ML062890458

License Amendment, Issuance of Amendments Containment Spray and Cooling Systems Surveillance Requirement

ML062890458
Person / Time
Site:	Byron, Braidwood
Issue date:	12/06/2006
From:	Gratton C NRC/NRR/ADRO/DORL/LPLIII-2
To:	Crane C Exelon Generation Co
Kuntz, Robert F, NRR/DORL, 415-3733
Shared Package
ML062890484	List: ML062890458 ML063420522
References
TAC MC9754, TAC MC9755, TAC MC9756, TAC MC9757
Download: ML062890458 (21)

Text

December 6, 2006 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS RE: CONTAINMENT SPRAY AND COOLING SYSTEMS SURVEILLANCE REQUIREMENT (TAC NOS.

MC9754, MC9755, MC9756, AND MC9757)

Dear Mr. Crane:

The Commission has issued the enclosed Amendment No.149 to Facility Operating License No. NPF-37 and Amendment No.149 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively, and Amendment No.143 to Facility Operating License No. NPF-72 and Amendment No. 143 to Facility Operating License No. NPF-77 for the Braidwood Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated January 12, 2006.

The amendments revise Technical Specification 3.6.6, Containment Spray and Cooling Systems, Surveillance Requirement 3.6.6.3, governing containment cooling train cooling water flow rate, from $ 2660 gallons per minute (gpm) to each train to $ 2660 gpm to each cooler, to accurately reflect the existing plant design.

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/

Christopher Gratton, Senior Project Manager Licensing Plant Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457

Enclosures:

1. Amendment No.149 to NPF-37

2. Amendment No.149 to NPF-66

3. Amendment No.143 to NPF-72

4. Amendment No.143 to NPF-77

5. Safety Evaluation cc w/encls: See next page

Mr. Christopher M. Crane December 6, 2006 President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS RE: CONTAINMENT SPRAY AND COOLING SYSTEMS SURVEILLANCE REQUIREMENT (TAC NOS.

MC9754, MC9755, MC9756, AND MC9757)

Dear Mr. Crane:

The Commission has issued the enclosed Amendment No.149 to Facility Operating License No. NPF-37 and Amendment No.149 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively, and Amendment No.143 to Facility Operating License No. NPF-72 and Amendment No. 143 to Facility Operating License No. NPF-77 for the Braidwood Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated January 12, 2006.

The amendments revise Technical Specification 3.6.6, Containment Spray and Cooling Systems, Surveillance Requirement 3.6.6.3, governing containment cooling train cooling water flow rate, from $ 2660 gallons per minute (gpm) to each train to $ 2660 gpm to each cooler, to accurately reflect the existing plant design.

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/

Christopher Gratton, Senior Project Manager Licensing Plant Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456 and STN 50-457

Enclosures:

1. Amendment No. 149 to NPF-37

2. Amendment No. 149 to NPF-66

3. Amendment No. 143 to NPF-72

4. Amendment No. 143 to NPF-77

5. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC RidsNrrDirsItsb LPL3-2 R/F RidsRgn3MailCenter RidsNrrDorlLpl3-2 RidsOgcRp RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsNrrPMCGratton GHill (8) RidsNrrDorlDpr RidsNrrPMRKuntz Package: ML062890484 Amendment: ML062890458 Tech Spec Pages: ML063420522 *SE dated **NLO OFFICE PM:LPL3-2 LA:LPL3-2 DIRS/ITSB OGC BC:LPD3-2 NAME CGratton:mw EWhitt TKobetz* BPoole** MMarshall DATE 12/6/06 12/6/06 11/27/2006 12/4/06 12/6/06 OFFICIAL RECORD COPY

Byron/Braidwood Stations cc:

Dwain W. Alexander, Project Manager Plant Manager - Byron Station Westinghouse Electric Corporation Exelon Generation Company, LLC Energy Systems Business Unit 4450 N. German Church Road Post Office Box 355 Byron, IL 61010-9794 Pittsburgh, PA 15230-0355 Site Vice President - Byron Howard A. Learner Exelon Generation Company, LLC Environmental Law and Policy 4450 N. German Church Road Center of the Midwest Byron, IL 61010-9794 35 East Wacker Dr., Suite 1300 Chicago, IL 60601-2110 U.S. Nuclear Regulatory Commission Braidwood Resident Inspectors Office U.S. Nuclear Regulatory Commission 35100 S. Rt. 53, Suite 79 Byron Resident Inspectors Office Braceville, IL 60407 4448 N. German Church Road Byron, IL 61010-9750 County Executive Will County Office Building Regional Administrator, Region III 302 N. Chicago Street U.S. Nuclear Regulatory Commission Joliet, IL 60432 Suite 210 2443 Warrenville Road Plant Manager - Braidwood Station Lisle, IL 60532-4351 Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Ms. Lorraine Creek Braceville, IL 60407-9619 RR 1, Box 182 Manteno, IL 60950 Ms. Bridget Little Rorem Appleseed Coordinator Chairman, Ogle County Board 117 N. Linden Street Post Office Box 357 Essex, IL 60935 Oregon, IL 61061 Document Control Desk - Licensing Mrs. Phillip B. Johnson Exelon Generation Company, LLC 1907 Stratford Lane 4300 Winfield Road Rockford, IL 61107 Warrenville, IL 60555 Attorney General Site Vice President - Braidwood 500 S. Second Street Exelon Generation Company, LLC Springfield, IL 62701 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Illinois Emergency Management Agency Senior Vice President - Operations Support Division of Disaster Assistance & Exelon Generation Company, LLC Preparedness 4300 Winfield Road 110 East Adams Street Warrenville, IL 60555 Springfield, IL 62701-1109

Byron/Braidwood Stations Director - Licensing and Regulatory Senior Vice President - Midwest Operations Affairs Exelon Generation Company, LLC Exelon Generation Company, LLC 4300 Winfield Road 4300 Winfield Road Warrenville, IL 60555 Warrenville, IL 60555 Manager Regulatory Assurance - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Manager Regulatory Assurance - Byron Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Vice President - Regulatory & Legal Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood/Byron 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.149 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 January 12, 2006, 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. 149 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/

Michael L. Marshall, Chief Plant Licensing Branch III-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 6, 2006

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 149 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 January 12, 2006, 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. 149 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/

Michael L. Marshall, Chief Plant Licensing Branch III-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 6, 2006

ATTACHMENT TO LICENSE AMENDMENT NOS. 149 AND 149 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 Appendix A Technical Specifications (TSs) with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert Unit 1 License NPF-37 Unit 1 License NPF-37 Page 3 Page 3 Unit 2 License NPF-66 Unit 2 License NPF-66 Page 3 Page 3 Units 1 and 2 TSs Units 1 and 2 TSs 3.6.6-2 3.6.6-2

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 143 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 January 12, 2006, 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. 143 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/

Michael L. Marshall, Chief Plant Licensing Branch III-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 6, 2006

EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 143 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 January 12, 2006, 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. 143 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/

Michael L. Marshall, Chief Plant Licensing Branch III-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 6, 2006

ATTACHMENT TO LICENSE AMENDMENT NOS. 143 AND 143 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Facility Operating Licenses and Appendix "A" Technical Specifications (TSs) with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert Unit 1 License NPF-72 Unit 1 License NPF-72 Page 3 Page 3 Unit 2 License NPF-77 Unit 2 License NPF-77 Page 3 Page 3 Units 1 and 2 TSs Units 1 and 2 TSs 3.6.6-2 3.6.6-2

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 149 TO FACILITY OPERATING LICENSE NO. NPF-37, AMENDMENT NO. 149 TO FACILITY OPERATING LICENSE NO. NPF-66, AMENDMENT NO. 143 TO FACILITY OPERATING LICENSE NO. NPF-72, AND AMENDMENT NO. 143 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 letter to the Nuclear Regulatory Commission (NRC or the Commission) dated January 12, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML060130404), Exelon Generation Company, LLC (Exelon, the licensee) requested changes to the technical specification (TS) surveillance requirements (SRs) for the Byron Station, Unit Nos. 1 and 2 (Byron), and the Braidwood Station, Unit Nos. 1 and 2 (Braidwood). The proposed changes would revise TS 3.6.6, Containment Spray and Cooling Systems, SR 3.6.6.3 from $ 2660 gallons per minute (gpm) to each train, to $ 2660 gpm to each cooler. The change corrects an error introduced into the TSs during the conversion to improved standard technical specifications (ITS) format.

The containment cooling system (CCS) consists of two redundant trains, each of sufficient capacity to supply 100 percent of the design cooling requirement. Each train consists of two 50 percent capacity reactor containment fan coolers (RCFCs). The RCFCs for each train are supplied with cooling water from separate trains of the essential service water system (SX).

Byron and Braidwood converted to ITS in December 1998 (ADAMS Accession No. ML020870040). The SR in the previous TSs that was equivalent to SR 3.6.6.3 required that each train of the containment cooling system be demonstrated OPERABLE by verifying an SX flow rate of $ 2660 gpm to each RCFC. During the ITS conversion, standard verbiage for SR 3.6.6.3 was adopted; however, the specific plant design of two RCFCs per containment cooling train was overlooked. Currently, SR 3.6.6.3 requires that each CCS train be supplied by the SX at a flow rate of $ 2660 gpm. The licensee identified this inconsistency and has implemented appropriate administrative controls. The licensee considers SR 3.6.6.3 nonconservative. The licensee is requesting that the SR be revised to require the cooling water

flow rate to each RCFC be $ 2660 gpm to be consistent with the Byron and Braidwood plant design basis.

2.0 REGULATORY EVALUATION

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

Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(b) requires that [e]ach license authorizing operation of a production or utilization facility of the type described in Section 50.21 or Section 50.22 will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to Section 50.34. The Commission may include such additional technical specifications as the Commission finds appropriate. Section 50.36(c)(3)

Surveillance Requirements, states that [s]urveillance requirements 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 NRC staff reviewed the proposed changes for compliance with 10 CFR 50.36, ?Technical Specifications.

In addition, licensees may revise their TSs to adopt the ITS format and content provided that a plant-specific review supports a finding of continued adequate safety because the changes are:

(1) editorial, administrative, or provides clarification (i.e., no requirements are materially altered); (2) more restrictive than the licensees current requirement; or (3) less restrictive than the licensees current requirements, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards.

3.0 TECHNICAL EVALUATION

The NRC staff reviewed the licensees technical analyses in support of its proposed license amendment, which is described in Section 4.0 of the licensees January 12, 2006, submittal.

The licensees changes to SR 3.6.6 clarify that a flow rate of $ 2660 gpm to each cooler is needed to satisfy the SR. The NRC staff reviewed the proposed changes and found that they continue to provide adequate safety because they are consistent with the design of Byron and Braidwood and correct the error introduced when the licensee converted the TSs to the ITS format. The changes also comply with 10 CFR 50.36 and are consistent with the ITS. On this basis, the NRC staff concludes that the proposed changes to the TS for Byron and Braidwood, are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, the Illinois State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change the requirements with respect to installation or use of the facilities components located within the restricted areas as defined in 10 CFR Part 20 and changes surveillance requirements. 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 (71 FR 23954; April 25, 2006). 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.

Principal Contributor: T. Wertz Date: December 6, 2006

(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 Commissions 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 power) in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 149 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 licensees 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. 149

(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 Commissions 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. 149, 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. 149

(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 Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels is not in excess of 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 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. 143, 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 Agencys 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. 143

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 Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels is not in excess of 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 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. 143, 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 Agencys 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. 143