ML083120487
| ML083120487 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/03/2008 |
| From: | David M Plant Licensing Branch III |
| To: | Pardee C Exelon Nuclear |
| David, Marshall - DORL 415-1547 | |
| References | |
| TAC MD8447, TAC MD8448, TAC MD8449, TAC MD8450 | |
| Download: ML083120487 (20) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 3,2008 Mr. Charles G. Pardee President and Chief Nuclear Officer 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 RE: REVISION TO TECHNICAL SPECIFICATIONS FOR ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (TAC NOS. MD8447, MD8448, MD8449, AND MD8450)
Dear Mr. Pardee:
The Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 154 to Facility Operating License No. NPF-72 and Amendment No. 154 to Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, and Amendment No. 159 to Facility Operating License No. NPF-37 and Amendment No. 159 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 March 18, 2008.
The amendments revise the numbering scheme of Surveillance Requirements (SRs) 3.3.2.6 and 3.3.2.7 for Technical Specification 3.3.2, "Engineered Safety Feature Actuation System (ESFAS)
Instrumentation," to correct inconsistencies introduced in previous license amendments issued by the Commission. The amendments also supersede the 120-day period for implementation of the changes to SRs 3.3.2.6 and 3.3.2.7, approved in the previous license amendments.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
~ S?~;J:4!t Mar~1I ~-';David, Senior roject Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket l\\Ios. STN 50-456, STN 50-457, STN 50-454, and STN 50-455
Enclosures:
- 1. Amendment No. 154 to NPF-72
- 2. Amendment No. 154 to NPF-77
- 3. Amendment No. 159 to NPF-37
- 4. Amendment No. 159 to NPF-66
- 5. Safety Evaluation cc w/encls: Distribution via ListServ
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 l'Jo. 154 License No. NPF-72
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated March 18, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
- 2 (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 154, 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 30 days of the date of issuance. This implementation period supersedes the 120-day period for implementation of the changes to SRs 3.3.2.6 and 3.3.2.7, approved in Amendment No. 148.
FOR THE NUCLEAR REGULATORY COMMISSION Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance: December 3, 2008
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. 154 License No. NPF-77
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated March 18, 2008, 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 (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 154, 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.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance. This implementation period supersedes the 120-day period for implementation of the changes to SRs 3.3.2.6 and 3.3.2.7, approved in Amendment No. 148.
FOR THE NUCLEAR REGULATORY COMMISSION Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of l'Juclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
December 3, 2008
ATTACHMENT TO LICENSE AMENDMENT NOS. 154 AND 154 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 the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License NPF-72 License NPF-72 License Page 3 License Page 3 License NPF-77 License NPF-77 License Page 3 License Page 3 TSs TSs 3.3.2-7 3.3.2-7
-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 3586.6 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. 154, 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)
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. 154
-3 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 are 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 3586.6 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 Speci"fications contained in Appendix A as revised through Amendment No. 154, 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. 154
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
SLiRVEI LLANCE FREQUENCY SR 3.3.2.4 Perform ACTUATION LOGIC TEST.
SR 3.3.2.5 Perform MASTER RELAY TEST.
SR 3.3.2.6 Per*form COT.
NOTE-------------------
Verification of relay setpoints not required.
Perform TADOT.
SR 3.3.2.8 Perform SLAVE RELAY TEST.
NOTE-------------------
Verification of setpoint not required.
Perform TADOT.
92 days on a STAGGERED TEST BASIS 92 days on a STAGGERED TEST BASIS 184 days 92 days 18 months 18 months (contlnued)
BRAI DWOOD -
LIN ITS 1 & 2 3.3.2 - 7 Amendment 154
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. 159 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 March 18,2008, 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 (2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 159, 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 30 days of the date of issuance. This implementation period supersedes the 120-day period for implementation of the changes to SRs 3.3.2.6 and 3.3.2.7, approved in Amendment No. 153.
Fa;;;R1J{;YCOMMISSION Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
December 3, 2008
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. 159 License No. I\\JPF-66
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated March 18, 2008, 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 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG 1113), as revised through Amendment No. 159, and the Environmental Protection Plan contained in Appendix B, both of which are 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 30 days of the date of issuance. This implementation period supersedes the 120-day period for implementation of the changes to SRs 3.3.2.6 and 3.3.2.7, approved in Amendment 1\\10. 153.
Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Spedfications and Facility Operating License Date of Issuance: December 3, 2008
ATTACHMENT TO LICENSE AMENDMENT NOS. 159 AND 159 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 and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-37 License NPF-37 License Page 3 License Page 3 License NPF-66 License NPF-66 License Page 3 License Page 3 TSs TSs 3.3.2-7 3.3.2-7
-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.
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 3586.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 159, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Deleted.
(4)
Deleted.
(5)
Deleted.
(6)
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report, and as approved in the SER dated February 1987 through Supplement No.8, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. 159
-3 (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 are 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 regulation 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 3586.6 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 (NUREG 1113), as revised through Amendment No. 159, and the Environmental Protection Plan contained in Appendix B, both of which are 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. 159
ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE FREQUENCY SR 3.3.2.4 Perform ACTUATION LOGIC TEST.
SR 3.3.2.5 Perform MASTER RELAY TEST.
SR 3.3.2.6 Perform COT.
NOTE --------------
Verification of relay setpoints not required.
Perform TADOT.
SR 3.3.2.8 Perform SLAVE RELAY TEST.
NOTE-------------------
Verification of setpo-j nt not requ-j red.
Perform TADOT.
92 days on a STAGGERED TEST BASIS 92 days on a STAGGERED TEST BASIS 184 days 92 days 18 months 18 months (contlnued)
BYRON ~ UNITS 1 &2 3.3.2 - 7 Amendment 159
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 154 TO FACILITY OPERATING LICENSE 1\\10. NPF-72, AMENDMENT NO. 154 TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-37, AND AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-66 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, AND STN 50-455
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated March 18, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML080790342), Exelon Generation Company, LLC (EGC, the licensee) submitted a license amendment request (LAR) for Braidwood Station, Units 1 and 2 (Braidwood), and Byron Station, Unit Nos. 1 and 2 (Byron). The LAR proposed to renumber two surveillance requirements (SRs) associated with Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation." Specifically, the LAR proposed to renumber SR 3.3.2.6 (to perform a trip actuating device operational test (TADOT)) as SR 3.3.2.7 and to renumber SR 3.3.2.7 (to perform a channel operational test (COT)) as SR 3.3.2.6.
2.0 BACKGROUND
On January 8, 2007 (ADAMS Accession No. ML080180213), EGC submitted a LAR to revise, in part, limiting condition for operation (LCO) 3.3.2, "ESFAS Instrumentation," to adopt completion times, test bypass times, and SR frequency changes. As part of that LAR, EGC also renumbered the ESFAS Instrumentation SRs for a COT (from 3.3.2.6 to 3.3.2.7) and for a TADOT (from 3.3.2.7 to 3.3.2.6). The numbering of these two SRs in the LAR established a frequency sequence for the ESFAS SRs that progressed from shortest to longest. The January 8, 2007, LAR was approved by the NRC staff on January 29,2008 (ADAMS Accession No. ML080110179) as Amendment 1\\10. 148 for Braidwood and Amendment No. 153 for Byron.
However, while implementing Amendment Nos. 148 and 153, EGC discovered that the LAR had not requested changes to the references to these two SRs in the accompanying ESFAS
- 2 instrumentation TS Table 3.3.2-1, "Engineered Safety Feature Actuation System Instrumentation," to reflect the change in SR numbering. As a result, incorrect SRs were referenced in Table 3.3.2-1. Upon discovery, EGC informed the NRC staff of the issue. In accordance with the guidance in !'JRC Administrative Letter 98-10, "Dispositioning of Technical Specifications That Are Insufficient to Assure Plant Safety," December 29, 1998, EGC entered the matter into the respective station corrective action programs, implemented Amendment Nos. 148 and 153 except for the changes to SRs 3.3.2.6 to 3.3.2.7, and submitted the current LAR on March 18, 2008.
3.0 REGULATORY EVALUATION
Title 10 of The Code of Federal Regulations (10 CFR) Section 50.36(c)(3) states that TSs will include SRs, which "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 limiting conditions for operation will be met."
The current LAR would renumber SR 3.3.2.6 (TADOT) as SR 3.3.2.7 and renumber SR 3.3.2.7 (COT) as SR 3.3.2.6. The current LAR makes a correction to the January 8, 2007, LAR, approved by the NRC staff on January 29,2008, by renumbering the LCO 3.3.2 SRs for a COT and a TADOT so that the appropriate ESFAS instrumentation SRs are performed in accordance with TS Table 3.3.2-1. As a result, 10 CFR 50.36(c)(3) will be met; therefore, the proposed renumbering of the SRs is acceptable.
4.0 TECHNICAL EVALUATION
For reasons discussed above in Section 3.0, the current LAR would renumber SR 3.3.2.6 (TADOT) as SR 3.3.2.7 and renumber SR 3.3.2.7 (COT)) as SR 3.3.2.6. The current LAR makes a correction to the January 8, 2007, LAR, approved by the NRC staff on January 29, 2008, by renumbering the LCO 3.3.2 SRs for a COT and a TADOT so that the appropriate ESFAS instrumentation SRs are performed in accordance with TS Table 3.3.2-1. This correction ensures that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. Therefore, the proposed renumbering of the SRs is acceptable.
5.0 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.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility's components located within the restricted area, as defined in 10 CFR Part 20, or changes SRs.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such
- 3 finding (73 FR 34341; June 17,2008). 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.
7.0 COI\\JCLUSION 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) 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: A. Lewin, NRR Date: December 3, 2008
'SE Memo Date NRR-058 OFFICE LPL3-2/PM LPL3-2/LA DIRS/ITSB/BC OGC LPL3-2/BC NAME MDavid EWhitl RElliotl*
LSubin RGibbs DATE 11/18/08 11/17/08 07/02/08 11/20108 12/3108