ML042670510
| ML042670510 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 10/04/2004 |
| From: | Dick G NRC/NRR/DLPM/LPD3 |
| To: | Crane C Exelon Generation Co |
| Dick G F, NRR/DLPM, 415-3019 | |
| Shared Package | |
| ML042670517 | List: |
| References | |
| TAC MC3283, TAC MC3284, TAC MC3285, TAC MC3286 | |
| Download: ML042670510 (18) | |
Text
October 4, 2004 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
ISSUANCE OF AMENDMENTS; REVISED PRESSURE-TEMPERATURE LIMITS METHODOLOGY; BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 (TAC NOS. MC3285, MC3286, MC3283 AND MC3284)
Dear Mr. Crane:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 139 to Facility Operating License No. NPF-37 and Amendment No. 139 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively, and Amendment No. 132 to Facility Operating License No. NPF-72 and Amendment No. 132 to Facility Operating License No. NPF-77 for the Braidwood Station, Unit Nos. 1 and 2, respectively. The amendments are in response to Exelon Generation Company, LLC application dated May 21, 2004.
The amendments revise the technical specifications to add an additional reference as an acceptable method for determining the reactor pressure vessel pressure-temperature limits.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
George F. Dick, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.: STN 50-454, STN 50-455, STN 50-456 and STN 50-457
Enclosures:
- 1. Amendment No. 139 to NPF-37
- 2. Amendment No. 139 to NPF-66
- 3. Amendment No. 132 to NPF-72
- 4. Amendment No. 132 to NPF-77
- 5. Safety Evaluation cc w/encls: See next page
October 4, 2004 Mr. Christopher M. Crane, President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
ISSUANCE OF AMENDMENTS; REVISED PRESSURE-TEMPERATURE LIMITS METHODOLOGY; BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 (TAC NOS. MC3285, MC3286, MC3283 AND MC3284)
Dear Mr. Crane:
The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 139 to Facility Operating License No. NPF-37 and Amendment No. 139 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively, and Amendment No. 132 to Facility Operating License No. NPF-72 and Amendment No. 132 to Facility Operating License No. NPF-77 for the Braidwood Station, Unit Nos. 1 and 2, respectively. The amendments are in response to Exelon Generation Company, LLC application dated May 21, 2004.
The amendments revise the technical specifications to add an additional reference as an acceptable method for determining the reactor pressure vessel pressure-temperature limits.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
George F. Dick, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos.: STN 50-454, STN 50-455, STN 50-456 and STN 50-457
Enclosures:
- 1. Amendment No. 139 to NPF-37
- 2. Amendment No. 139 to NPF-66
- 3. Amendment No. 132 to NPF-72
- 4. Amendment No. 132 to NPF-77
- 5. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PD3-2 R/F WRuland GSuh PCoates OGC ACRS GDick TBoyce AStone, RIII MKhanna LLois GHill (8)
ADAMS Accession Number: ML042670517 (Package)
ADAMS Accession Number: ML042670510 (Amendment)
- SE dated 09/10/04 ADAMS Accession Number: ML042810556 (Technical Specifications) *SE dated 09/14/04 OFFICE PM:PDIII-2 LA:PDIII-2 SC:SRXB SC:EMCB SC:IROB OGC SC:PDIII-2 NAME GDick PCoates JUhle**
SCoffin*
TBoyce AHodgdon GSuh DATE 10/01/04 10/01/04 09/10/04 09/14/04 9/28/04 10/1/04 10/04/04 OFFICIAL RECORD COPY
Byron/Braidwood Stations cc:
Ms. C. Sue Hauser, Project Manager Westinghouse Electric Corporation Energy Systems Business Unit Post Office Box 355 Pittsburgh, PA 15230 Joseph Gallo Gallo & Ross 1025 Connecticut Ave., NW, Suite 1014 Washington, DC 20036 Howard A. Learner Environmental Law and Policy Center of the Midwest 35 East Wacker Dr., Suite 1300 Chicago, IL 60601-2110 U.S. Nuclear Regulatory Commission Byron Resident Inspectors Office 4448 N. German Church Road Byron, IL 61010-9750 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Ms. Lorraine Creek RR 1, Box 182 Manteno, IL 60950 Chairman, Ogle County Board Post Office Box 357 Oregon, IL 61061 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, IL 61107 George L. Edgar Morgan, Lewis and Bockius 1800 M Street, NW Washington, DC 20036-5869 Attorney General 500 S. Second Street Springfield, IL 62701 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Byron Station Plant Manager Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Site Vice President - Byron Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 U.S. Nuclear Regulatory Commission Braidwood Resident Inspectors Office 35100 S. Rt. 53, Suite 79 Braceville, IL 60407 Chairman Will County Board of Supervisors Will County Board Courthouse Joliet, IL 60434 Braidwood Station Plant Manager Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Ms. Bridget Little Rorem Appleseed Coordinator 117 N. Linden Street Essex, IL 60935
Byron/Braidwood Stations Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Site Vice President - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Senior Vice President - Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President of Operations - Mid-West Pressurized Water Reactors Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Regulatory Assurance Manager - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Regulatory Assurance Manager - Byron Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood, Byron and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 139 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 May 21, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions 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. 139 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.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 139 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Exelon Generation Company, LLC (the licensee) dated May 21, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions 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 (NUREG-1113), as revised through Amendment No. 139 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
ATTACHMENT TO LICENSE AMENDMENT NOS. 139 AND 139 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by amendment number and contain marginal lines indicating the area of change.
Remove Page Insert Page 5.6-5 5.6-5
EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 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 May 21, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 132 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.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 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 May 21, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions 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 Commissions 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 Commissions 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. 132 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date if its issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Gene Y. Suh, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 4, 2004
ATTACHMENT TO LICENSE AMENDMENT NOS. 132 AND 132 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by amendment number and contain marginal lines indicating the area of change.
Remove Page Insert Page 5.6-5 5.6-5
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 139 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 139 TO FACILITY OPERATING LICENSE NO. NPF-66, AMENDMENT NO. 132 TO FACILITY OPERATING LICENSE NO. NPF-72, AND AMENDMENT NO. 132 TO FACILITY OPERATING LICENSE NO. NPF-77 EXELON GENERATION COMPANY, LLC BYRON STATION, UNIT NOS. 1 AND 2 BRAIDWOOD STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-454, STN 50-455, STN 50-456 AND STN 50-457
1.0 INTRODUCTION
By application dated May 21, 2004 (ML041470212), Exelon Generation Company, LLC (the licensee, EGC) requested changes to the Technical Specifications (TS) for the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (Byron and Braidwood). The staffs proposed no significant hazards consideration determination was published in the Federal Register on August 3, 2004 (69 FR 46583).
The proposed changes would revise the technical specifications (TS) by adding to the list of approved methods for determining reactor pressure vessel pressure-temperature (P-T) limits a reference to an NRC staff letter. Specifically the proposed changes would revise TS 5.6.6.b to include a reference to NRC letter of August 8, 2001 (ML011720218), Issuance of Exemption from the Requirements of 10 CFR 50 Part 60 and Appendix G, for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The exemption approved the use of ASME Code Case N-588, Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor Vessels,Section XI, Division 1, and Code Case N-640, Alternative Reference Fracture Toughness for Development of P-T Limit Curves for ASME Section XI, Division 1. Inclusion of the NRCs August 8, 2001, letter into the TS will permit the licensee to use the two Code Cases in calculating the P-T curves for the four units at Byron and Braidwood.
2.0 REGULATORY EVALUATION
By letter dated January 23, 1998, the NRC issued amendments 98 and 89 for Byron and Braidwood respectively. The amendments approved the relocation of the reactor coolant system pressure and temperature limits for heatup, cooldown, low-temperature operation and hydrostatic testing, and the low-temperature overpressure protection (LTOP) system setpoint curves into a Pressure and Temperature Limits Report (PTLR). The staff found that the licensees amendment request was submitted consistent with the guidance provided in Generic Letter 96-03 Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits, with three exceptions which the licensee addressed.
The staff concluded that it was acceptable for the licensee to relocate the P-T curves and the LTOP systems limits from the TS to a licensee controlled PTLR. Retained in the TS were references to the methodology to be used in the calculation of the P-T limits. Changes to the methodology require a request by the licensee for a license amendment in accordance with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Application for Amendment of License or Construction Permit.
3.0 TECHNICAL EVALUATION
3.1 Licensee Evaluation In the May 21, 2004, submittal, the licensee provided a license amendment request that included a proposed revision to TS 5.6.6 for Byron and Braidwood, and identified the documents which fully describe the PTLR methodology for the units. The proposed change to the PTLR methodology includes the August 8, 2001, letter, which documents NRC approval of the use of the ASME Code Cases N-640 and N-588.
The current Braidwood and Byron P-T limit curves are applicable for reactor pressure vessel exposures less than or equal to 14 effective full power years (EFPY) for the Braidwood Station Units 1 and 2, 15.6 EFPY for Byron Station, Unit 1, and 15.5 EFPY for Byron Station, Unit 2.
The first unit to reach the limiting exposure for the P-T curves is Byron Station, Unit 1, which is expected to reach 15.6 EFPY in the fall of 2004. The licensees submittal indicated that staff approval was not required for the P-T limit curves, since the P-T limit curves were not part of the Braidwood and Byron TS; however, the licensee noted that their existing curves, as provided in their existing PTLR, will be modified to allow an additional 2 EFPY of operation for each unit based on the use of the Code Cases. The revised PTLR will be submitted to the NRC in accordance with TS 5.6.6.c. The licensee indicated that the revised PTLR for Byron would be submitted within 30 days of the implementation of the extended P-T curves. The Braidwood PTLR will be submitted after implementation of the revised curves.
In addition, the licensee provided TS pages that amended those provided in the licensees original January 21, 1998, submittal to include the reference to the August 8, 2001, letter.
3.2 NRC Staff Evaluation As indicated previously, the staff issued a license amendment dated January 23, 1998, whereby the staff found it acceptable that the P-T limit curves be included in a PTLR controlled by the licensee for Byron and Braidwood. Therefore, any revisions made to the P-T limit curves or LTOP limits no longer require staff approval since they are not part of the Byron and Braidwood TS.
By letter dated December 8, 2000, the licensee requested an exemption to 10 CFR 50, Appendix G, to apply Code Cases N-588, Alternative to Reference Flaw Orientation of Appendix G for Circumferential Welds in Reactor VesselsSection XI, Division 1, and N-640, Alternative Reference Fracture Toughness for Development of P-T Limit Curves for Section XI, Division 1.
The staff approved EGCs exemption request by letter dated August 8, 2001 (ML011720218).
The licensee used Code Cases N-588 and N-640 and 22 EFPY fluence values (for each unit) to calculate 22 EFPY P-T limit curves. Application of the Code Cases results in the current P-T limits being more conservative that the 22 EFPY P-T limits. The licensees stated intent to extend the limits by 2 EFPY is based on this conservatism. Because the extension is based on the validity of the 22 EFPY limit curves, the staff reviewed their fluence value and the fluence methodology used to calculate the curves. The licensees submittal references WCAP-15316 as the source of the 22 EFPY fluence values. This report, in addition to the Braidwood, Unit 1 surveillance analysis results includes updates of the same unit capsules U and X for cross sections from ENDF/B-V to ENDF/B-VI and is replotting the results of the other three units using a computer program to replace the manual plots. With the updates of the cross sections, the fluence methodology adheres to the guidance in Regulatory Guide 1.190. Therefore, the proposed fluence values for 22 EFPY are acceptable.
The licensee compared the pressure and temperature values for the P-T curves to the 22 EFPY values. In all instances (i.e., isothermal, heatup, and cooldown), the current pressures (for a given coolant temperature) are so much lower that the increase in the temperature value due to the additional radiation of the 2 EFPY extension is insignificant.
Because the P-T curves will not be changed in the extension the LTOP enable temperature setting remains the same.
Since the licensee is appropriately modifying the current approved PTLR methodology to include the Code Cases that have been previously approved, the staff finds the proposed revision to incorporate the staffs letter dated August 8, 2001, approving the use of Code Case N-588 and Code Case N-640, to be acceptable. The staff also verified that the fluence methodology adheres to the guidance in Regulatory Guide (RG) 1.190, which is also addressed as part of the PTLR methodology as addressed in Generic Letter (GL) 96-03.
3.3 Summary Based on the NRC staffs review of the information provided in the licensees May 21, 2004, submittal, the staff found that the licensee appropriately revised TS 5.6.6.b to include the appropriate documentation of the licensees PTLR methodology for Byron and Braidwood. In addition, the staff verified that the fluence methodology adheres to the guidance of RG 1.190.
In order to satisfy TS 5.6.6.c, the staff noted that EGC will submit to the staff the revised PTLR, which will include the application of Code Cases N-588 and N-640.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (69 FR 46583). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions 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.
7.0 REFERENCES
1.
NRC Amendments Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2, Acceptance for Referring of Pressure Temperature Limits Report, dated January 21, 1998.
2.
License Amendment Request from Exelon, Amendment to the Pressure Temperature Limits Report, dated May 21, 2004.
3.
GL-96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits, dated January 31, 1996.
4.
Letter from U.S. NRC to O.D. Kingsley (Exelon Generating Company, LLC), Issuance of Exemption from the Requirements of 10 CFR 50 Part 60 and Appendix G for Byron Station, Units 1 and 2 and Braidwood Station Units 1 and 2, dated August 8, 2001.
5.
WCAP-15316, Revision 1, Analysis of Capsule W from the Commonwealth Edison Company Braidwood Unit 1 Reactor Vessel Radiation Surveillance Program by E. Terrek et al, Westinghouse Electric Company LLC, December 1999.
6.
Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence US Nuclear Regulatory Commission, March 2001.
Principal Contributors: M. Khanna, NRR/DE L. Lois, NRR/DSSA Date: October 4, 2004