ML062890458

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License Amendment, Issuance of Amendments Containment Spray and Cooling Systems Surveillance Requirement
ML062890458
Person / Time
Site: Byron, Braidwood  Constellation icon.png
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:
References
TAC MC9754, TAC MC9755, TAC MC9756, TAC MC9757
Download: ML062890458 (21)
v • d • e


Text

December 6, 2006Mr. 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, UNITNOS. 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 LicenseNo. 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 CoolingSystems," 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 theCommission's 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 RegulationDocket 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 Evaluationcc w/encls: See next page Mr. Christopher M. CraneDecember 6, 2006President 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, UNITNOS. 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 LicenseNo. 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 CoolingSystems," 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 theCommission's 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 RegulationDocket 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
PUBLICRidsNrrDirsItsbLPL3-2 R/F RidsRgn3MailCenterRidsNrrDorlLpl3-2RidsOgcRp RidsNrrLAEWhittRidsAcrsAcnwMailCenterRidsNrrPMCGratton GHill (8)RidsNrrDorlDprRidsNrrPMRKuntz Package: ML062890484 Amendment: ML062890458 Tech Spec Pages: ML063420522 *SE dated**NLOOFFICEPM:LPL3-2LA:LPL3-2DIRS/ITSBOGCBC:LPD3-2 NAMECGratton:mwEWhittTKobetz*BPoole**MMarshallDATE12/6/0612/6/0611/27/200612/4/0612/6/06OFFICIAL RECORD COPY Byron/Braidwood Stations cc:

Dwain W. Alexander, Project ManagerWestinghouse Electric Corporation Energy Systems Business Unit Post Office Box 355 Pittsburgh, PA 15230-0355Howard A. LearnerEnvironmental Law and Policy Center of the Midwest 35 East Wacker Dr., Suite 1300 Chicago, IL 60601-2110U.S. Nuclear Regulatory CommissionByron Resident Inspectors Office 4448 N. German Church Road Byron, IL 61010-9750Regional Administrator, Region IIIU.S. Nuclear Regulatory Commission Suite 210 2443 Warrenville Road Lisle, IL 60532-4351Ms. Lorraine CreekRR 1, Box 182 Manteno, IL 60950Chairman, Ogle County BoardPost Office Box 357 Oregon, IL 61061Mrs. Phillip B. Johnson1907 Stratford Lane Rockford, IL 61107Attorney General500 S. Second Street Springfield, IL 62701Illinois Emergency Management Agency Division of Disaster Assistance &

Preparedness 110 East Adams Street Springfield, IL 62701-1109Plant Manager - Byron StationExelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794Site Vice President - ByronExelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794U.S. Nuclear Regulatory CommissionBraidwood Resident Inspectors Office 35100 S. Rt. 53, Suite 79 Braceville, IL 60407County Executive Will County Office Building 302 N. Chicago Street Joliet, IL 60432Plant Manager - Braidwood Station Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619Ms. Bridget Little RoremAppleseed Coordinator 117 N. Linden Street Essex, IL 60935Document Control Desk - LicensingExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Site Vice President - BraidwoodExelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619Senior Vice President - Operations SupportExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Byron/Braidwood Stations Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Manager Regulatory Assurance - BraidwoodExelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619Manager Regulatory Assurance - ByronExelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794Assistant General CounselExelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348Vice President - Regulatory & Legal AffairsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Manager Licensing - Braidwood/ByronExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Senior Vice President - Midwest OperationsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-454BYRON STATION, UNIT NO. 1AMENDMENT TO FACILITY OPERATING LICENSEAmendment No.149License No. NPF-371.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Exelon Generation Company, LLC (thelicensee) dated January 12, 2006, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment 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 beimplemented within 30 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Michael L. Marshall, ChiefPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating LicenseDate of Issuance: December 6, 2006 EXELON GENERATION COMPANY, LLCDOCKET NO. STN 50-455BYRON STATION, UNIT NO. 2AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 149License No. NPF-661.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Exelon Generation Company, LLC (thelicensee) dated January 12, 2006, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendix A (NUREG-1113), asrevised 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 beimplemented within 30 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Michael L. Marshall, ChiefPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating LicenseDate of Issuance: December 6, 2006 ATTACHMENT TO LICENSE AMENDMENT NOS. 149 AND 149FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66DOCKET NOS. STN 50-454 AND STN 50-455Replace the following pages of the Facility Operating Licenses and Appendix "A" TechnicalSpecifications (TSs) with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsertUnit 1 License NPF-37Unit 1 License NPF-37Page 3Page 3Unit 2 License NPF-66 Unit 2 License NPF-66 Page 3Page 3Units 1 and 2 TSsUnits 1 and 2 TSs3.6.6-23.6.6-2 EXELON GENERATION COMPANY, LLCDOCKET NO. STN 50-456BRAIDWOOD STATION, UNIT NO. 1AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 143 License No. NPF-721.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 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendix A as revised throughAmendment 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 beimplemented within 30 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Michael L. Marshall, ChiefPlant 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, LLCDOCKET NO. STN 50-457BRAIDWOOD STATION, UNIT NO. 2AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 143 License No. NPF-771.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Exelon Generation Company, LLC (thelicensee) dated January 12, 2006, 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 theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 SpecificationsThe Technical Specifications contained in Appendix A as revised throughAmendment 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 beimplemented within 30 days of the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Michael L. Marshall, ChiefPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating LicenseDate of Issuance: December 6, 2006 ATTACHMENT TO LICENSE AMENDMENT NOS. 143 AND 143FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77DOCKET NOS. STN 50-456 AND STN 50-457Replace the following pages of the Facility Operating Licenses and Appendix "A" TechnicalSpecifications (TSs) with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsertUnit 1 License NPF-72Unit 1 License NPF-72Page 3Page 3Unit 2 License NPF-77 Unit 2 License NPF-77 Page 3Page 3Units 1 and 2 TSsUnits 1 and 2 TSs3.6.6-23.6.6-2 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED 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-77EXELON GENERATION COMPANY, LLCBYRON STATION, UNIT NOS. 1 AND 2BRAIDWOOD STATION, UNIT NOS. 1 AND 2DOCKET NOS. STN 50-454, STN 50-455, STN 50-456 AND STN 50-45

71.0INTRODUCTION

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 sufficientcapacity to supply 100 percent of the design cooling requirement. Each train consists of two50 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 forSR 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 hasimplemented 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 plantdesign basis.

2.0REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operatinglicenses 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]achlicense 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 specificationswill 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 aplant-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 licensee's current requirement; or (3) less restrictive than the licensee's 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 licensee's technical analyses in support of its proposed licenseamendment, which is described in Section 4.0 of the licensee's January 12, 2006, submittal.

The licensee's changes to SR 3.6.6 clarify that a flow rate of 2660 gpm to each cooler isneeded 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.

4.0STATE CONSULTATION

In accordance with the Commission's regulations, the Illinois State official was notified of theproposed issuance of the amendments. The State official had no comments.

5.0ENVIRONMENTAL CONSIDERATION

The amendments change the requirements with respect to installation or use of the facilitiescomponents 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 findingthat 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.

6.0CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) thereis 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: 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 notseparate, 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 specifiedin 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 LevelThe licensee is authorized to operate the facility at reactor core powerlevels not in excess of 3586.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.(2)Technical SpecificationsThe Technical Specifications contained in Appendix A as revised throughAmendment 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 theapproved 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 protectionprogram 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 notseparate, 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 specifiedin 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 LevelThe licensee is authorized to operate the facility at reactor core powerlevels 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 PlanThe Technical Specifications contained in Appendix A (NUREG-1113), asrevised 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 specifiedin 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 LevelThe licensee is authorized to operate the facility at reactor core powerlevels 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 to this license shall be completed as specified. is hereby incorporated into this license.(2)Technical SpecificationsThe Technical Specifications contained in Appendix A as revised throughAmendment 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 PlanningIn the event that the NRC finds that the lack of progress in completion ofthe 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. 143 material as sealed neutron sources for reactor startup, sealed sources forreactor 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 Parts30, 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 Parts30, 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 specifiedin 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 LevelThe licensee is authorized to operate the facility at reactor core powerlevels 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 to this license shall be completed as specified. is hereby incorporated into this license.(2)Technical SpecificationsThe Technical Specifications contained in Appendix A as revised throughAmendment 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 PlanningIn the event that the NRC finds that the lack of progress in completion ofthe 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. 143

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