliminating the requirement to verify the APRM channel does not exceed the calculated power by greater than 2 percent is acceptable.

For Dresden, LaSalle, and Quad Cities, if the APRM is inoperable, note 2 in TS 3.3.1.1 currently allows the licensee to delay entry into the associated TS conditions and required actions for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months if the APRM is indicating a lower power value than the calculated power, and for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if the APRM is indicating a higher power value than the calculated power. These delay periods provide time for the licensee to adjust the APRM channels to meet the LCO and SR before entry into the associated TS conditions and required actions. Consistent with the proposed changes to the APRM SR, the licensee is proposing to revise note 2 to eliminate the delay period for the situation where the APRM channel exceeds the calculated power.

However, the licensee proposes to retain the 2-hour delay period for the situation where the calculated power exceeds the APRM channel, with revised wording to make the note consistent with the proposed wording for the APRM SR.

For Clinton, FitzPatrick, Limerick, NMP-2, and Peach Bottom, the licensee proposed to add a TS note to permit a 2-hour delay before entering the TS conditions and required actions for an APRM that is inoperable due to the calculated power exceeding the APRM output by more than 2 percent of RTP. As shown in Table 2, above, the proposed new note for these facilities is similar to the proposed revised note for Dresden, LaSalle, and Quad Cities. For NMP-1, instead of adding a new note, the licensee proposed to revise LCO 3.6.2(b)(2) to state: "Action shall be taken within two (2) hours to adjust the APRM gain in accordance with Specification 2.1.2a."

The application states that this 2-hour delay period is intended to provide time to restore an inoperable APRM channel before entry into the associated TS conditions and required actions.

In Section 3.3, "Justification of a Two-Hour Completion Time," of the application, the licensee stated that "two hours remains a reasonable time frame in which to restore multiple APRM channels to within the TS specified limit based on the low probability of a transient or [design-basis accident] occurring simultaneously." The licensee cited NRG-approved amendments for LaSalle and Monticello Nuclear Generating Plant (Monticello) as precedents that justify the proposed 2-hour delay period (ADAMS Accession Nos. ML021120212 and ML12339A035, respectively). The application stated that for the LaSalle amendments, a 2-hour delay period to restore APRM channels was justified "as being reasonable since it is consistent with power distribution limit related completion times." The APRM systems for Clinton, FitzPatrick, Limerick, NMP-1, NMP-2, and Peach Bottom are similar in functionality to those for LaSalle and Monticello. Due to the similarities between the designs and the TS requirements for these facilities, the NRC staff finds that the 2-hour delay period is reasonable for Clinton, FitzPatrick, Limerick, NMP-1, NMP-2, and Peach Bottom.

As part of TSTF-546, the revised STS APRM SR included a requirement to adjust the APRM channels if the calculated power exceeds the APRM output by more than 2 percent of RTP.

The APRM SRs for Limerick and NMP-1 already require adjustment of the APRM channel to conform to the power values calculated by a heat balance during reactor operation when thermal power is greater than or equal to 25 percent of RTP. However, the licensee did not request to include a requirement to adjust the APRM channels within the APRM SR or elsewhere in the TSs for Clinton, Dresden, FitzPatrick, LaSalle, NMP-2, Peach Bottom, or Quad Cities. Instead, the licensee has proposed to add or retain a 2-hour delay period in the TSs before entry into the TS conditions and required actions associated with an inoperable APRM, which would allow the licensee time to adjust the APRM channels. Although the licensee's proposed TS changes are different than the proposed STS changes in TSTF-546, entry into the TS conditions and required actions would still occur if the licensee could not adjust the APRM channels to meet the revised SR.

The NRC staff reviewed the proposed changes to the TSs for each facility by considering whether the requirements of 1 O CFR 50.36 would continue to be met. The NRC staff determined that with the proposed changes, the TSs for each facility will continue to provide appropriate controls and acceptance criteria to ensure that the APRMs adequately reflect reactor power. Therefore, with the proposed changes, the APRM SR for each facility will continue to meet the requirements in 10 CFR 50.36(c)(3), which specifies that SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. In addition, with the proposed changes, the TSs will continue to provide appropriate remedial actions, in accordance with 10 CFR 50.36(c)(2), when the LCO for RPS Instrumentation is not met as a result of an inoperable APRM channel.

3.2 Additional TS Changes For Clinton, FitzPatrick, NMP-2, and Peach Bottom, the licensee also proposed to revise TS 3.3.1.1 by numbering the existing note as note 1 and changing "NOTE" to "NOTES" in the header. These changes are acceptable because they do not change the TS requirements and, instead, are editorial.

For NMP-1, the licensee also proposed to change "THERMAL POWER" and "RATED THERMAL POWER" from all capitals to lowercase in footnote (m) to TS Table 4.6.2a. In the STS, defined terms are written in all capitals. However, NMP-1 does not use this convention, and these terms are not defined in the NMP-1 TSs. Therefore, this proposed change is acceptable because it does not alter the NMP-1 requirements and, instead, is editorial.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Illinois, Pennsylvania, and New York State officials were notified of the proposed issuance of the amendments on October 9, 2018.

The State officials had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to the installation or use of facility components located within the restricted areas as defined in 1 O CFR Part 20 and change SRs.

The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding, which was published in the Federal Register on August 14, 2018 (83 FR 40348), that the amendments involve no significant hazards consideration, and there has been no public comment on such finding.

Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The 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 Commission's 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 Contributors: Huda Akhavannik, NRR Date of issuance:

January 16, 2019

SUBJECT:

CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; JAMES A. FITZPATRICK NUCLEAR POWER PLANT; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2; PEACH BOTIOM ATOMIC POWER STATION, UNITS 2 AND 3; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO REVISE THE AVERAGE POWER RANGE MONITOR REQUIREMENTS (EPID L-2018-LLA-0167) DATED JANUARY 16, 2019 DISTRIBUTION:

PUBLIC RidsNrrDorlLpl1 Resource RidsNrrDorlLpl3 Resource RidsRgn1 MailCenter Resource RidsRgn3MailCenter Resource RidsNrrLALRonewicz Resource RidsNrrLASRohrer Resource RidsAcrs_MailCTR Resource RidsNrrPMExelon Resource RidsNrrPMClinton Resource RidsNrrPMDresden Resource RidsNrrPMFitzPatrick Resource RidsNrrPMLaSalle Resource RidsNrrPMLimerick Resource RidsNrrPMNineMilePoint Resource RidsNrrPMPeachBottom Resource RidsNrrPMQuadCities Resource RidsNrrDeEicb Resource RidsNrrDssStsb Resource TSweat, NRR HAkhavannik, NRR RStattel, NRR ADAMS A ccess1on N ML18304A365 o.:

b

1

,yema1 OFFICE NRR/DORL/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DE/EICB/BC DSS/STSB/BC NAME BPurnell SRohrer MWaters*

VCusumano DATE 11/20/18 11/18/18 10/31/18 11/7/18 OFFICE OGC NLO NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME JWachutka DWrona BPurnell DATE 11/20/18 1/16/19 1/16/19 OFFICIAL RECORD COPY

v t e Letter Sequence Approval
EPID:L-2018-LLA-0167, TSTF-546, TSTF-546 (Approved, Closed)
Initiation Request, Request Acceptance... Administration Questions Answers Results Approval Other: ML18192B622, ML18254A398
MONTHYEAR2018-06-15 [Table View]

ML18304A365

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Dear Mr. Hanson:

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1.0 INTRODUCTION

2.1 REGULATORY EVALUATION

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3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

SUBJECT:

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