ML022520116

Issuance of Amendments 146 & 142 to Licenses NPF-11 & NPF-18, Respectively, Extending the Use of Pressure & Temperature Limit Curves in Technical Specification 3.4.11

ML022520116
Person / Time
Site:	LaSalle
Issue date:	12/03/2002
From:	Macon W NRC/NRR/DLPM/LPD3
To:	Skolds J Exelon Nuclear
Macon W, NRR/DLPM/LPDIII-02, 415-3965
References
TAC MB5658, TAC MB5667
Download: ML022520116 (12)

Text

December 3, 2002 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO EXTEND THE USE OF PRESSURE AND TEMPERATURE LIMIT CURVES (TAC NOS. MB5657 AND MB5658)

Dear Mr. Skolds:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 156 to Facility Operating License No. NPF-11 and Amendment No. 142 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 July 19, 2002, as supplemented by letters dated October 21 and November 8, 2002.

The amendments extend the use of the current pressure and temperature (P/T) limit curves in Technical Specification (TS) 3.4.11, "RCS Pressure and Temperature (P/T) Limits," until December 15, 2004. The change will allow sufficient time for the incorporation of the General Electric Topical Report NEDC-32983P, "General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation," methodology into the P/T curves in TS 3.4.11.

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/

William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374

Enclosures:

1. Amendment No. 156 to NPF-11

2. Amendment No. 142 to NPF-18

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

LaSalle County Station Units 1 and 2 cc:

Site Vice President - LaSalle Regional Administrator Exelon Generation Company, LLC U.S. NRC, Region III 2601 North 21st Road 801 Warrenville Road Marseilles, IL 61341-9757 Lisle, IL 60532-4351 LaSalle County Station Plant Manager Illinois Department of Nuclear Safety Exelon Generation Company, LLC Office of Nuclear Facility Safety 2601 North 21st Road 1035 Outer Park Drive Marseilles, IL 61341-9757 Springfield, IL 62704 Regulatory Assurance Manager - LaSalle Document Control Desk-Licensing Exelon Generation Company, LLC Exelon Generation Company, LLC 2601 North 21st Road 4300 Winfield Road Marseilles, IL 61341-9757 Warrenville, IL 60555 U.S. Nuclear Regulatory Commission Senior Vice President - Nuclear Services LaSalle Resident Inspectors Office Exelon Generation Company, LLC 2605 North 21st Road 4300 Winfield Road Marseilles, IL 61341-9756 Warrenville, IL 60555 Phillip P. Steptoe, Esquire Vice President Sidley and Austin Mid-West Operations Support One First National Plaza Exelon Generation Company, LLC Chicago, IL 60603 4300 Winfield Road Warrenville, IL 60555 Assistant Attorney General 100 W. Randolph St. Suite 12 Senior Vice President Chicago, IL 60601 Mid-West Regional Operating Group Exelon Generation Company, LLC Chairman 4300 Winfield Road LaSalle County Board Warrenville, IL 60555 707 Etna Road Ottawa, IL 61350 Vice President - Licensing and Regulatory Affairs Attorney General Exelon Generation Company, LLC 500 S. Second Street 4300 Winfield Road Springfield, IL 62701 Warrenville, IL 60555 Chairman Illinois Commerce Commission 527 E. Capitol Avenue, Leland Building Springfield, IL 62706 Robert Cushing, Chief, Public Utilities Division Illinois Attorney Generals Office 100 W. Randolph Street Chicago, IL 60601

LaSalle County Station Units 1 and 2 Director - Licensing Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Counsel, Nuclear Mid-West Regional Operating Group Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager - Licensing -Clinton and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

December 3, 2002 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO EXTEND THE USE OF PRESSURE AND TEMPERATURE LIMIT CURVES (TAC NOS. MB5657 AND MB5658)

Dear Mr. Skolds:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 156 to Facility Operating License No. NPF-11 and Amendment No. 142 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 July 19, 2002, as supplemented by letters dated October 21 and November 8, 2002.

The amendments extend the use of the current pressure and temperature (P/T) limit curves in Technical Specification (TS) 3.4.11, "RCS Pressure and Temperature (P/T) Limits," until December 15, 2004. The change will allow sufficient time for the incorporation of the General Electric Topical Report NEDC-32983P, "General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation," methodology into the P/T curves in TS 3.4.11.

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/

William A. Macon, Jr., Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-373, 50-374

Enclosures:

1. Amendment No. 156 to NPF-11

2. Amendment No. 142 to NPF-18

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

Public AMendiola WMacon CRosenberg PD3-2 r/f OGC, O15B18 ACRS. T2E26 LLois GHill (4), T5C3 RDennig BBurgess, RIII PKG.: ML023440398 ADAMS Accession Number: ML022520116 TS: ML023440216 OFFICE PM:LPD3-2 LA:LPD3-2 SC:SRXB OGC SC:LPD3-2 NAME WMacon, Jr. CRosenberg FAkstulewicz DGauch LRaghavan for AMendiola DATE 11/12/02 11/12/02 11/12/02 11/15 /02 12/2/02 OFFICIAL RECORD COPY

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. NPF-11

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment filed by the Exelon Generation Company, LLC (the licensee), dated July 19, 2002, as supplemented by letters dated October 21 and November 8, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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 set forth in 10 CFR Chapter I; 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 enclosure 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 Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 156, 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 until December 15, 2004, and shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by LRaghavan for/

Anthony J. Mendiola, 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: December 3, 2002

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. NPF-18

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment filed by the Exelon Generation Company, LLC (the licensee), dated July 19, 2002, as supplemented by letters dated October 21 and November 8, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 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 set forth in 10 CFR Chapter I; 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 enclosure 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 Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 142, 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 until December 15, 2004, and shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by LRaghavan for/

Anthony J. Mendiola, 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: December 3, 2002

ATTACHMENT TO LICENSE AMENDMENT NOS. 156 & 142 FACILITY OPERATING LICENSE NO. NPF-11 AND NPF-18 DOCKET NOS. 50-373 AND 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove Pages Insert Pages 3.4.11-6 3.4.11-6 3.4.11-7 3.4.11-7 3.4.11-8 3.4.11-8 3.4.11-9 3.4.11-9 3.4.11-10 3.4.11-10 3.4.11-11 3.4.11-11

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 156 TO FACILITY OPERATING LICENSE NO. NPF-11 AND AMENDMENT NO. 142 TO FACILITY OPERATING LICENSE NO. NPF-18 EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374

1.0 INTRODUCTION

By application dated July 19, 2002, as supplemented by letters dated October 21 and November 8, 2002, Exelon Generation Company (Exelon, the licensee) requested changes to the Technical Specifications (TS) for the LaSalle County Station, Units 1 and 2. The supplements dated October 21, 2002, and November 8, 2002, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on October 30, 2002 (67 FR 66170).

The proposed change would extend the use of the current pressure and temperature (P/T) limit curves in TS 3.4.11, "RCS Pressure and Temperature (P/T) Limits," until December 15, 2004.

The proposed change will allow sufficient time for the incorporation of the results of the General Electric Topical Report NEDC-32983P, "General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation," methodology into the P/T curves in TS 3.4.11. The staff previously approved the current interim P/T limits based on estimated conservatism at the time of their applicability. The original limits were calculated for 32 effective full power years (EFPY);

however, the methodology used was not acceptable to the staff. The current interim limits are valid for about 16 EFPY and their approval was based on a factor of 2 conservatism in the period of validity. The staff approved the current interim limits to give the licensee time to use a staff approved methodology to recalculate the peak vessel fluence to the end of the current license.

2.0 REGULATORY EVALUATION

The staff finds that the licensee in Section 4.0 of Attachment 2 of its October 21, 2002, submittal identified the applicable regulatory requirements. The regulatory requirements for which the staff based its acceptance are 10 CFR 50.36(c)(2)(ii)(B), "Criterion 2," which requires that a process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier, must be included in a licensee's TS.

Additionally, Regulatory Guide (RG) 1.190, published in March 2001, describes fluence calculational methods acceptable to the staff (Reference 1). Therefore, this review seeks to

establish that the methodology used followed the guidance in RG 1.190, that it was applied correctly, and that the available EFPY are adequate for the extension requested.

3.0 TECHNICAL EVALUATION

The staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment which are described in Sections 5.0 and 6.0 of Attachment 2 of the licensees October 21, 2002, submittal. The detailed evaluation below will support the conclusion that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

On November 8, 2000, the staff approved the current P/T limits in Amendment 144 for Unit 1 and Amendment 130 for Unit 2. In the issuance of these amendments, the staff limited the use of the P/T curves to an interim period not to exceed December 15, 2002. The staff approved this interim period on the basis of a factor of 2 conservatism between the 32 EFPY of the original calculation and the 16 EFPY of the interim period of approval. (Note: the current P/T limit curves are common to both Units, because they assumed the same fluence and the same limiting beltline element.)

The licensee submitted the plant specific report GE-NE-0000-0002-5244-02 (Reference 2) that details the calculational method and the assumptions and inputs for the peak vessel fluence evaluation. The staff confirmed that the calculational method adheres to the guidance in RG 1.190 and that the licensee used the staff approved method described in NEDC-32983PA (Reference 3). The licensee used cross sections based on the ENDF/B-VI data file as stated in RG 1.190. The calculation assumes a power level of 3489 MWt from initiation of reactor operation. The assumed power level is conservative in that it assumes the uprated power for the entire operating history of the plant.

The licensee calculated the peak vessel inside surface fluence values for both Units 1 and 2.

The calculated values for 32 EFPY are: 1.02x1018 n/cm2 and 1.09x1018 n/cm2 , respectively.

These values are considerably higher than the values used in the development of the current P-T limits of 5.0x1017 n/cm2 for Unit 1 and 6.03x1017 n/cm2 for Unit 2. At the present power level, the calculated peak fluence values are estimated to occur at 15.7 EFPY for Unit 1 and 17.7 EFPY for Unit 2. As of June 2002, Unit 1 had accumulated 11.6 EFPY and Unit 2 had accumulated 11.0 EFPY. The licensee calculated, and the staff agrees, that Unit 1 could operate for another 4.1 EFPY and Unit 2 for another 6.7 EFPY before they would reach the fluence limit of the current P/T curves. Unit 1 is expected to reach its value first. Assuming that Unit 1 operates at 100 percent load factor, it will not reach this value until after June 2006.

The staff reviewed the information submitted by the licensee in support of their request for continued use of the current P/T curves to allow time for preparation of new P/T limit curves.

The licensee recalculated the peak vessel fluence using a staff approved methodology which satisfies the guidance in RG 1.190. The staff concluded that the new values indicate that the current P-T curves are acceptable and will remain valid until June 2006. Therefore, the staff has approved the requested change for the continued use of the current limits for an interim period not to exceed December 15, 2004.

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 a requirement with respect to the 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 (67 FR 66170). 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. RG 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, U.S. Nuclear Regulatory Commission, March 2001.

2. GE-NE-0000-0002-5244-02, LaSalle 1 and 2 Neutron Flux Evaluation, by Tang Wu, General Electric, June 2002.

3. NEDC-32983PA, Rev. 0, Licensing Topical Report, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluations, December 2001.

Principal Contributor: L. Lois Date: December 3, 2002