Text

Issuance of Amendments Regarding Control Room Ventilation Temperature Control System (CAC Nos. MF9932, MF9933, MF9934, and MF9935; EPID L-2017-LLA-0247)
	ML18054B436
Person / Time
Site:	Byron, Braidwood ; (NPF-037, NPF-066, NPF-072, NPF-077)
Issue date:	04/30/2018
From:	Joel Wiebe; Plant Licensing Branch III
To:	Bryan Hanson; Exelon Generation Co
	Wiebe J, NRR/DORL/LPLIII
References
	CAC MF9932, CAC MF9933, CAC MF9934, CAC MF9935, EPID L-2017-LLA-0247
	Download: ML18054B436 (27)
	v • d • e

Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 30, 2018 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS.

1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING CONTROL ROOM VENTILATION TEMPERATURE CONTROL SYSTEM (CAC NOS. MF9932, MF9933, MF9934, AND MF9935; EPID L-2017-LLA-0247)

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 195 to Renewed Facility Operating License No. NPF-72 and Amendment No.

195 to Renewed Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, respectively, and Amendment No. 201 to Renewed Facility Operating License No. NPF-37 and Amendment No. 201 to Renewed Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated June 30, 2017 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML17181A276).

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

Docket Nos. STN 50-456, STN 50-457, STN 50-454, and STN 50-455

Enclosures:

1. Amendment No. 195 to NPF-72

2. Amendment No. 195 to NPF-77

3. Amendment No. 201 to NPF-37

4. Amendment No. 201 to NPF-66

5. Safety Evaluation Cc w/enclosures: Listserv Sincerely,

~~~!sd::!::nager I ~~ant 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. STN 50-456 BRAIDWOOD STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 Renewed License No. NPF-72

1.

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

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 30, 2017, 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-72 is hereby amended to read as follows:

(2)

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

3.

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

Attachment:

Changes to the Technical FOR THE NUCLEAR REGULATORY COMMISSION r

David J. Wrona, Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance: Apr i 1 3 o, 2 o 1 8

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 195 Renewed License No. NPF-77

1.

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

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 30, 2017, 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-77 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 195 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

Attachment:

Changes to the Technical FOR THE NUCLEAR REGULATORY COMMISSION (jJOV~

David J. Wrona, d,ief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance: April 3 o, 2 O 1 8

ATTACHMENT TO LICENSE AMENDMENT NOS. 195 AND 195 RENEWED FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Renewed Facility Operating Licenses and Appendix A Technical Specifications 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-72 Page 3 License NPF-77 Page 3 TSs Page 3.7.11-2 Page 3.7.11-3 License NPF-72 Page 3 License NPF-77 Page 3 TSs Page 3.7.11-2 Page 3.7.11-3 (2)

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

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

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

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

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the 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 3645 megawatts thermal ( 100 percent rated power) in accordance with the conditions specified herein.

(2)

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

Renewed License No. NPF-72 Amendment No. 195 (2)

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

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

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

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

C.

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 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 195 and the Environmental Protection Plan contained in Appendix B, both of which are attached to Renewed License No. NPF-72, dated January 27, 2016, are hereby incorporated into the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. NPF-77 Amendment No. 195

ACTIONS (continued)

CONDITION C.

Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.

D.

Two VC Temperature Control System trains inoperable.

BRAIDWOOD - UNITS 1 & 2 C.1.1 AND C.1.2 OR C.2.1 AND C.2.2 0.1 AND 0.2 AND 0.3 VC Temperature Control System 3.7.11 REQUIRED ACTION COMPLETION TIME Place OPERABLE VC Immediately Temperature Control System train in operation.

Verify OPERABLE VC Immediately Temperature Control System train is capable of being powered by an OPERABLE emergency power source.

Suspend movement of Immediately irradiated fuel assemblies.

Suspend positive Immediately reactivity additions.

Initiate action to Immediately implement mitigating actions.

Verify control room Immediately temperature~ 80°F.

AND Once per hour thereafter Restore one VC 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Temperature Control System train to OPERABLE status.

(continued) 3.7.11-2 Amendment 195

VC Temperature Control System

3. 7.11 ACTIONS (continued)

CONDITION REQUIRED ACTION E.

Required Action and E.1 Be in MODE 3.

associated Completion Time of Condition D AND not met in MODE 1, 2, 3, or 4.

E.2 Be in MODE 5.

F.

Required Action and F.1 Suspend movement of associated Completion irradiated fuel Time of Condition D assemblies.

not met in MODE 5 AND or 6, or during movement of irradiated F.2 Suspend positive fuel assemblies.

reactivity additions.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.11.1 Verify control room temperature~ 90°F.

SR 3.7.11.2 Verify each VC Temperature Control System train has the capability to remove the required heat load.

BRAIDWOOD - UNITS 1 & 2 3.7.11-3 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 195

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 201 Renewed License No. NPF-37

1.

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

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 30, 2017, 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-37 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 201 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

Attachment:

Changes to the Technical FOR THE NUCLEAR REGULATORY COMMISSION

~~a.imv __

Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance:

Apr i 1 3 O, 2 O 1 8

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 201 Renewed License No. NPF-66

1.

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

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated June 30, 2017, 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-66 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 201 and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No.

NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

Attachment:

Changes to the Technical FOR THE NUCLEAR REGULATORY COMMISSION a~ q o/~

David J. Wrona, Chief Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance: April 30, 201 8

ATTACHMENT TO LICENSE AMENDMENT NOS. 201 AND 201 RENEWED FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 BYRON STATION. UNIT NOS.1 AND 2 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Renewed Facility Operating License and Appendix A Technical Specifications 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-37 Page 3 License NPF-66 Page 3 TSs Page 3.7.11-2 Page 3.7.11-3 Insert License NPF-37 Page 3 License NPF-66 Page 3 TSs Page 3.7.11-2 Page 3.7.11-3 (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 Updated Final Safety Analysis Report, as supplemented and amended; (3)

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

( 4)

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

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

C.

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 3645 megawatts thermal ( 100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 201 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Deleted.

( 4)

Deleted.

Renewed License No. NPF-37 Amendment No. 201 (2)

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

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

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

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

C.

The renewed license shall be deemed to contain and is subject to the conditions specified in the 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 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A (NUREG-1113), as revised through Amendment No. 201 and the Environmental Protection Plan contained in Appendix B, both of which were attached to Renewed License No. NPF-37, dated November 19, 2015, are hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Renewed License No. NPF-66 Amendment No. 201

ACTIONS (continued)

CONDITION C.

Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.

D.

Two VC Temperature Control System trains inoperable.

BYRON - UNITS 1 & 2 C.1.1 AND C.1.2 OR C.2.1 AND C.2.2 0.1 AND 0.2 AND 0.3 VC Temperature Control System 3.7.11 REQUIRED ACTION COMPLETION TIME Place OPERABLE VC Immediately Temperature Control System train in operation.

Verify OPERABLE VC Immediately Temperature Control System train is capable of being powered by an OPERABLE emergency power source.

Suspend movement of Immediately irradiated fuel assemblies.

Suspend positive Immediately reactivity additions.

Initiate action to Immediately implement mitigating actions.

Verify control room Immediately temperature~ 80°F.

AND Once per hour thereafter Restore one VC 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Temperature Control System train to OPERABLE status.

(continued) 3.7.11 - 2 Amendment 201

VC Temperature Control System

3. 7.11 ACTIONS (continued)

CONDITION REQUIRED ACTION E.

Required Action and E.l Be in MODE 3.

associated Completion Time of Condition D AND not met in MODE 1, 2, 3, or 4.

E.2 Be in MODE 5.

F.

Required Action and F.1 Suspend movement of associated Completion irradiated fuel Time of Condition D assemblies.

not met in MODE 5 AND or 6, or during movement of irradiated F.2 Suspend positive fuel assemblies.

reactivity additions.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.11.1 Verify control room temperature~ 90°F.

SR 3.7.11.2 Verify each VC Temperature Control System train has the capability to remove the required heat load.

BYRON - UNITS 1 & 2 3.7.11-3 COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 201

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 195 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 195 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-77.

AMENDMENT NO. 201 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-37.

AND AMENDMENT NO. 201 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-66 EXELON GENERATION COMPANY. LLC BRAIDWOOD STATION. UNITS 1 AND 2 BYRON STATION. UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456. STN 50-457.

STN 50-454. AND STN 50-455

1.0 INTRODUCTION

By application dated June 30, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17181A276), Exelon Generation Company, LLC (EGC, the licensee) submitted a license amendment request (LAR) for Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2, to the U.S. Nuclear Regulatory Commission (NRC, the Commission). The LAR would revise technical specification (TS) limiting condition for operation (LCO) 3.7.11, "Control Room Ventilation (VC) Temperature Control System," to allow a completion time (CT) of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore one of the two control room ventilation temperature control system trains to operable status rather than require immediate entry into TS LCO 3.0.3 and commencing a plant shutdown within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . This proposed change would avoid the risks and costs of shutdown transients of one or both operating reactors should one train of control room ventilation cooling become inoperable while the other train is already inoperable due to planned preventive maintenance or corrective maintenance due to a failure of the other temperature control system train with a reactor in Modes 1, 2, 3, and 4. Instead of the TS LCO 3.0.3 requirement to commence shutdown of the operating units within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and subsequently reaching cold shutdown within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months , a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months would be allowed to restore one of the two inoperable control room ventilation cooling trains to an operable status.

The Braidwood and Byron Stations each have a common control room for both Units 1 and 2.

The common control rooms have a ventilation system with two trains of emergency filtration for control of airborne radioactivity to limit operator dose during an accident and two trains of temperature control that remove the heat put into the control room by operating equipment and limit ambient temperatures to ensure proper electrical and electronic equipment operation and a habitable environment for operators during normal operations and during an accident. The control room ventilation temperature control system purpose is to ensure control room temperature will not exceed equipment operational requirements following isolation of the control room by maintaining the control room temperatures 90 °F (degrees Fahrenheit). The TS LCO 3.7.10, "Control Room Ventilation (VC) Filtration System," would remain unchanged.

2.0 REGULATORY EVALUATION

Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications" states that the TSs must include items in specific categories. These categories include: (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. Section 50.36 also states that when an LCO is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TSs until the condition can be met. Section 50.36 does not specify what actions are required or how quickly they must be completed.

Appendix A to 10 CFR 50 provides the General Design Criteria (GDC) for nuclear power plants.

The following GDC are related to this LAR.

Criterion 19-Control room. A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents.

Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident. Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures.

Criterion 4-Environmental and dynamic effects design bases. Structures, systems, and components important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents.

These structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit. However, dynamic effects associated with postulated pipe ruptures in nuclear power units may be excluded from the design basis when analyses reviewed and approved by the Commission demonstrate that the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis for the piping.

3.0 TECHNICAL EVALUATION

Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2, are Westinghouse design 4-loop pressurized water reactors within large, dry ambient prestressed-concrete primary containments. Both units at each site share a common control room with a common ventilation system which includes two redundant trains of emergency filtration and two redundant temperature control system trains.

The control room ventilation temperature control system is designed to ensure that the environments in all spaces served by the control room heating, ventilation, and air conditioning system ( control room envelope) are controlled within specified limits which are conducive to prolonged service life of Safety Class 1 components during all station conditions.

3.1 Licensee's Proposed Changes The existing Braidwood Station and Byron Station TS 3.7.11 Conditions D and Estate:

CONDITION REQUIRED ACTION COMPLETION TIME D.

Two VC Temperature D.1 Suspend movement of Immediately Control System trains irradiated fuel inoperable in Mode 5 or 6, assemblies.

or during movement of irradiated fuel assemblies.

AND D.2 Suspend positive Immediately reactivity additions.

E.

Two VC Temperature E1.

Enter LCO 3.0.3.

Immediately Control System trains inoperable in MODE 1, 2, 3, or 4.

The proposed Braidwood Station and Byron Station TS 3.7.11 Conditions D and E and new Condition F would state:

CONDITION REQUIRED ACTION COMPLETION TIME D.

Two VC Temperature D.1 Initiate action to Immediately Control System trains implement mitigating inoperable.

actions.

AND D.2 Verify control room Immediately temperatures 80°F.

AND Once per hour AND thereafter D.3 Restore one VC 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Temperature Control System train to OPERABLE status.

E.

Required Action and E.1.

Bein MODE3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition D AND not met in MODE 1, 2, 3, or 4.

E.2 Be in MODE 5.

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

Required Action and F.1 Suspend movement Immediately associated Completion of irradiated fuel Time of Condition D not assemblies.

met in MODE 5 or 6, or during movement of AND irradiated fuel assemblies.

F.2 Suspend positive Immediately reactivity additions.

The licensee proposed changes to TS 3.7.11 would alter the CT for the action required if both control room ventilation temperature control system trains are inoperable. Instead of immediately proceeding with the TS LCO 3.0.3 required action of commencing shutdown of the operating units within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and achieving cold shutdown within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months , the licensee would have 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore one of the temperature control system trains to operability before having to commence the unit shutdowns. However, the licensee would immediately begin monitoring control room temperature at least once per hour to verify temperature s 80 °F and initiating mitigating actions. TS SR 3. 7.11.1 requires verification of control room temperature s 90 °F thus additional margin to the operability threshold would be maintained. The LAR stated that the lowest specification for control room equipment cabinets is 104 °F. With the proposed TS change, if control room temperature exceeds 80 °F prior to the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months expiring, the operating units are required to be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and MODE 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

3.2 Justification for the TS Changes The licensee identified in the LAR that NUREG-1432, "Standard Technical Specifications Combustion Engineering Plants" (ADAMS Accession No. ML12102A165), TS 3. 7.12 provides 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for restoration of one of two inoperable control room cooling trains. This allowance was approved and incorporated into the standard technical specifications for combustion engineering plants by the NRC on May 30, 2013, as TSTF-426, Revision 5, "Revise or Add Actions to Preclude Entry into LCO 3.0.3 - RITSTF [Risk Informed Technical Specification Task Force] Initiatives 6b & 6c" (78 FR 32476; ADAMS Accession No. ML113260461). Similarly, NUREG-1433, "Standard Technical Specifications General Electric BWR/4 Plants," Revision 4 (ADAMS Accession No. ML12104A192), TS 3.7.5 provides 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for restoration of one of two inoperable control room cooling subsystems. NUREG-1434, "Standard Technical Specifications General Electric BWR/6 Plants," Revision 4 (ADAMS Accession No. ML12104A195), TS 3.7.4 provides 7 days for restoration of one of two inoperable control room cooling subsystems. These provisions of time to restore one of two control room cooling trains were included with the rationale that a reasonable period of time to restore one train of control room cooling would involve comparable and perhaps less risk than commencing an immediate unit shutdown transient and associated significant costs. Although these NUREGs are not directly applicable to Braidwood or Byron Station, the control room cooling function is largely independent of the reactor nuclear steam supply system vendor design and similar justifications for the requested change would be consistent.

The LAR identified four industry events from the last 10 years where both trains of control room cooling were inoperable. A 2014 event at Ft. Calhoun Station, Unit 1, where one train failed while the other train was inoperable for maintenance lasted 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months before one train of control room cooling was restored during which time reactor power had been reduced to 33 percent.

A 2011 event at Catawba Nuclear Station, which has 2 units with a shared control room, also involved one train failing while the other train was inoperable for maintenance. The Catawba reactors were shutdown but allowed to remain in MODE 3 when a Notice of Enforcement Discretion (NOED) was granted by the NRC (ADAMS Accession No. ML113560359). One train of control room cooling was restored in 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months . A 2010 event at McGuire Nuclear Station, which has 2 units with a shared control room, also involved one train failing while the other train was inoperable for maintenance. The McGuire reactors' power reduction was halted when a NOED was granted (ADAMS Accession No. ML100201023). One train of control room cooling was restored in 23 hours2.662037e-4 days 0.00639 hours 3.80291e-5 weeks 8.7515e-6 months . A 2008 event at Sequoyah Nuclear Plant, which has 2 units with a shared control room, involved one train failing while the other train was inoperable for maintenance on the associated emergency diesel generator. The Sequoyah reactors' shutdown was halted when an NOED was granted by the NRC (ADAMS Accession No. ML082760667).

One train of control room cooling was restored in 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months . In these four events, a 24-hour CT to restore one train of control room cooling to an operable status would have been sufficient to avoid reactor shutdowns or the need for an NOED. The justification for granting these NOEDs was based primarily on a qualitative risk assessment that allowing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for restoration of one train of control room cooling was bounded by the risk of unscheduled reactor shutdowns.

The Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2, TS LCO 3.7.10, "Control Room Ventilation (VC) Filtration System," would remain the same. TS LCO 3.7.10 CONDITIONS would still have to be met or the associated REQUIRED ACTIONS taken accordingly.

Based on the above discussion, the NRC staff finds that the proposed changes meet Appendix A to 1 O CFR Part 50, Criterion 19, "Control room," since the control room temperature is to be maintained s 80 °F, which is below the temperature necessary for proper electrical and electronic equipment operation (104 °F) and supports habitability for control room personnel for the duration of the proposed new 24-hour CT. Based on the above discussion, the NRC staff finds that the proposed changes also meet Appendix A to 10 CFR Part 50, Criterion 4, "Environmental and dynamic effects design bases," because the control room temperature will continue to be maintained s 90 °F as required by SR 3. 7.11.1, which remains unchanged.

The regulation 10 CFR 50.36 does not specify what actions are required or how quickly they must be completed. The 24-hour CT of the proposed new REQUIRED ACTION D.3 is reasonable based on the determination that the mitigating actions of REQUIRED ACTION D.1 and the s 80 °F temperature of REQUIRED ACTION D.2 will ensure that control room temperature is maintained within the temperature limit for proper equipment operation and habitability for control room personnel while limiting the probability that control room temperatures would adversely affect the equipment or occupants ability to control the reactor and maintain it in a safe shutdown condition in the event of a design basis accident during the proposed 24-hour CT. The proposed 24-hour CT will also provide a reasonable time to restore at least one temperature control system train to operability. Based on the above, the NRC staff concludes that the proposed changes continue to meet 10 CFR 50.36 and that, therefore, the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments on February 23, 2018. The State official 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 area as defined in 1 O CFR Part 20. 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 on August 29, 2017 (82 FR 41068) 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 Section 51.22(c)(9). Pursuant to 10 CFR Section 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 Contributor: J. Bettle Date of issuance: April 30, 2018

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS.

1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING CONTROL ROOM VENTILATION TEMPERATURE CONTROL SYSTEM (CAC NOS. MF9932, MF9933, MF9934, AND MF9935; EPID L-2017-LLA-0247)

DATED APRIL 30, 2018 DISTRIBUTION:

PUBLIC RidsNrrDirsltsb Resource RidsRgn3MailCenter Resource RidsNrrDorlLpl3 Resource RidsNrrLASRohrer Resource RidsNrrPMByron Resource RidsNrrDorlDpr Resource RidsNrrPMBraidwood Resource RidsACRS_MailCTR Resource Accession No. ML180548436 OFFICE DORL/LPL3/PM NAME JWiebe DATE 03/28/18 OFFICE STSB/BC NAME VCusumano DATE 03/27/18

via memo **via e-mail DORL/LPL3/LA DSS/CPSB/BC DRA/ARCB/BC SRohrer RDennig*

KHsueh 02/26/18 02/21/18 02/27/18 OGC DORL/LPL3/BC DORL/LPL3/PM JWachutka DWrona JWiebe 04/04/18 04/30/18 04/30/18 OFFICIAL RECORD COPY