ML15007A555

Issuance of Amendments

ML15007A555
Person / Time
Site:	Byron, Braidwood
Issue date:	01/30/2015
From:	Joel Wiebe Plant Licensing Branch III
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Joel Wiebe, NRR/DORL 415-6606
References
TAC MF2643, TAC MF2644, TAC MF2645, TAC MF2646
Download: ML15007A555 (32)

Text

Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 30, 2015 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 MAIN STEAM INSOLATION VALVE TECHNICAL SPECIFICATIONS (TAC NOS. MF2643, MF2644, MF2645, AND MF2646)

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 181 to Facility Operating License No. NPF-72 and Amendment No. 181 to Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, respectively, and Amendment No. 187 to Facility Operating License No. NPF-37 and Amendment No. 187 to 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 August 21, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13235A095). The approval revises Technical Specification 3.7.2, "Main Steam Isolation Valves (MSIVs)," to include new CONDITIONS and associated REQUIRED ACTIONS and COMPLETION TIMES (CTs) in the ACTIONS table specific to MSIV actuator trains. Additionally, surveillance requirement (SR) 3.7.2.2 is being revised to clearly identify that each MSIV actuator train is required to be tested to support the operability of the associated MSIV.

A copy of the 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. 181 to NPF-72

2. Amendment No. 181 to NPF-77

3. Amendment No. 187 to NPF-37

4. Amendment No. 187 to NPF-66

5. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely, Joel S. Wiebe, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch 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 FACILITY OPERATING LICENSE Amendment No. 181 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 August 21, 2013, 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-72 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 181 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULA TORY COMMISSION

~d~*

Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance: January 30, 2015

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 FACILITY OPERATING LICENSE Amendment No. 181 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 August 21, 2013, 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-77 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 181 and the Environmental Protection Plan contained in Appendix 8, both of which are attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this 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.

FOR THE NUCLEAR REGULATORY COMMISSION

(;~/(~-

Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

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

January 30, 2015

ATTACHMENT TO LICENSE AMENDMENT NOS. 181 AND 181 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Facility Operating Licenses and Appendix "A" Technical Specifications with the attached 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 3.7.2-1 3.7.2-2 License NPF-72 Page 3 License NPF-77 Page 3 TSs 3.7.2-1 3.7.2-2 3.7.2-3 (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.

The 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 is not in excess of 3645 megawatts thermal (1 00 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license.

The items identified in Attachment 1 to this license shall be completed as specified. is hereby incorporated into the license.

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 181 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

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

Amendment No. 181 material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

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

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

C.

The 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 (1 00 percent rated power) in accordance with the conditions specified herein and other items identified in to this license. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 181 and the Environmental Protection Plan contained in Appendix 8, both of which are attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

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

Amendment No. 181

3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCD 3.7.2 Four MSIVs and their associated actuator trains shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 except when all MSIVs are closed.

ACTIONS MSIVs 3.7.2 CONDITION REQUIRED ACTION COMPLETION TIME A.

One MSIV actuator A.1 Restore MSIV actuator 7 days train inoperable.

train to OPERABLE status.

B.

Two MSIVs each with B.1 Restore one MSIV 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> one actuator train actuator train to inoperable such that OPERABLE status.

the inoperable actuator trains are in different ESF Divisions.

C.

Two MSIVs each with C.1 Restore one MSIV 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> one actuator train actuator train to inoperable and both OPERABLE status.

inoperable actuator trains are in the same ESF Division.

D.

Two MSIV actuator D.1 Declare the affected Immediately trains inoperable on MSIV inoperable.

the same MSIV.

(cont1nued)

BRAIDWOOD - UNITS 1 & 2 3.7.2-1 Amendment No.

181

ACTIONS (continued)

CONDITION E.

Three or more MSIV actuator trains inoperable.

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

F.

One MSIV inoperable in MODE 1.

G.

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

H.

---

NOTE---------

Separate Condition entry is allowed for each MSIV.

One or more MSIV inoperable in MODE 2 or 3.

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

BRAIDWOOD - UNITS 1 & 2 E.1 F.1 G.1 H.1 AND H.2 I.1 AND I.2 REQUIRED ACTION Declare each affected MSIV inoperable.

Restore MSIV to OPERABLE status.

Be in MODE 2.

Close MSIV.

Verify MSIV is closed.

Be in MODE 3.

Be in MODE 4.

MSIVs 3.7.2 COMPLETION TIME Immediately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 6 hours 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Once per 7 days 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours 3.7.2-2 Amendment No. 181 I

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SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SURVEILLANCE

---

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

Only required to be performed in MODES 1 and 2.

Verify closure time of each MSIV is s 5 seconds.

---

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

Only required to be performed in MODES 1 and 2.

Verify each actuator train actuates the MSIV to the isolation position on an actual or simulated actuation signal.

BRAIDWOOD - UNITS 1 & 2 3.7.2-3 MSIVs 3.7.2 FREQUENCY In accordance with the Inservice Testing Program In accordance with the Surveillance Frequency Control Program Amendment No. 181

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY. LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 187 License No. NPF-37

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated August 21, 2013, 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-37 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 187 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR JE NUCLEAR REGULATORY COMMISSION

(~;-~d~

Travis L. Tate, Branch Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

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

January 30, 2015

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 FACILITY OPERATING LICENSE Amendment No. 187 License No. NPF-66

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Exelon Generation Company, LLC (the licensee) dated August 21, 2013, 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-66 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-1113}, as revised through Amendment No. 187 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Travis L. Tate, Branch Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

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

January 30, 2015

ATTACHMENT TO LICENSE AMENDMENT NOS. 187 AND 187 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Facility Operating License and Appendix "A" Technical Specifications with the attached 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 3.7.2-1 3.7.2-2 License NPF-37 Page 3 License NPF-66 Page 3 TSs 3.7.2-1 3.7.2-2 3.7.2-3 (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 and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

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 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 power) in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 187 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Deleted.

(4)

Deleted.

(5)

Deleted.

(6)

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report, and as approved in the SER dated February 1987 through Supplement No. 8, subject to the following provision:

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

Amendment No. 187 (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.

B.

The 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 (1 00 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. 187 and the Environmental Protection I

Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Deleted.

(4)

Deleted.

(5)

Deleted.

Amendment No. 187

3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCD 3.7.2 Four MSIVs and their associated actuator trains shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 except when all MSIVs are closed.

ACTIONS MSIVs 3.7.2 CONDITION REQUIRED ACTION COMPLETION TIME A.

One MSIV actuator A.1 Restore MSIV actuator 7 days train inoperable.

train to OPERABLE status.

B.

Two MSIVs each with B.1 Restore one MSIV 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> one actuator train actuator train to inoperable such that OPERABLE status.

the inoperable actuator trains are in different ESF Divisions.

c.

Two MSIVs each with C.1 Restore one MSIV 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> one actuator train actuator train to inoperable and both OPERABLE status.

inoperable actuator trains are in the same ESF Division.

D.

Two MSIV actuator D.1 Declare the affected Immediately trains inoperable on MSIV inoperable.

the same MSIV.

(cont1nued)

BYRON - UNITS 1 & 2 3.7.2-1 Amendment No. 187

ACTIONS (continued)

CONDITION E.

Three or more MSIV actuator trains inoperable.

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

F.

One MSIV inoperable in MODE 1.

G.

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

H.

---

NOTE---------

Separate Condition entry is allowed for each MSIV.

One or more MSIV inoperable in MODE 2 or 3.

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

BYRON - UNITS 1 & 2 E.1 F.1 G.1 H.1 AND H.2 I.1 AND I.2 REQUIRED ACTION MSIVs 3.7.2 COMPLETION TIME Declare each affected Immediately MSIV inoperable.

Restore MSIV to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OPERABLE status.

Be in MODE 2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Close MSIV.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Verify MSIV is Once per 7 days closed.

Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.7.2-2 Amendment No. 187 I

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SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SURVEILLANCE

---

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

Only required to be performed in MODES 1 and 2.

Verify closure time of each MSIV is

~ 5 seconds.

---

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

Only required to be performed in MODES 1 and 2.

Verify each actuator train actuates the MSIV to the isolation position on an actual or simulated actuation signal.

MSIVs 3.7.2 FREQUENCY In accordance with the Inservice Testing Program In accordance with the Surveillance Frequency Control Program BYRON - UNITS 1 & 2 3.7.2-3 Amendment No. 187

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 187 TO FACILITY OPERATING LICENSE NO. NPF-37, AND AMENDMENT NO. 187 TO FACILITY OPERATING LICENSE NO. NPF-66

1.0 INTRODUCTION

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 By application dated August 21, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13235A095), Exelon Generation Company, LLC (the licensee), requested changes to the technical specifications (TSs) for Braidwood Station, Units 1 and 2 (Braidwood), and Byron Station, Unit Nos. 1 and 2 (Byron). These amendments would revise TS 3.7.2, "Main Steam Isolation Valves (MSIVs)," to include new CONDITIONS and associated REQUIRED ACTIONS and COMPLETION TIMES (CTs) in the ACTIONS table specific to MSIV actuator trains. Additionally, Surveillance Requirement (SR) 3.7.2.2 is being revised to clearly identify that each MSIV actuator train is required to be tested to support the operability of the associated MSIV. The existing conditions and required actions in TS 3.7.2 would be renumbered to account for the proposed new conditions and required actions.

The licensee stated that the existing CT for an inoperable MSIV does not typically provide a reasonable amount of time to effect repairs to one inoperable actuator train. Therefore, the licensee proposed to incorporate requirements specifically for the MSIV actuator trains within TS 3.7.2 such that the specification would include Conditions and Required Actions to address inoperable MSIV actuator trains.

2.0 REGULATORY EVALUATION

2.1

System Description

The MSIVs isolate steam flow from the secondary side of the steam generators following a steam line isolation signal. One MSIV is installed in each of the main steam lines outside the containment and downstream of the main steam safety valves. Each MSIV is a gate valve with a double gate design that is hydraulically operated. The valve is designed to close in less than 5 seconds based on the limiting accident of a steam line break outside the containment to limit cool down rate of the reactor coolant system.

Each MSIV is equipped with two redundant hydraulic actuator trains such that either actuator train can independently perform the safety function to close the valve on demand. The MSIVs fail as is on loss of control or actuation power and are interlocked with the engineered safety features (ESF) system to auto close on the following main steam line isolation signals: manual; low steam line pressure; high negative rate steam line pressure; and containment pressure high-high (Hi-2).

2.2 Regulatory Requirements Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. These TSs are derived from the plant safety analyses.

Section 50.36 to Title 10 to the Code of Federal Regulations (1 0 CFR) contains the requirements for the content of the TS. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls.

Section 50.36(a)(1) to 10 CFR requires each applicant for a license to include a summary statement of the bases or reasons for proposed TS; however, the bases shall not become part of the TSs.

Section 50.36(c)(2) to 10 CFR states that LCOs are the lowest functional capability or performance level of equipment required for safe operation of the facility and when LCOs are not met, the licensee shall shut down the reactor or follow any remedial action permitted by the TS until the LCO can be met.

Section 50.36(c)(3) to 10 CFR states 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 LCO will be met.

2.3 Regulatory Guidance In determining the acceptability of revising TS 3.7.2, the NRC staff used plant-specific licensing basis information as well as the accumulation of generically approved guidance in NUREG-1431, "Standard Technical Specifications, Westinghouse Plants" dated April2012 (ADAMS Accession No. ML12100A222).

The single-failure criterion for nuclear power plants is the requirement for safety-related structures, systems, and components (SSCs) used to mitigate abnormal operational occurrences and design basis accidents (DBAs) to have sufficient redundancy in components and features such that the safety function(s) for any such SSG can be accomplished assuming any single failure. The single-failure criterion is defined in Appendix A, "General Design Criteria (GDC) for Nuclear Power Plants," of 10 CFR Part 50, and stated in GDCs 17, 34, 35, 38, 41, and 44. Plants are designed and licensed to meet the single-failure criterion. Plants are normally operated with the requirement that the single-failure criterion is being met in that the TSs contain LCOs that require all necessary SSCs, which meet the four criteria in 1 0 CFR 50.36(c)(2)(ii) to be operable.

Plant TSs are formulated to preserve the single-failure criterion for SSCs described in the updated final safety analysis report that are relied upon in the DBA analyses. The single-failure criterion is preserved by specifying LCOs that require all redundant components of safety-related systems to be operable. When the required redundancy is not maintained, either due to equipment failure or a maintenance outage, the TSs require plant shutdown or a remedial action to be taken within aCT, which is a temporary relaxation of the single-failure criterion. The specified CT provides a limited time, consistent with overall system reliability and risk considerations, to fix the equipment or otherwise make it operable.

Given that the design and safety function(s) of the MSIVs and the associated actuator trains are not being changed by the proposed amendment, there are no applicable GDCs related to the design and safety function of the MSIVs, and the associated actuator trains, for this amendment.

3.0 TECHNICAL EVALUATION

3.1 TS Changes LCO 3.7.2 Current Text: Four MSIVs shall be OPERABLE Revised Text: Four MSIVs and their associated actuator trains shall be OPERABLE Evaluation: The revised text specifically identifies the MSIV actuator trains as equipment required to be OPERABLE for safe operation of the facility. The MSIV actuator trains are required to close the MSIVs when needed. Based on the MSIV actuator train function to close the MSIVs, the NRC staff determined that 10 CFR 50.36(c)(2) is met.

Add new CONDITIONs, REQUIRED ACTIONs, and COMPLETION TIMEs as follows:

CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV actuator train A.1 Restore MSIV actuator 7 days inoperable train to OPERABLE status.

Evaluation: The proposed new Condition A addresses the condition of having one MSIV actuator train inoperable for a single valve. The proposed Required Action for this Condition requires restoring the inoperable actuator train to OPERABLE status within 7 days. The licensee's justification for new Condition A is that with only a single actuator train inoperable on one MSIV, a CT of 7 days for Required Action A.1 is reasonable due to the fact that with one actuator train inoperable and the dual-redundant actuator design, the affected valve would still be capable of closing on demand (assuming no additional failures) via the remaining OPERABLE actuator train. The licensee stated that the proposed 7-day CT takes into account the design redundancy, reasonable time for repairs, and the low probability of a DBA occurring during this period. The NRC staff determined that the CONDITION meets 10 CFR 50.36(c)(2) based on the evaluation of the revised text for LCO 3.7.2, above. The NRC staff determined that the Required Action is acceptable because it directly corrects the CONDITION. The NRC determined that the Completion Time of 7 days is acceptable because it is consistent with NUREG-1431 which provides similar CTs for similar LCOs that involve redundant equipment such as the 7-day completion time for one of two inoperable steam supplies to the turbine driven auxiliary feedwater pump.

CONDITION REQUIRED ACTION COMPLETION TIME B. Two MSIVs each with B.1 Restore one MSIV 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> one actuator train actuator train to inoperable such that OPERABLE status.

the inoperable actuator trains are in different ESF Divisions.

Evaluation: The proposed new Condition B addresses the condition of having two MSIV actuator trains inoperable for different valves. That is, one actuator train inoperable for each of two MSIVs such that the actuator trains are not in the same ESF division. The proposed Required Action for this Condition would require restoring at least one actuator train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The licensee's justification for new Condition B and the associate Required Action and CT is that with one inoperable actuator train on one MSIV and one inoperable actuator train on another MSIV, such that the actuator trains are not in the same ESF division, a CT of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for Required Action B.1 is reasonable based on the dual-redundant actuator train design which ensures that with only one actuator train inoperable on each of the affected MSIVs, each MSIV would still be capable of closing on demand, assuming no additional failures. The licensee stated that it is appropriate to have a shorter CT for Condition B compared to Condition A since with an actuator train inoperable on each of two MSIVs, there is an increased likelihood that an additional failure (such as the failure of an actuation logic train) would cause an MSIV to fail to close. The NRC staff determined that the CONDITION meets 10 CFR 50.36(c)(2) based on the evaluation of the revised text for LCO 3.7.2, above. The NRC staff determined that the Required Action is acceptable because it directly corrects the CONDITION. The NRC determined that the Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is acceptable because, similar to Condition A, above, the affected MSIVs will still close on demand.

The NRC staff determined that a reduced Completion Time from 7 days to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is acceptable because it is necessarily more conservative than that of Condition A based on an increased likelihood of an additional failure.

CONDITION REQUIRED ACTION COMPLETION TIME C. Two MSIVs each with C.1 Restore one MSIV 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> one actuator train actuator train to inoperable and both OPERABLE status.

inoperable actuator trains are the same ESF Division.

The proposed new Condition C addresses the situation when two MSIV actuator trains are inoperable for different valves and the inoperable actuator trains are both in the same ESF division. The proposed Required Action for this Condition would require restoring at least one actuator train to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The licensee provided the following justification for the 24-hour CT:

With one inoperable actuator train on one MSIV and one inoperable actuator train on another MSIV, but with both inoperable actuator trains in the same ESF division, a Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Required Action C.1 is appropriate. Like the above cases, the dual-redundant actuator train design for each MSIV ensures that a single inoperable actuator train for any valve would not prevent the affected valve from closing on demand. In this regard, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is reasonable and conservative since only one actuator train per valve is permitted to be inoperable (for two MSIVs), so that the remaining OPERABLE actuator train on each affected MSIV remains capable of effecting valve closure on demand (assuming no additional failures). A Completion Time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is also considered appropriate given the low probability of an event occurring during such an interval that would demand MSIV closure. Additionally, the Completion Time is consistent with Condition G of TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," which provides a 24-hour Completion Time for restoring one train to OPERABLE status.

Condition G is applicable to Function 4.b (Steam Line Isolation Automatic Actuation Logic and Actuation Relays) which provides the actuation logic from the Solid State Protection System to the actuator trains. A loss of one actuation logic train would be equivalent to a loss of all actuator trains that receive a signal from that actuation logic.

However, compared to the Required Action for Condition B above, a shorter Completion Time for Condition C is appropriate since with two actuator trains inoperable in the same ESF division, an additional failure such as the failure of an actuation logic train in the other ESF division could cause both affected MSIVs to fail to close on demand.

The NRC staff determined that the CONDITION meets 10 CFR 50.36(c)(2) based on the evaluation of the revised text for LCO 3.7.2, above. The NRC staff determined that the Required Action is acceptable because it directly corrects the CONDITION.

The proposed CT of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Condition C is based on: (1) the extent to which the affected MSIVs are impacted, (2) being less than the proposed CT of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for Condition B (two MSIVs with an in operable actuator on different ESF trains), and (3) being consistent with the CT for an inoperable ESFAS actuation logic train. An MSIV with an inoperable actuator train would still be expected to close on demand by the redundant actuation train. Based on the above, the NRC staff determined that the CT of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is acceptable.

CONDITION REQUIRED ACTION COMPLETION TIME D. Two MSIV actuator D.1 Declare the affected Immediately trains inoperable on the MSIV inoperable.

same MSIV Evaluation: The proposed new Condition D addresses the situation when both actuator trains for one MSIV are inoperable. The Required Action proposed for this Condition would require immediately declaring the affected MSIV inoperable. The licensee stated that the CT of immediately is conservative and appropriate because when both actuator trains for one MSIV are inoperable, it is appropriate to immediately declare the valve inoperable, since having both actuator trains inoperable would cause the affected MSIV to fail to close on demand.

The NRC staff determined that the CONDITION meets 10 CFR 50.36(c)(2) based on the evaluation of the revised text for LCO 3. 7.2, above. Given that the two inoperable actuator trains make the MSIV incapable of performing its safety function, the NRC staff determined that the current TS required action and CT for an inoperable MSIV, should apply. Therefore, the NRC staff determined that the proposed required action and CT for proposed Condition D are acceptable.

CONDITION REQUIRED ACTION COMPLETION TIME E. Three or more actuator E.1 Declare each affected Immediately trains inoperable.

MSIV inoperable.

OR Required Action and associated Completion Time of Condition A, B, or C not met Evaluation: The proposed new Condition E addresses the condition of having three or more MSIV actuator trains inoperable, or the condition when, after entering Conditions A, B, or C, it is determined that the Required Action and Completion Time of any of those Conditions cannot be met. The Required Action for this Condition would require immediately declaring each affected MSIV inoperable. The licensee provided the following justification for new Condition E:

With respect to Condition E, for the Condition when the Required Action and associated Completion Time of Condition A, B, or Cis not met, it follows that the affected MSIV(s) should immediately be declared inoperable since the assumption is that the Completion Time(s) of Condition A, B, or C has expired or cannot be met. This "default" Condition is in keeping with the intent that when only the actuator trains for affected MSIVs are inoperable (and not the valves themselves), the Conditions and Required Actions for the inoperable valve actuator trains should be entered first, and then if those Required Actions cannot be met, the affected MSIVs should be declared inoperable so that the Conditions and Required Actions for the inoperable valves are then entered. Required Action E.1 ensures the affected MSIV(s) are promptly declared inoperable. This format or approach is consistent with other Technical Specifications and the format of the Improved Standard Technical Specifications (NUREG-1431).

For the other portion of Condition E, i.e., for the condition when three or more actuator trains are inoperable, it is conservative and appropriate as well to immediately declare the affected MSIVs inoperable for this condition. For the situation of having three inoperable actuator trains, for example, such a condition could involve two inoperable actuator trains on one valve and one inoperable actuator train on another valve, or one inoperable actuator train on each of three valves. In each case, the inoperable actuator trains could all be in the same ESF division or be staggered among the two ESF divisions. In the former case, a single assumed failure such as an instrument logic train failure could cause one or two valves to fail to close on demand. In the latter case, such a single failure could cause either none of the valves to fail to close on demand, or all three to fail to close on demand. Thus, immediately declaring the affected MSIVs inoperable is appropriate. In any case, the conditions addressed by Condition E would constitute an inoperability that exceeds the scope of any of the conditions addressed by Conditions A, B. or C, and it is conservative in this case to simply require declaring all of the affected MSIVs inoperable.

Since the proposed Condition E would represent a condition in which the affected MSIVs would not be able to perform their safety function, the NRC staff concludes that it is appropriate to declare the affected MSIVs inoperable. The licensee would then follow the remedial actions already approved by the staff. Therefore, the staff finds the proposed Required Action and Completion Time to be acceptable.

The licensee provided a discussion related to its use of probabilistic risk analysis (PRA) in assessing the proposed CTs for the new Required Actions. The licensee stated that the conclusion of the PRA evaluation was that the CTs for inoperable MSIV actuator trains were conservative. The NRC staff did not use the PRA information to make a determination on the acceptability of the proposed CT. Rather, the NRC staff assessed the licensee's non-PRA justifications for the proposed Conditions, Required Actions and CTs as discussed above.

With the proposed addition of new Conditions A through E, the licensee renumbered the existing Conditions A through D. The existing conditions would become Conditions F through I, and the references in existing Conditions B and D to the existing Conditions A and D would become references to the renumbered Conditions F and H.

Evaluation: The NRC staff determined that these changes are administrative in nature in that they do not materially change any existing requirements in TS 3.7.2. Based on this, the staff concludes that these changes to existing Conditions A through D are acceptable. The NRC staff further concludes that these proposed changes meet 10 CFR 50.36 and are, therefore, acceptable.

SR 3.7.2.2 Existing text: Verify each MSIV actuates to the isolation position on an actual or simulated actuation signal.

Revised text: Verify each actuator train actuates the MSIV to the isolation position on an actual or simulated actuation signal.

Evaluation: The existing text does not refer to the actuator train. With the explicit reference to each actuator train in the proposed SR text, the SR clearly states the actuator trains are required to be tested. Since both actuator trains for an MSIV are capable of separately closing the valve, both actuator trains must be shown to close the valve on an actual or simulated signal. The staff determined that the proposed language for SR 3.7.2.2 will assure that both actuator trains will be tested to demonstrate that each train alone can close the MSIV. This will provide assurance that the necessary quality of systems and components is maintained and that the LCOs are met. Therefore, the staff determined that proposed SR language is acceptable and meets 10 CFR 50.36(c)(3).

Based on the evaluations above, the NRC staff concludes that the proposed changes to the TS CONDITIONs, REQUIRED ACTIONs, and COMPLETION TIMEs describe appropriate remedial actions the licensee must take when the LCO is not met due to actuator train issues. Further, the NRC staff finds that the proposed change to SR 3.7.2.2 ensures that the necessary quality of SSCs is maintained, that facility operation will be within safety limits, and the SR requirements are sufficient to ensure operability of the required MSIV actuator trains. The NRC staff notes that the licensee used a PRAto validate the conservatism of the proposed CTs. The NRC staff's review did not include the licensee's risk assessment, as such this approval should not be construed to include acceptance of application of the licensee's PRA methodology in determining the acceptability of TS CTs for Byron or Braidwood.

3.2 Proposed TS Bases As discussed in 10 CFR 50.36(c)(2), the licensee may make changes to the TS Bases without prior NRC staff review and approval in accordance with the TS Bases Control Program (TS 5.5.14). Accordingly, along with the proposed TS changes, the licensee also submitted for information, TS Bases changes corresponding to the proposed TS changes.

The NRC staff notes that the TS Bases changes are consistent with the proposed changes and provide the purpose for each requirement consistent with the Commission's Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 2, 1993 (58 FR 39132). The NRC staff, therefore, concludes that 10 CFR 50.36(a)(1) is met in that the licensee included a summary statement of the bases for the proposed TS change. The NRC staff did not approve the TS Bases.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change the requirements with respect to installation or use of a facility's components located within the restricted area as defined in 10 CFR Part 20 and change a SR requirement. 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 that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (79 FR 18332; April 1, 2014). 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 Contributor: M. Hamm, NRR Date of issuance: January 30, 2015 A copy of the 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. 181 to NPF-72

2. Amendment No. 181 to NPF-77

3. Amendment No. 187 to NPF-37

4. Amendment No. 187 to NPF-66

5. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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