ML14239A427
| ML14239A427 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/07/2014 |
| From: | Weibe J Plant Licensing Branch III |
| To: | Pacilio M Exelon Generation Co |
| Joel Wiebe, NRR/DORL 415-6606 | |
| References | |
| TAC MF4023, TAC MF4024, TAC MF4025, TAC MF4026 | |
| Download: ML14239A427 (32) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 7, 2014 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2-ISSUANCE OF AMENDMENTS TO CLARIFY TECHNICAL SPECIFICATIONS 3.3.1, "REACTOR TRIP SYSTEM INSTRUMENTATION,"
AND TS 3.3.2, "ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (TAC NOS. MF4023, MF4024, MF4025, AND MF4026)
Dear Mr. Pacilio:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 180 to Facility Operating License No. NPF-72 and Amendment No. 180 to Facility Operating License No. NPF-77 for the, Braidwood Station, Units 1 and 2, respectively, and Amendment No. 186 to Facility Operating License No. NPF-37 and Amendment No. 186 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 April 17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14111A257).
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. 180 to NPF-72
- 2. Amendment No. 180 to NPF-77
- 3. Amendment No. 186 to NPF-37
- 4. Amendment No. 186 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. 180 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 April17, 2014, 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 Title 1 0 of the Code of Federal Regulations (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. 180 and the Environmental Protection Plan contained in Appendix 8, 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.
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 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:
December 7, 2014
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. 180 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 April17, 2014, 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 Title 1 0 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 1 0 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. 180 and the Environmental Protection Plan contained in Appendix B, both of which were 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 d~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:
December 7, 2014
ATTACHMENT TO LICENSE AMENDMENT NOS. 180 AND 180 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 3.3.1-3 3.3.1 -4 3.3.1-6 3.3.2-3 3.3.2-7 License NPF-72 Page 3 License NPF-77 Page 3 TSs 3.3.1-3 3.3.1 -4 3.3.1 -6 3.3.2-3 3.3.2-7 (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 not in excess of 3645 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in 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. 180, 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 provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 180 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 1 0 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 and other items identified in Attachment 1 to this license. The items identified in to this license shall be completed as specified. is hereby incorporated into this license.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 180, and the Environmental Protection Plan contained in Appendix B, 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 provisions of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 180
ACTIONS (continued)
CONDITION D.
One Power Range Neutron Flux-High channel inoperable.
BRAIDWOOD - UNITS 1 & 2 REQUIRED ACTION
NOTE------------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
D.l OR D.2 Place channel in trip.
Be in MODE 3.
RTS Instrumentation 3.3.1 COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours (continued) 3.3.1-3 Amendment No. 180
ACTIONS (continued)
CONDITION E.
One channel inoperable.
BRAIDWOOD - UNITS 1 & 2 REQUIRED ACTION
NOTE------------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
E.1 OR E.2 Place channel in trip.
Be in MODE 3.
RTS Instrumentation 3.3.1 COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours (continued) 3.3.1-4 Amendment No. 180
ACTIONS (continued)
CONDITION K.
One channel inoperable.
L.
One Turbine Trip channel inoperable.
BRAIDWOOD - UNITS 1 & 2 REQUIRED ACTION
NOTES------------
- 1. For Functions with installed bypass test capability (Functions 8a, 9, 10), one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
- 2.
For Functions with no installed bypass test capability (Functions 12 and 13), the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
K.1 Place channel in trip.
OR K.2 Reduce THERMAL POWER to< P-7.
NOTE-------------
The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
L.1 Place channel in trip.
OR L.2 Reduce THERMAL POWER to < P-8.
RTS Instrumentation 3.3.1 COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours (contlnued) 3.3.1-6 Amendment No. 180
ACTIONS (continued)
CONDITION D.
One channel inoperable.
BRAIDWOOD - UNITS 1 & 2 D.1 OR ESFAS Instrumentation 3.3.2 REQUIRED ACTION
NOTE---------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
Place channel in trip.
COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D.2.1 Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND D.2.2 Be in MODE 4.
84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> (continued) 3.3.2 - 3 Amendment No. 180
ACTIONS (continued)
CONDITION K.
One channel i noperab 1 e.
BRAIDWOOD - UNITS 1 & 2 K.1 OR ESFAS Instrumentation 3.3.2 REQUIRED ACTION
NOTE----------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
Place channel in trip.
COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> K.2.1 Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND K.2.2 Be in MODE 5.
108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> (continued) 3.3.2 - 7 ArnendmenLNo. 180
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. 186 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 April17, 2014, 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 Title 10 of the Code of Federal Regulations (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 1s hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 186 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.
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 o~o~~*
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:
December 7, 2014
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. 186 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 April17, 2014, 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 Title 1 0 of the Code of Federal Regulations (10 CFR) Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 1 0 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. 186 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 REGULA TORY 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: December 7, 2014
ATTACHMENT TO LICENSE AMENDMENT NOS. 186 AND 186 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 Page 3 License NPF-37 Page 3 License NPF-66 TSs 3.3.1-3 3.3.1-4 3.3.1-5 3.3.2 - 3 3.3.2-7 Insert Page 3 License NPF-37 Page 3 License NPF-66 TSs 3.3.1-3 3.3.1-4 3.3.1-5 3.3.2 - 3 3.3.2 - 7 (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.
This 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 power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 186 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 license 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. 186 (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 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. 186 and the Environmental Protection Plan contained in Appendix 8, 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. 186
ACTIONS (continued)
CONDITION D.
One Power Range Neutron Flux-High channel inoperable.
E.
One channel i noperab 1 e.
BYRON - UNITS 1 & 2 REQUIRED ACTION
NOTE-------------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
D.1 Place channel in trip.
OR D.2 Be in MODE 3.
NOTE------------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
E.1 Place channel in trip.
OR E.2 Be in MODE 3.
RTS Instrumentation 3.3.1 COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours
( contwued) 3.3.1-3 Amendment No. 186
ACTIONS (continued)
CONDITION F.
One Intermediate Range F.1 Neutron Flux channel inoperable.
OR F.2 G.
Two Intermediate Range G.1 Neutron Flux channels i noperab 1 e.
AND G.2 H.
One Source Range H.1 Neutron Flux channel inoperable.
I. Two Source Range I.1 Neutron Flux channels inoperable.
BYRON - UNITS 1 & 2 REQUIRED ACTION Reduce THERMAL POWER to < P-6.
Increase THERMAL POWER to > P-10.
Suspend operations involving positive reactivity additions.
Reduce THERMAL POWER to < P-6.
Suspend operations involving positive reactivity additions.
Open Reactor Trip Breakers CRTBs).
RTS Instrumentation 3.3.1 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hours Irrrnediately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Irrrnediately Irrrnediately Ccont1nued) 3.3.1-4 Amendment No. 186
ACTIONS (continued)
CONDITION J. One Source Range Neutron Flux channel inoperable.
K.
One channel inoperable.
BYRON - UNITS 1 & 2 REQUIRED ACTION J.1 Restore channel to OPERABLE status.
OR J.2.1 Initiate action to fully insert all rods.
AND J.2.2 Place the Rod Control System in a condition incapable of rod withdrawal.
NOTES------------
- 1.
For Functions with installed bypass test capability (Functions 8a, 9, 10), one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
- 2.
For Functions with no installed bypass test capability (Functions 12 and 13), the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
K.1 Place channel in trip.
OR K.2 Reduce THERMAL POWER to< P-7.
RTS Instrumentation 3.3.1 COMPLETION TIME 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 48 hours 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> 72 hours 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> (contlnued) 3.3.1-5 Amendment No. 186
ACTIONS (continued)
CONDITION D.
One channel inoperable.
BYRON - UNITS 1 & 2 D.1 OR ESFAS Instrumentation 3.3.2 REQUIRED ACTION
NOTE---------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
Place channel in trip.
COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> D.2.1 Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND D.2.2 Be in MODE 4.
84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> (continued) 3.3.2 - 3 Amendment No. 186
ACTIONS (continued)
CONDITION K.
One channel inoperable.
BYRON - UNITS 1 & 2 K.1 OR ESFAS Instrumentation 3.3.2 REQUIRED ACTION
NOTE---------
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
Place channel in trip.
COMPLETION TIME 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> K.2.1 Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND K.2.2 Be in MODE 5.
108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> (continued) 3.3.2 - 7 Amendment No. 186
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 180 TO FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 180 TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 186 TO FACILITY OPERATING LICENSE NO. NPF-37, AND AMENDMENT NO. 186 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 appiication to the U.S. Nuclear Regulatory Commission (NRC) dated April17, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14111A257), Exelon Generation Company, LLC (the licensee) requested changes to the technical specifications (TSs) and facility operating licenses for the Braidwood Station (Braidwood), Units 1 and 2, and Byron Station (Byron), Unit Nos. 1 and 2. The proposed changes revise required action notes in the Braidwood and Byron TS 3.3.1 and TS 3.3.2 to reflect the specific functions that have bypass test capability installed and the specific functions that do not have bypass test capability installed. The current wording is no longer applicable because the installation and implementation of the bypass test instrumentation modifications for certain functions have been completed.
2.0 REGULATORY EVALUATION
The NRC staff determined that the licensee, in Section 4.1 of its submittal, identified the applicable regulatory requirements. The regulatory requirements for which the staff based its acceptance are as follows.
Enclosure Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.36(c)(2)(ii)(C) requires, in part, that a TS limiting condition for operation (LCO) be established for a structure, system, or component that is part of the primary success path and that functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
3.0 TECHNICAL EVALUATION
3.1 TS 3.3.1 Condition D Required Action Notes Current Text:
- 1. For Functions with installed bypass test capability, one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
- 2. For Functions with no installed bypass test capability, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment of other channels.
Revised Text:
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
Evaluation The licensee in its March 14, 2011 (ADAMS Accession No. ML110760088), letter, identifies that Condition D applies to the Power Range Neutron Flux-High function.
The NRC staff by amendment dated April9, 2012 (ADAMS Accession No. ML120950371), approved installed bypass capability for Power Range Neutron Flux.
In its April17, 2014, submittal, the licensee states that Power Range Neutron Flux-High function has been modified to have installed bypass capability.
Based on the above NRC evaluation, the NRC staff determined that the wording regarding functions with no installed bypass test capability no longer applies and should be removed for clarification. The NRC staff, therefore, concludes that the revised text is consistent with the currently installed function capability and is acceptable.
Condition E Required Action Notes Current Text:
- 1. For Functions with installed bypass test capability, one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
- 2. For Functions with no installed bypass test capability, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment of other channels.
Revised Text:
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
Evaluation The licensee in its April17, 2014, application, identified that ConditionE applies to the following functions:
Power Range Neutron Flux-Low; Overtemperature ~ T; Overpower ~T; Power Range Neutron Flux-High Positive Rate; and SG Water Level-Low Low.
The NRC staff by amendment dated April 9, 2012, approved installed bypass capability for the above listed functions. In its April 17, 2014, submittal, the licensee states that the above listed functions have been modified to have installed bypass capability.
Based on the above NRC evaluation, the NRC staff determined that the wording regarding functions with no installed bypass test capability no longer applies and should be removed for clarification. The NRC staff, therefore, concludes that the revised text is consistent with the currently installed function capability and is acceptable.
Condition K Required Action Notes Current Text:
- 1. For Functions with installed bypass test capability, one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
- 2. For Functions with no installed bypass test capability, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
Revised Text:
- 1. For Functions with installed bypass test capability (Functions Sa, 9, and 1 0), one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
- 2. For Functions with no installed bypass test capability (Functions 12 and 13), the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
Evaluation The licensee in its April 17, 2014, application, identified that Condition K applies to the following functions:
o Function 8a o Function 9 o
Function 10 o
Function 12 o
Function 13 Pressurizer Pressure-Low Pressurizer Water Level - High Reactor Coolant Flow - Low Undervoltage Reactor Coolant Pumps Underfrequency Reactor Coolant Pumps The NRC staff by amendment dated April 9, 2012, approved installed bypass capability for:
Function 8a Function 9 Function 10 Pressurizer Pressure-Low Pressurizer Water Level - High Reactor Coolant Flow - Low In its April17, 2014, submittal, the licensee stated that the above three functions have been modified to have installed bypass capability. The revised text provides clarification wording to specify Functions 12 and 13.
Based on the above NRC evaluation, the NRC staff determines that the wording regarding functions with installed bypass test capability is applicable to Functions 8a, 9, and 10 and that the wording regarding the functions with no installed bypass test capability is applicable to Functions 12 and 13. The NRC staff, therefore, concludes that the revised text is consistent with the function capability and is acceptable.
3.2 TS 3.3.2 Condition D Required Action Notes Current Text:
- 1. For Functions with installed bypass test capability, one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
- 2. For Functions with no installed bypass test capability, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment of other channels.
Revised Text:
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment.
Evaluation The licensee in its April17, 2014, application, identified that Condition D applies to the following functions:
Containment Pressure-High 1; Pressurizer Pressure-Low; Steam Line Pressure-Low; Containment Pressure-High 2; Steam Line Pressure-Negative Rate-High; SG Water Level-Low Low; and SG Water Level-High High (P-14).
The NRC staff by amendment dated April 9, 2012, approved installed bypass capability for the above functions. In its April17, 2014, submittal, the licensee stated that the above functions have been modified to have installed bypass capability.
Based on the above NRC evaluation, the NRC staff determined that the wording regarding functions with no installed bypass test capability no longer applies and should be removed for clarification. The NRC staff, therefore, concludes that the revised text is consistent with the currently installed function capability and is acceptable.
Condition K Required Action Notes Current Text:
- 1.
For Functions with installed bypass test capability, one channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
- 2.
For Functions with no installed bypass test capability, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
Revised Text:
One channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing.
Evaluation The licensee in its March 14, 2011, letter, identifies that Condition K applies the Refueling Water Storage Tank Level-Low Low function. The NRC staff by amendment dated April9, 2012, approved installed bypass capability for the Refueling Water Storage Tank Level-Low Low function. In its April17, 2014, submittal, the licensee states that the Refueling Water Storage Tank Level-Low Low function has been modified to have installed bypass capability.
Based on the above NRC evaluation, the NRC staff determined that the wording regarding functions with no installed bypass test capability no longer applies and should be removed for clarification. The NRC staff, therefore, concludes that the revised text is consistent with the currently installed cuntion capability and is acceptable.
Based on the above, the NRC staff concludes that the TS revisions did not change LCOs, surveillances, or other TS requirements. The revisions removed text that was no longer applicable and inserted text to specifically identify TS required functions that have bypass test capability. Therefore the NRC staff concludes that the TSs with the requested revisions continue to meet 10 CFR 50.36(c)(2)(ii)(C) requirements.
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 make editorial and minor revisions to the license that do not change requirements or intent. 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 FA 42546; July 22, 2014). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 O)(v). Pursuant to 10 CFR 51.22(1 O)(v) 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: Joel S. Wiebe.
Date of issuance: December 7, 2014