ML062220386

License Amendments 181 and 168 Regarding Technical Specification 5.6.5, Core Operating Limits Report.

ML062220386
Person / Time
Site:	LaSalle
Issue date:	02/15/2007
From:	Sands S NRC/NRR/ADRO/DORL/LPLIII-2
To:	Crane C Exelon Generation Co
Sands, S, NRR/DLPM/PD3-2, 415-3154
Shared Package
ML062220400	List: ML062220386
References
TAC MD1356, TAC MD1357
Download: ML062220386 (15)

Text

February 15, 2007Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTSRE: TECHNICAL SPECIFICATION 5.6.5, "CORE OPERATING LIMITS REPORT" (TAC NOS. MD1356 and MD1357)

Dear Mr. Crane:

The Nuclear Regulatory Commission (NRC, Commission) has issued the enclosed AmendmentNo. 181 to Facility Operating License No. NPF-11 and Amendment No. 168 to Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2, respectively. The amendments are in response to your application dated April 4, 2006, to Technical Specification (TS) Section 5.6.5, "Core Operating Limits Report (COLR)."The amendments add one NRC approved topical report reference to the list of analyticalmethods and delete seven obsolete references in the same TS Section 5.6.5. 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/Stephen P. Sands, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-373 and 50-374

Enclosures:

1. Amendment No. 181 to NPF-11

2. Amendment No. 168 to NPF-18

3. Safety Evaluationcc w/encls: See next page Mr. Christopher M. CraneFebruary 15, 2007President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTSRE: TECHNICAL SPECIFICATION 5.6.5, "CORE OPERATING LIMITS REPORT" (TAC NOS. MD1356 and MD1357)

Dear Mr. Crane:

The Nuclear Regulatory Commission (NRC, Commission) has issued the enclosed AmendmentNo. 181 to Facility Operating License No. NPF-11 and Amendment No. 168 to Facility Operating License No. NPF-18 for the LaSalle County Station, Units 1 and 2, respectively. The amendments are in response to your application dated April 4, 2006, to Technical Specification (TS) Section 5.6.5, "Core Operating Limits Report (COLR)."The amendments add one NRC approved topical report reference to the list of analyticalmethods and delete seven obsolete references in the same TS Section 5.6.5. 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/Stephen P. Sands, Project ManagerPlant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-373 and 50-374

Enclosures:

1. Amendment No. 181 to NPF-11

2. Amendment No. 168 to NPF-18

3. Safety EvaluationDISTRIBUTION

PUBLICLPL3-2 R/FRidsNrrPMSSandsRidsOgcRp GHill (4)RidsNrrDirsItsbRidsAcrsAcnwMailCenterRidsRgn3MailCenter RidsNrrLAEWhittRidsNrrDorlDprRidsNrrDorlLpl3-2RidsNrrDssSnpb JKaizer, NRR Amendment: ML062220386 Package: ML062220400TS Pages: ML** No major changes to SE dated 06/26/2006OFFICELPL3-2/PMLPL3-2/LADIRS/ITSBDSS/SNPB**OGC LPL3-2/BC (A)NAMESSands:mwEWhittTKobetzRlandry SHamrickMMarshallDATE02/15/0702/16/0702/12 /0706/ 26 /0702/ 09 /0702/15/07OFFICIAL RECORD COPY LaSalle County Station, Units 1 and 2 cc:

Site Vice President - LaSalle County StationExelon Generation Company, LLC 2601 North 21st Road Marseilles, IL 61341-9757Plant Manager - LaSalle County StationExelon Generation Company, LLC 2601 North 21st Road Marseilles, IL 61341-9757Manager Regulatory Assurance - LaSalleExelon Generation Company, LLC 2601 North 21st Road Marseilles, IL 61341-9757U.S. Nuclear Regulatory CommissionLaSalle Resident Inspectors Office 2605 North 21st Road Marseilles, IL 61341-9756Phillip P. Steptoe, EsquireSidley and Austin One First National Plaza Chicago, IL 60603Assistant Attorney General100 W. Randolph St. Suite 12 Chicago, IL 60601ChairmanLaSalle County Board 707 Etna Road Ottawa, IL 61350Attorney General500 S. Second Street Springfield, IL 62701ChairmanIllinois Commerce Commission 527 E. Capitol Avenue, Leland Building Springfield, IL 62706Robert Cushing, Chief, Public Utilities DivisionIllinois Attorney General's Office 100 W. Randolph Street Chicago, IL 60601Regional AdministratorU.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351Illinois Emergency Management Agency Division of Disaster Assistance &

Preparedness 110 East Adams Street Springfield, IL 62701-1109Document Control Desk - LicensingExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Senior Vice President -Operations SupportExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Director - Licensing and Regulatory AffairsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Vice President - Regulatory & Legal AffairsExelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555Assistant General CounselExelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 LaSalle County Station, Units 1 and 2 cc:Manager Licensing - LaSalleExelon 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, LLCDOCKET NO. 50-373LASALLE COUNTY STATION, UNIT 1AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 181License No. NPF-111.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment filed by the Exelon Generation Company, LLC(the licensee), dated April 4, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the 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 set forth in 10 CFR Chapter I;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 the Facility Operating License No. NPF-11 is hereby amended to read as follows: (2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 181, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.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, Jr., 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: February 15, 2007 EXELON GENERATION COMPANY, LLCDOCKET NO. 50-374LASALLE COUNTY STATION, UNIT 2AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 168License No. NPF-181.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment filed by the Exelon Generation Company, LLC(the licensee), dated April 4, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the 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 set forth in 10 CFR Chapter I;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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows: (2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 168, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.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, Jr., 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: February 15, 2007 ATTACHMENT TO LICENSE AMENDMENT NOS. 181 AND 168FACILITY OPERATING LICENSE NOS. NPF-11 AND NPF-18DOCKET NOS. 50-373 AND 50-374Replace the following pages of the Facility Operating Licenses and Appendix "A" TechnicalSpecifications with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.Remove InsertUnit 1 License Page 3Unit 1 License Page 3 Unit 2 License Page 3Unit 2 License Page 3 5.6-35.6-3 5.6-45.6-4 (4)Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and(5)Exelon Generation Company, LLC, pursuant to the Act and 10 CFRParts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2.C.This 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 not in excess of full power (3489 megawatts thermal).(2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 181, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.(3)Conduct of Work Activities During Fuel Load and Initial StartupThe licensee shall review by committee all Unit 1 PreoperationalTesting and System Demonstration activities performed concurrently with Unit 1 initial fuel loading or with the Unit 1 Startup Test Program to assure that the activity will not affect the safe performance of the Unit 1 fuel loading or the portion of the Unit 1 Startup Program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security and health physics, with respect to performance of the activity concurrently with the Unit 1 fuel loading or the portion of the Unit 1 Startup Program being performed. The committee for the review shall be composed of at least three members, knowledgeable in the above areas, and who meet the qualifications for professional-technical personnel specified byAmendment No. 181 (5)Pursuant to the Act and 10 CFR Parts 30, 40, and 70 possess, but notseparate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station Units 1 and 2.C.This 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 not in excess of full power (3489 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.(2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 168, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.(3)Conduct of Work Activities During Fuel Load and Initial StartupThe licensee shall review by committee all Unit 2 Preoperational Testingand System Demonstration activities performed concurrently with Unit 2 initial fuel loading or with the Unit 2 Startup Test Program to assure that the activity will not affect the safe performance of the Unit 2 fuel loading or the portion of the Unit 2 Startup Program being performed. The review shall address, as a minimum, system interaction, span of control, staffing, security and health physics, with respect to performance of the activity concurrently with the Unit 2 fuel loading or the portion of the Unit 2 Startup Program being performed. The committee for the review shall be composed of at least three members, knowledgeable in the above areas, and who meet the qualifications for professional-technical personnel specified by section 4.4 of ANSI N18.7-1971. At least one of these three shall be a senior member of the Assistant Superintendent of Operation's staff.Amendment No. 168 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE NO. NPF-11AND AMENDMENT NO. 168 TO FACILITY OPERATING LICENSE NO. NPF-18EXELON GENERATION COMPANY, LLCLASALLE COUNTY STATION, UNITS 1 AND 2DOCKET NOS. 50-373 AND 50-37

41.0INTRODUCTION

By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated April 4, 2006,(Agencywide Documents Access and Management System (ADAMS) Accession Number ML060950095), Exelon Generation Company, LLC (EGC, or the licensee), requested changes to the Technical Specifications (TSs), for LaSalle County Station, Units 1 and 2 (LaSalle). The proposed changes would add one NRC-approved topical report reference to the list of analytical methods in TS 5.6.5, "Core Operating Limits Report (COLR)," that can be used to determine core operating limits and would delete seven obsolete references from the same TS section.Specifically, the proposed changes include the following:

1.Add a NRC previously approved Framatome ANP topical report reference fordetermination of minimum critical power ratio (MCPR) following a loss of feedwater heating transient event, and2.Remove seven obsolete references (References 2 - 8) which describe previouslyapproved Global Nuclear Fuel (GNF) and FRA-ANP methodologies for the analysis of ATRIUM-9B and GE9 fuel, both of which have or will be completely discharged from both LaSalle reactors after the loading of ATRIUM-10 fuel during the LaSalle, Unit 2, refueling outage currently scheduled for February 2007.The proposed changes are the result of a decision to reinsert FRA-ANP ATRIUM-10 fuel duringthe LaSalle, Unit 2, Refueling Outage 11, currently scheduled for February 2007. The ATRIUM-10 fuel is now manufactured and licensed by FRA-ANP a subsidiary of the AREVA group. This organization has previously been known as Siemens Power Corporation (SPC) and subsequently as FRA-ANP. The LaSalle, Unit 2, Cycle 12 core reload will be analyzed by FRA-ANP.

2.0REGULATORY EVALUATION

Section 50.36, paragraph (c)(5), of Title 10 of the Code of Federal Regulations (10 CFR) statesthat the TS will include administrative controls that address the provisions relating to organization and management, procedures, record keeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. The COLR is required as part of the reporting requirements specified in the LaSalle TS administrative controls. In addition, it isrequired that the analytical methods used to determine the core operating limits be approved and described in the administrative controls section of the TS. The proposed changes ensure that these requirements are met.General Design Criterion (GDC) 10, "Reactor design," of Appendix A to 10 CFR Part 50requires that specified acceptable fuel design limits are not exceeded during any operation, including the effects of anticipated operational transients.Generic Letter 88-16, "Guidance For Technical Specification Changes For Cycle-SpecificParameter Limits," provides guidance for reporting requirements.

3.0TECHNICAL EVALUATION

The analytical methods currently listed in TS 5.6.5 support the determination of core operatinglimits for both units by using GNF or FRA-ANP methodology. LaSalle, Unit 1, currently uses a mixture of ATRIUM-10 and GE-14 fuel in the core. The determination of GE-14 and ATRIUM-10 fuel assembly critical power for the current operating cycle is determined with a FRA-ANP critical power correlation. This method has been previously approved by the NRC for use with GE-14 fuel. Overall core operating limits for LaSalle, Unit 1, are determined using a FRA-ANP methodology, including a cycle-specific FRA-ANP evaluation of loss of feedwater heater(LOFWH) transients.

LaSalle, Unit 2, currently uses a mixture of ATRIUM-9B, ATRIUM-10 and GE-14 fuel. Thedetermination of fuel assembly critical power for the mixture of ATRIUM-9B, ATRIUM-10 and GE-14 fuel is determined with a GNF critical power correlation, and overall core operating limits are determined using GNF methodology. EGC will continue to load FRA-ANP ATRIUM-10 and completely discharge ATRIUM-9B duringthe upcoming LaSalle, Unit 2, Refueling Outage 11 currently scheduled to begin February 2007.

All GE-9 fuel was completely discharged during a previous refueling outage. LaSalle will use the most recent FRA-ANP methodologies to determine overall core operating limits for future core configurations, verses the current GNF methodology. This change will require the listing of an additional analytical methodology for evaluating LOFWH conditions with the FRA-ANPmethodology. Thus, the proposed changes will allow LaSalle to use FRA-ANP's most recent LOFWH analytical method to determine core operating limits for LaSalle. TS 5.6.5 requires that a COLR be established and that the analytical methods used todetermine the core operating limits be those previously reviewed and approved by the NRC.

The approved analytical methods are listed in TS 5.6.5.b. The analytical methods listed in this section support operation of certain types of fuel contained in the reactor core and list the analytical codes used to calculate operating parameters. The analytical codes are utilized to predict core behavior under normal and accident conditions. The proposed additional code is discussed below.The NRC-approved Topical Rreport ANF-1358(P), Revision 3, "The Loss of Feedwater HeatingTransient in Boiling Water Reactors (Reference 1)." This topical report presented revisions for an approved methodology for determining the MCPR following a LOFWH event. LaSalle has determined that the use of this FRA-ANP topical report and the processes for the application ofthe critical power correlation to pre-existing co-resident fuel as described in Reference 2 are appropriate for LaSalle, and provides an equivalent level of protection as that currently provided. Since ANF-1358(P), Revision 3, has been reviewed and approved in Reference 3 for application by FRA-ANP to previously exposed co-resident fuel in safety analyses for mixed reload cores, the NRC staff finds it acceptable to reference this topical report in LaSalle TS 5.6.5.References 2 - 8 are specific to ATRIUM 9B and GE-9 fuels. As both LaSalle units will containonly ATRIUM-10 and GE-14 fuel after the refueling outage for LaSalle, Unit 2, the references are obsolete and should be removed from the TS. Based on its review, the NRC staff concludes that the proposed changes to LaSalle, TS Section5.6.5, to add the Topical Report ANF-1358(P) (Revision 3), as a reference to be used for calculating cycle-specific core operating limits is acceptable for incorporation because the reference is an approved vendor topical report which is applicable to and has been validated for the analyses of LaSalle reload cores. Furthermore, the removal of Topical Reports ANF-1125(P)(A), ANF-89-014(P)(A), ANF-91-048(P)(A), EMF-1125(P)(A), ANF-1125(P)(A),

NEDC-32981P(A), and the letter from Ashok C.Thadani (NRC) from the COLR is acceptable because these references are made obsolete with the removal of ATRIUM-9B and GE-9 fuel from the LaSalle cores.

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 requirements with respect to the installation or use of the facilitiescomponents 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. TheCommission 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 46933; dated August 15, 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: J. Kaizer Date: February 15, 2007

7.0REFERENCES

1.Letter from H. N. Berkow (U.S. NRC) to R. L. Gardner (Framatome), Final SafetyEvaluation for Framatome ANP Topical Report ANF-1358(P), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," dated September 20, 2005.2.ANF-1125(P)(A), "ANFB Critical Power Correlation."

3.Letter, Ashok C. Thadani (NRC) to R. A. Copeland (SPC), "Acceptance for Referencingof ULTRAFLOW TM Spacer on 9x9-IX/X BWR Design," July 28, 1993.4.ANF-89-014(P)(A), "ANF Corporation Generic Mechanical Design for ANF Corporation9x9-IX and 9x9-9X BWR Reload Fuel." 5.ANF-91-048(P)(A), "ANF Corporation Methodology for Boiling Water Reactors EXEMBWR Evaluation Model." 6.EMF-1125(P)(A), "ANFB Critical Power Correlation Application for Co-Resident Fuel."

7.ANF-1125(P)(A), "ANFB Critical Power Correlation Determination of ATRIUM-9BAdditive Constant Uncertainties." 8.NEDC-32981P(A), "GEXL96 Correlation for Atrium-9B Fuel."