ML14085A532
| ML14085A532 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Clinton, Quad Cities, LaSalle  (DPR-019, DPR-025, DPR-029, DPR-030, DPR-062, NPF-011, NPF-018, NPF-037, NPF-066, NPF-072, NPF-077) |
| Issue date: | 07/21/2014 |
| From: | Joel Wiebe Plant Licensing Branch III |
| To: | Pacilio J Exelon Generation Co |
| Joel Wiebe, NRR/DORL 415-6606 | |
| References | |
| TAC MF2679, TAC MF2680, TAC MF2681, TAC MF2682, TAC MF2683, TAC MF2684, TAC MF2685, TAC MF2686, TAC MF2687, TAC MF2688, TAC MF2689 | |
| Download: ML14085A532 (60) | |
Text
Mr. Michael J. Pacilio Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 21, 2014 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2-ISSUANCE OF AMENDMENTS RE: ADOPTION OF TSTF-522 VENTILATION SYSTEM SURVEILLANCE REQUIREMENTS (TAC NOS. MF2679, MF2680, MF2681 I MF2682, MF2683, MF2684, MF2685, MF2686, MF2687, MF2688, AND MF2689)
Dear Mr. Pacilio:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 177 to Facility Operating License No. NPF-72 and Amendment No 177 to Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2; and Amendment No. 183 to Facility Operating License No. NPF-37; and Amendment No. 183 to Facility Operating License No.
NPF-66 for the Byron Station, Unit Nos 1 and 2; and Amendment No. 201 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No. 1; and Amendment No. 241 to Renewed Facility Operating License No. DPR-19 and Amendment No. 234 to Renewed Facility Operating License No. DPR-25 for Dresden Nuclear Power Station, Units 2 and 3; and Amendment No. 208 to Facility Operating License No. NPF-11 and Amendment No. 195 to Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2; and Amendment No. 252 to Renewed Facility Operating License No. DPR-29 and Amendment No. 247 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2. The amendments are in response to your application dated September 3, 2013 (Agencywide Documents Access and Management System Accession No. ML13246A321).
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, STN 50-455, 50-461, 50-237, 50-249, 50-373, 50-37 4, 50-254, and 50-265
Enclosures:
- 1.
Amendment No. 177 to NPF-72
- 2.
Amendment No. 177 to NPF-77
- 3.
Amendment No. 183 to NPF-37
- 4.
Amendment No. 183 to NPF-66
- 5.
Amendment No. 201 to DPR-62
- 6.
Amendment No. 241 to DPR-19
- 7.
Amendment No. 234 to DPR-25
- 8.
Amendment No. 208 to NPF-11
- 9.
Amendment No. 195 to NPF-18
- 10. Amendment No. 252 to DPR-29
- 11. Amendment No. 247 to DPR-30
- 12. Safety Evaluation cc w/encls: Listserv Sincerely,
~cJ;?-
oel S. Wiebe, Senior Project Manager lant 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. 177 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 September 3; 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 lrcense 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. 177 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 105 days of the date of issuance.
Attachment:
Changes to the Facility Operating License FOR THE NUCLEAR REGULA TORY COMMISSION Travis L. Tate, Chief Plant Licensing II 1-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: -July 21, 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. 177 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 September 3, 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. 177 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 of its issuance and shall be implemented within 1 05 days of the date of issuance.
Attachment:
Changes to the Facility Operating License 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 Date of Issuance:
July 21, 2014
ATTACHMENT TO LICENSE AMENDMENT NOS. 177. AND 177 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 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 3.7.10-3 License NPF-72 Page 3 License NPF-77 Page 3 TSs 3.7.10-3 (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 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. Attachment 1 is hereby incorporated into this license.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 177 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. 177 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 Attachment 1 to this license. The items identified in 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. 177 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 provision of 10 CFR Section 50.54(s)(2) will apply.
Amendment No. 177
VC Filtration System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION E.
Two VC Filtration E.l Suspend movement of System trains irradiated fue 1 inoperable in MODE 5 assemblies.
or 6, or during movement of irradiated AND fuel assemblies.
E.2 Suspend positive OR reactivity additions.
One or more VC Filtration System trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.
F.
Two VC Filtration F.1 Enter LCD 3.0.3.
System trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.
SURVEILLANCE REQUIREMENTS SR 3.7.10.1 SURVEILLANCE Operate each VC Filtration System train with:
- a.
Flow through the makeup system filters for ~ 15 continuous minutes with the heaters operating; and
- b.
Flow through the recirculation charcoal adsorber for ~ 15 minutes.
BRAIDWOOD - UNITS 1 & 2 3.7.10-3 CC>>1PLETION TIME Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
Amendment 1 7 7
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. 183 License No. NPF-37
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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. 183 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 105 days of the date of issuance.
Attachment:
Changes to the Facility Operating License FOR THE NUCLEAR REGULA TORY COMMISSION (jj_ /vJL w Travis L. Tate, Chief Plant Licensing II 1-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: July 21, 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. 183 License No. NPF-66
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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 The Technical Specifications contained in Appendix A as revised through Amendment No. 183 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 105 days of the date of issuance.
Attachment:
Changes to the Facility Operating License FOR THE NUCLEAR REGULA TORY COMMISSION Travis L. Tate, Chief Plant Licensing II 1-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: July 21, 2014
ATTACHMENT TO LICENSE AMENDMENT NOS. 183 AND 183 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 Licenses 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 3.7.10-3 License NPF-37 Page 3 License NPF-66 Page 3 TSs 3.7.10-3 (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 or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This 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. 183 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. 183 (3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This 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. 183 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)
Deleted.
(4)
Deleted.
(5)
Deleted.
Amendment No. 183
VC Filtration System 3.7.10 ACTIONS (continued)
CONDITION REQUIRED ACTION E.
Two VC Filtration E.l Suspend movement of System trains irradiated fuel inoperable in MODE 5 assemblies.
or 6, or during movement of AND irradiated fue 1 assemblies.
E.2 Suspend positive reactivity additions.
QR One or more VC Filtration System trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.
F.
Two VC Filtration F.1 Enter LCD 3.0.3.
System trains inoperable in MODE 1,
- 2. 3, or 4 for reasons other than Condition B.
SURVEILLANCE REQUIREMENTS SR 3.7.10.1 SURVEILlANCE Operate each VC Filtration System train with:
- a.
Flow through the makeup system filters for 2 15 continuous minutes with the heaters operating; and
- b.
Flow through the recirculation charcoal adsorber for~ 15 minutes.
BYRON - UNITS 1 & 2 3.7.10- 3 COMPLETION TIME Inmediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
Amendment 18 3
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 201 License No. NPF-62
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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-62 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 201, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
Attachment:
Changes to the Facility Operating License 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 Date of Issuance: July 21, 2014
ATIACHMENT TO LICENSE AMENDMENT NO. 201 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following pages of the Facility Operating License with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-62 Page 3 TSs 3.6-53 3.7-6 License NPF-62 Page 3 TSs 3.6-53 3.7-6 (4)
Exelon Generation Company, pursuant to the Act and to 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (6)
Exelon Generation Company, pursuant to the Act and 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. Mechanical disassembly of the GE14i isotope test assemblies containing Cobalt-60 is not considered separation; and (7)
Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, to intentionally produce, possess, receive, transfer, and use Cobalt-60.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 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 Exelon Generation Company is authorized to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, as revised through Amendment No. 201 are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 201
ACTIONS (contlnued)
CONDITION REQUIRED ACTION SGT System 3.6.4.3 COMPLETION TIME E.
Two SGT subsystems E. 1 Suspend movement of Immediately inoperable during recently irradiated movement of recently irradiated fuel fuel assemblies in the primary and secondary assemblies 1n the containmer,t.
primary or secondary containment, or during AND OPDRVs.
E.2 Initiate action to suspend OPDRVs.
SURVEILLANCE REQUIREMENTS SR 3.6.4.3.1 SR 3.6.4.3.2 SR 3.6.4.3.3 SR 3.6.4.3.4 CLINTON SURVEILLANCE Operate each SGT subsystem for
~ 15 continuous minutes with heaters operating.
Perform required SGT filter testing 1n accordance with the Ventilation Filter Testing Program (VFTP).
verify each SGT subsystem actuates on an actual or simulated initiation signal.
Verify each SGT filter cooling bypass damper can be opened and the fan started.
3.6-53 Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance w1 th lhe VFTP In accordance with the Survei} lance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 2 01
Control Room Ventilation System 3.7.3 ACTIONS (continued)
CONDITION REQUIRED ACTION G.
Two Control Room G.l Suspend movement of irradiated fuel assemblies in the primary and secondary containment.
OR ventilation subsystems inoperable during movement of irradiated fuel assemblies in the primary or secondary containment, during
~
CORE ALTERATIONS, or during OPDRVs.
G.2 AND One or more Control Room Ventilation G.3 subsystems inoperable due to inoperable CRE boundary during movement of irradiated fuel assemblies in the primary or secondary containment, during CORE ALTERATIONS, or during OPDRVs.
Suspend CORE ALTERATIONS.
Initiate action to suspend OPDRVs.
SURVEILLANCE REQUIREMENTS SR 3.7.3.1 SR 3.7.3.2 CLINTON SURVEILLANCE Operate each Control Room Ventilation subsystem with flow throu9h the makeup filter for ~ 15 continuous minutes with the heaters operating.
Operate each Control Room Ventilation subsystem with flow through the recirculation filter for ~ 15 minutes.
3.7-6 COMPLETION TIME Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment No. 201
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 241 License No. DPR-19
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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. DPR-19 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through*
Amendment No. 241, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULA TORY COMMISSION nJ, ~
L 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 Renewed Facility Operating License Date of Issuance: July 21, 2014
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 234 License No. DPR-25
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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 activitres authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 234, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULA TORY COMMISSION th ~
J2 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 Renewed Facility Operating License Date of Issuance:
July 21, 2014
ATTACHMENT TO LICENSE AMENDMENT NOS. 241 AND 234 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Replace the following pages of the Facility Operating Licenses with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License DPR-19 Page 3 License DPR-25 Page4 TSs 3.6.4.3-3 3.7.4-3 License DPR-19 Page 3 License DPR-25 Page 4 TSs 3.6.4.3-3 3.7.4-3 (2)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear materials as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended; (3)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct special nuclear materials as may be produced by the operation of the facility.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2957 megawatts thermal (1 00 percent rated power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 241, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Operation in the coastdown mode is permitted to 40% power.
Renewed License No. DPR-19 Amendment No. 241
- f.
Surveillance Requirement 4.9.A.10- Diesel Storage Tank Cleaning (Unit 3 and Unit 2/3 only)
Each of the above Surveillance Requirements shalf be successfully demonstrated prior to entering into MODE 2 on the first plant startup following the fourteenth refueling outage (D3R14).
- 3.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A.
Maximum Power Level The licensee is authorized to operate the facility at steady state power levels not in excess of 2957 megawatts (thermal), except that the licensee shalf not operate the facility at power levels in excess of five (5) megawatts (thermal), until satisfactory completion of modifications and final testing of the station output transformer, the auto-depressurization interlock, and the feedwater system, as described in the licensee's telegrams; dated February 26,1971, have been verified in writing by the Commission.
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 234, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Reports The licensee shall make certain reports in accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Restrictions Operation in the coastdown mode is permitted to 40% power.
Renewed License No. DPR-25 Amendment No. 234
SURVEJLLANCE REOUJREMENTS SR 3.6.4.3.1 SR 3.6.4.3.2 SR 3.6.4.3.3 SURVEILLANCE Operate each SGT subsystem for
~ 15 continuous m1nutes with heaters operating.
Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTPl.
Verify each SGT subsystem actuates on an actual or simulated initiation signal.
SGT System 3.6.4.3 FREQUENCY In accordance wHh the Surveillance Frequency Control Program In accordance with the VFTP ln accordance with the Surveillance Frequency Control Program Dresden 2 and 3 3.6.4.3-3 Amendment No. 241/234
SURVEILLANCE REQUIREMENTS SR 3.7.4.1 SR 3.7.4.2 SR 3.7.4.3 SR 3.7.4.4 SURVEILLANCE Operate the CREV System for ~ 15 continuous minutes with the heaters operating.
Perform required CREV filter testing in accordance with the Ventilation Filter Testing Program CVFTP).
Verify the CREV System actuates on a manual initiation signal.
Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.
CREV System
- 3. 7. 4 FREQUENCY Jn accordance with the Surveillance Frequency Control Program In accordance with the VFTP In accordance with the Survei 11 ance Frequency Control Program In accordance with the Control Room Envelope Habitabi 1 ity Program Dresden 2 and 3 3.7.4-3 Amendment No. 241/234
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY. LLC DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 208 License No. NPF-11
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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 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 set forth in 10 CFR Chapter I; 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 rn 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-11 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 208, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in 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.
Attachment:
Changes to the Facility Operating License 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 Date of Issuance: July 21, 2014
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-37 4 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 195 License No. NPF-18
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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 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 set forth in 10 CFR Chapter I; 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-18 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in 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.
Attachment:
Changes to the Facility Operating License 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 Date of Issuance: July 21, 2014
ATTACHMENT TO LICENSE AMENDMENT NOS. 208 AND 195 FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18 DOCKET NOS. 50-373 AND 50-374 Replace the following pages of the Facility Operating Licenses with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-11 Page 3 License NPF-18 Page 3 TSs 3.6.4.3-3 3.7.4-3 3.7.4-4 License NPF-11 Page 3 License NPF-18 Page 3 TSs 3.6.4.3-3 3.7.4-3 3.7.7-4
Am.146 01/12/01 Am. 202 07/21/11 (4)
(5) License No, NPF-11 Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2 and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
C.
This 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 thereafter in effect; and is subject to the additional conditions specified or incorporated below:
Am. 198 09/16/10 Am. 208 07/21/14 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 Am. 194 08/28/09 (1)
(2)
(3)
(4)
(5)
(6)
(7)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal).
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 208, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
DELETED DELETED DELETED DELETED DELETED Amendment No. 208 License No. NPF-18 Am. 189 (5)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70 possess, but not 07/21/11 separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2, and such Class B and Class C low-level radioactive waste as may be produced by the operation of Braidwood Station, Units 1 and 2, Byron Station, Units 1 and 2, and Clinton Power Station, Unit 1.
C.
This 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:
Am. '185 (1) 09/1El/1 0 Am. 195 (2) 07/21/14 Am. 181 (3) 08/28/09 Am. 181 (4) 08/28/09 Am. 181 08/28/09 (5)
Am. 181 (6) 08/28/09 Am. 181 (7) 08/28/09 Am. 181 (8) 08/28/09 Am. 181 (9) 08/28/09 Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3546 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
DELETED DELETED DELETED DELETED DELETED DELETED DELETE Amendment No. 195
ACTIONS CONDITION REQUIRED ACTION E.
(continued>
E.2 E.3 Suspend CORE ALTERATIONS.
Initiate action to suspend OPORVs.
SURVEILLANCE REQUIREMENTS SR 3.6.4.3.1 SR 3.6.4.3.2 SR 3.6.4.3.3 SURVEILLANCE Operate each SGT subsystem for
~ 15 continuous minutes with heaters operating.
Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
Verify each SGT subsystem actuates on an actual or simulated initiation signal.
SGT System 3.6.4.3 COMPLETION TIME Immediately Immediate 1 y FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance wHh the VFTP In accordance with the Surveillance Frequency Control Program LaSalle 1 and 2 3.6.4.3-3 Amendment No. 2081195
ACTIONS CONDITION REQUIRED ACTION CRAF System 3.7.4 COMPLETION T lME F.
Two CRAF subsystems inoperable during
*--NOT£------***----
LCO 3.0.3 is not applicable.
movement of irradiated fuel assemblies in the secondary containment.
F.l during COR£ ALTERATIONS, or during OPDRVs.
One or more CRAF subsystems inoperable F.2 due to inoperable CRE boundary during movement of irradiated ANn fuel assemblies in the secondary containment, F.3 during CORE ALTERATIONS, or during OPDRVS.
SURVEILLANCE REQUIREMENTS Suspend movement of irradiated fuel assemblies in the secondary containment.
Suspend COR£ ALTERATIONS.
Initiate action to suspend OPDRVs.
SURVEILLANCE SR 3.7.4.1 LaSalle 1 and 2 Operate each CRAF subsystem for
~ 15 continuous minutes with the heaters operating.
3.7.4-3 Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
Amendment No. 2§-8 /19 5
SURVEILLANCE REQUIREMENTS SR 3.7.4.2 SR 3.7.4.3 SR 3.7.4.4 SR 3.7.4.5 SURVEILLANCE Manually initiate flow through the CRAF
,recirculation filters for<! 15 minutes.
Perform required CRAF filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
Verify each CRAF subsystem actuates on an actual or simulated initiation signal.
Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.
CRAF System 3.7.4 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the VFTP In accordance with the Surveillance Frequency Control Program In accordance with the Control Room Envelope Habitability Program LaSalle 1 and 2 3.7.4-4 Amendment No. 208/195
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 252 Renewed License No. DPR-29
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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 3.8 of Facility Operating License No. DPR-29 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULA TORY COMMISSION Travis L. Tate, Chief Plant Licensing II 1-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License Date of Issuance: July 21, 2014
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET N0.50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 24 7 Renewed License No. DPR-30
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated September 3, 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 3.8 of Facility Operating License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 247, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 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 Renewed Facility Operating License Date of Issuance: July 21, 2014
ATTACHMENT TO LICENSE AMENDMENT NOS. 252 AND 247 RENEWED FACILITY OPERATING LICENSES NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Facility Operating Licenses with the attached pages. The revised pages are identified by number and contain marginal lines indicating the areas of change.
Remove License DPR-29 Page 4 License DPR-30 Page4 TSs 3.6.4.3-3 3.7.4-3 License DPR-29 Page 4 License DPR-30 Page 4 TSs 3.6.4.3-3 3.7.4-3 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252, are hereby incorporated into this renewed operating license.
The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined sets of plans\\ which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The Exelon Generation Company CSP was approved by License Amendment No.
247.
F.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979, with supplements dated November 5, 1980, and 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-29 Amendment No. 252 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 247, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D.
Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.
Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP),
including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Exelon Generation Company CSP was approved by License Amendment No. 244.
F.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Renewed License No. DPR-30 Amendment No. 247
SURVEILLANCE REQUIREMENTS SR 3.6.4.3.1 SR 3.6.4.3.2 SR 3.6.4.3.3 SURVEILLANCE Operate each SGT subsystem for
~ 15 continuous minutes with heaters operating.
Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
Verify each SGT subsystem actuates on an actual or simulated initiation signal.
SGT System 3.6.4.3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the VFTP In accordance with the Surveillance Frequency Control Program Quad Cities 1 and 2 3.6.4.3-3 Amendment No.
252/247
CREV System 3.7.4 SURVEILLANCE REQUIREMENTS SR 3.7.4.1 SR 3.7.4.2 SR 3.7.4.3 SR 3.7.4.4 SURVE lLLANCE FREQUENCY Operate the CR£V System for ~ 15 continuous In accordance minutes with the heaters operating.
with the Surveillance Frequency Control Program Perform required CREV f1lter testing in accordance with the Venti1ation Filter 1esting Program (VFTP).
Verify the CREV System isolation dampers close on an actual or simulated initiation signal.
Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program.
In accordance with the VFTP In accordance with the Surveillance Frequency Control Program rn accordance with the Control Room Envelope Habitability Program Quad Cities 1 and 2 3.7.4-3 Amendment. 252/247
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 177 TO FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO. 177 TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 183 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 183 TO FACILITY OPERATING LICENSE NO. NPF-66, AMENDMENT NO. 201 TO FACILITY OPERATING LICENSE NO. NPF-62, AMENDMENT NO. 241 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-19, AMENDMENT NO. 234 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-25, AMENDMENT NO. 208 TO FACILITY OPERATING LICENSE NO. NPF-11, AMENDMENT NO. 195 TO FACILITY OPERATING LICENSE NO. NPF-18, AMENDMENT NO. 252 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29, AMENDMENT NO. 247 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30, EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 CLINTON POWER STATION, UNIT NO. 1 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 LASALLE COUNTY STATION, UNITS 1 AND 2 QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, STN 50-455, 50-461, 50-237, 50-249, 50-373, 50-374, 50-254, AND 50-265 2
1.0 INTRODUCTION
By letter dated September 3, 2013 (Agencywide Documents Access and Management System ADAMS) Accession No. ML13246A321 ), Exelon Generation Company, LLC (the licensee) requested changes to the technical specifications (TSs) for Braidwood Station, Units 1 and 2; Byron Station, Unit Nos. 1 and 2; Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; LaSalle County Station, Units 1 and 2; and Quad Cities Nuclear Power Station, Units 1 and 2. Specifically the licensee requested to adopt U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Standard Technical Specifications (STS) Change Traveler TSTF-522, "Revise Ventilation System Surveillance Requirements to Operate for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per Month", dated March 30, 2010 (ADAMS Accession No. ML100890316).
The proposed changes would revise TS surveillance requirements (SRs) that currently require operating ventilation systems (the specific ventilation systems and their TS are identified below) for at least 10 continuous hours with the heaters operating at a frequency controlled in accordance with the Surveillance Frequency Control Program (SFCP). The SRs would be changed to require at least 15 continuous minutes of ventilation system operation at a frequency controlled in accordance with the SFCP.
The licensee stated that the license amendment request is consistent with NRC-approved TSTF-522. The availability of this TS improvement was announced in the Federal Register on September 20, 2012 (77 FR 58421 ), as part of the consolidated line item improvement process.
2.0 REGULATORY EVALUATION
One of the reasons air filtration and adsorption systems are required at nuclear power plants is to lower the concentration of airborne radioactive material that may be released from the site to the environment due to a design basis event. Lowering the concentration of airborne radioactive materials can mitigate doses to plant operators and members of the public during a design basis event. A typical system consists of ventilation ductwork, fans, dampers, valves, instrumentation, prefilters or demisters, high-efficiency particulate air (HEPA) filters, heaters, and activated charcoal adsorbers. These systems are tested by operating the systems and monitoring the response of the overall system as well as individual components. Laboratory tests of charcoal adsorbers are also performed to ensure the charcoal adsorbs an acceptable amount of radioactive gasses.
The regulatory requirements for design and testing of these systems are contained in Title 10 of the Code of Federal Regulations (1 0 CFR) Section 50.67 and Part 100, as well as Part 50, Appendix A, "General Design Criteria [GDC] for Nuclear Power Plants," GDCs 19, 41, 42, 43, and 61.
Regulatory Guide (RG) 1.52, Revision 2, "Design, Testing, and Maintenance Criteria for Post-Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorbtion Units of Light-Water-Cooled Nuclear Power Plants" (ADAMS Accession No. ML003740139),
was published in March 1978 to provide guidance and criteria acceptable to the NRC staff for licensees to implement the regulations in 10 CFR related to air filtration and adsorption systems.
Regulatory Position 4.d of Revision 2 of RG 1.52 provides guidance that "Each ESF [engineered safety feature] atmosphere cleanup train should be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per month, with the heaters on (if so equipped), in order to reduce the buildup of moisture on the adsorbers and HEPA filters." The purpose of this guidance is to minimize the moisture content in the system and, thereby, enhance efficiency in the event the system is called upon to perform its design basis function.
Subsequent to the issuance of the above guidance, the NRC staff determined that 10 continuous hours of system operation would dry out the charcoal adsorber for a brief period of time but following heater de-energization the level of moisture accumulation in adsorbers would rapidly return to the pre-test level. The NRC staff subsequently issued NRC Generic Letter (GL) 99-02: "Laboratory Testing of Nuclear-Grade Activated Charcoal" (ADAMS Accession No. ML082350935, and errata sheet at ADAMS Accession No. ML031110094). GL 99-02 requested licensees to confirm that their charcoal testing protocols accurately reflect the adsorber gaseous activity capture capability. GL 99-02 also requested the licensees to account for the effects of moisture accumulation in adsorbers.
The NRC staff updated RG 1.52 to include the new information (ADAMS Accession No. ML011710176). RG 1.52, Revision 3, Regulatory Position 6.1, states, "Each ESF atmosphere cleanup train should be operated continuously for at least 15 minutes each month, with the heaters on (if so equipped), to justify the operability of the system and all its components."
One of the reasons for the previous 1 0-hour requirement for ventilation system operation with heaters operating was to minimize the effects of moisture on the adsorber's ability to capture gaseous activity. However, these effects are already accounted for in the Ventilation Filter Testing Program (VFTP) at each facility as described below.
The NRC's regulatory requirements related to the content of the TS are contained in 10 CFR 50.36. The regulations at 10 CFR 50.36 require that the TS include items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. SRs are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.
The NRC's guidance for the format and content of licensee TSs can be found in NUREG-1431, "Standard Technical Specifications Westinghouse Plants," NUREG-1433, "Standard Technical Specifications General Electric Plants, BWR/4," and NUREG-1434, "Standard Technical Specifications General Electric Plants, BWR/6."
3.0 TECHNICAL EVALUATION
The NRC staff evaluated the licensee's proposed change against the applicable regulatory guidance in RG 1.52, Revision 3, guidance in the STS as modified by TSTF-522, and the regulatory requirements of 10 CFR 50.36.
The licensee proposed the following changes to the SRs:
Braidwood, Units 1 and 2 SR 3.7.10.1 Replace:
With:
- a. Flow through the makeup system filters for<:: 10 continuous hours with the heaters operating; and
- a. Flow through the makeup system filters for<:: 15 continuous minutes with the heaters operating; and The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1431 by TSTF-522. Therefore, the NRC staff finds that the proposed changes are consistent with guidance in the NUREG-1431, as modified by TSTF-522.
Byron, Unit Nos. 1 and 2 SR3.7.10.1 Replace:
With:
- a. Flow through the makeup system filters for <:: 10 continuous hours with the heaters operating; and
- a. Flow through the makeup system filters for <:: 15 continuous minutes with the heaters operating; and The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1431 by TSTF-522. Therefore, the NRC staff finds that the proposed changes are consistent with guidance in the NUREG-1431, as modified by TSTF-522.
Clinton, Unit 1 SR 3.6.4.3.1 Replace:
With:
Operate each SGT subsystem for<:: 10 continuous hours with heaters operating Operate each SGT subsystem for <:: 15 continuous minutes with heaters operating.
SR 3.7.3.1 Replace:
Operate each control room ventilation subsystem with flow through the makeup filter for<:: 10 continuous hours with the heaters operating.
With: Operate each Control Room Ventilation subsystem with flow through the makeup filter for~ 15 continuous minutes with the heaters operating.
The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1434 by TSTF-522. Therefore, the NRC staff finds that the proposed changes are consistent with guidance in the NUREG-1434, as modified by TSTF-522.
Dresden, Units 2 and 3 SR 3.6.4.3.1 Replace:
With:
Operate each SGT subsystem for~ 10 continuous hours with heaters operating.
Operate each SGT subsystem for ~ 15 continuous minutes with heaters operating.
SR 3.7.4.1 Replace:
With:
Operate the CREV system for ~ 10 continuous hours with the heaters operating.
Operate the CREV system for ~ 15 continuous minutes with the heaters operating.
The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1433 by TSTF-522. Therefore, the NRC staff finds that the proposed changes are consistent with guidance in the NUREG-1433, as modified by TSTF-522.
LaSalle, Units 1 and 2 SR 3.6.4.3.1 Replace:
With:
Operate each SGT subsystem for~ 10 continuous hours with heaters operating.
Operate each SGT subsystem for ~ 15 continuous minutes with heaters operating.
SR 3.7.4.1 Replace:
Operate each CRAF subsystem for ~ 10 continuous hours with the heaters operating.
With: Operate each control room area infiltration (CRAF) subsystem for;:::: 15 continuous minutes with the heaters operating.
SR 3.7.4.2 Replace:
Manually initiate flow through the CRAF recirculation filters for 2: 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> With:
Manually initiate flow through the CRAF recirculation filters for 2: 15 minutes The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1434 by TSTF-522. Therefore, the NRC staff finds that the proposed changes are consistent with guidance in the NUREG-1434, as modified by TSTF-522.
Quad Cities, Units 1 and 2 SR 3.6.4.3.1 Replace:
With:
Operate each SGT subsystem for 2: 10 continuous hours with heaters operating.
Operate each SGT subsystem for 2: 15 continuous minutes with heaters operating.
SR 3.7.4.1 Replace:
With:
Operate the CREV system for 2: 10 continuous hours with the heaters operating.
Operate the CREV system for 2: 15 continuous minutes with the heaters operating.
The proposed changes adopt the TS format and content, to the extent practicable, contained in the changes made to NUREG-1433 by TSTF-522. Therefore, the NRC staff finds that the proposed changes are consistent with guidance in the NUREG-1433, as modified by TSTF-522.
The proposed changes require at least 15 minutes of system operation. Therefore, NRC staff found that the proposed change is consistent with guidance in RG 1.52, Revision 3.
The NRC staff compared the proposed changes to the existing SRs as well as the regulatory requirements of 10 CFR 50.36. The existing SRs provide assurance that the necessary quality of ventilation systems and components will be maintained and that the LCOs will be met. The proposed changes reduce the amount of required system operational time from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to 15 minutes. The 1 0-hour operational requirement for heaters was based on using the SR to eliminate moisture in the adsorbers and thus ensure the adsorbers would capture gaseous activity. The effects of moisture on the adsorber's ability to capture gaseous activity are now accounted for in the licensee's VFTP by performing testing in a manner to account for the effects of moisture on the adsorbers ability to capture gaseous activity. The VFTP requirements are contained in the TS as follows: Braidwood-5.5.11, Byron-5.5.11, Clinton-5.5.7, Dresden-5.5.7, LaSalle-5.5.8, and Quad Cities-5.5.7, and require testing at a specific temperature and relative humidity value to account for the effects of moisture. Since the SRs are no longer relied upon to ensure the effects of moisture on the adsorber's ability to capture gaseous activity are accounted for, the 1 0-hour heater operational requirement is unnecessary.
The NRC staff found that reducing the required minimum system operation time to 15 minutes, consistent with RG 1.52, Revision 3, in conjunction with the VFTP, is sufficient to justify operability of the system and all its components. The NRC staff found that the proposed SR meets the regulatory requirements of 10 CFR 50.36 because it provides assurance that the necessary quality of ventilation systems and components will be maintained and that the LCO will be met. Based on the above, the NRC staff determined that the TS SR changes identified above are acceptable.
The regulation at 10 CFR 50.36 states: "A summary statement of the bases or reasons for such specifications shall also be included in the application, but shall not become part of the technical specifications." 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 for Braidwood and Byron Stations; TS 5.5.11 for Clinton and LaSalle Stations; and TS 5.5.1 0 for Dresden and Quad Cities Stations. Accordingly, along with the proposed TS changes, the licensee also submitted TS Bases changes corresponding to the proposed TS changes. The staff notes that submitted TS Bases changes are consistent with the proposed TS changes and provide the purpose for each requirements in each specification consistent with the Commission's Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 2, 1993 (58 FR 39132). However, the staff did not review the TS Bases for approval.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official comments were supportive of the amendment.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change surveillance requirements with respect to how long to test ventilation systems. The NRC staff has determined that the amendment involves 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 (78 FR 77732, dated December 24, 2013). 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 NRC staff 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) 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 Date of issuance: July 21, 2014
ML14085A532 LPL3-2 R/F RidsNrrDorllpl3-2 Resource RidsNrrPMByron Resource RidsNrrLASRohrer Resource RidsNrrPMCiinton Resource RidsRgn1 MaiiCenter Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl1-2 Resource
- via memo OFFICE LPL3-2/PM LPL3-2/LA STSB OGC/NLO LPL3-2/BC NAME JWiebe SRohrer REIIiott MYoung TTate DATE 7/15/14 7/21/14 2/28/14 5/21/14 7/27/14