ML031920183

Issuance of Amendment Nos. 160 and 146, Respectively, Approving Changes Described in Updated Final Safety Analysis Report

ML031920183
Person / Time
Site:	LaSalle
Issue date:	08/13/2003
From:	Macon W NRC/NRR/DLPM/LPD3
To:	Skolds J Exelon Nuclear
References
TAC MB7001, TAC MB7002
Download: ML031920183 (15)

Text

August 13, 2003 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 AMENDMENT (TAC NOS. MB7001 AND MB7002)

Dear Mr. Skolds:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 160 to Facility Operating License No. NPF-11 and Amendment No. 146 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 December 20, 2002, as supplemented by letters dated May 30, and June 27, 2003.

The amendments approve changes to the LaSalle County Station facility as described in the Updated Final Safety Analysis Report. The amendments modify the basis for compliance with the requirements of Appendix H to Title 10 of the Code of Federal Regulations Part 50 (Appendix H to 10 CFR Part 50), Reactor Vessel Material Surveillance Program Requirements, by approving implementation of the Boiling-Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next 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 and 50-374

Enclosures:

1. Amendment No. 160 to NPF-11

2. Amendment No. 146 to NPF-18

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

August 13, 2003 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 AMENDMENT (TAC NOS. MB7001 AND MB7002)

Dear Mr. Skolds:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment No. 160 to Facility Operating License No. NPF-11 and Amendment No. 146 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 December 20, 2002, as supplemented by letters dated May 30, and June 27, 2003.

The amendments approve changes to the LaSalle County Station facility as described in the Updated Final Safety Analysis Report. The amendments modify the basis for compliance with the requirements of Appendix H to Title 10 of the Code of Federal Regulations Part 50 (Appendix H to 10 CFR Part 50), Reactor Vessel Material Surveillance Program Requirements, by approving implementation of the Boiling-Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next 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 and 50-374

Enclosures:

1. Amendment No. 160 to NPF-11

2. Amendment No. 146 to NPF-18

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

PUBLIC PDIII-2 r/f OGC GHill (4)

WBeckner ACRS DHills, RIII ADAMS Accession Number: ML031920183 *SE dated 07/03/03 OFFICE PM:LPD3-2 LA:LPD3-2 SC:EMCB OGC SC:LPD3-2 NAME WMacon THarris for PCoates SCoffin* SCole AMendiola DATE 07/21/03 07/18/03 07/03/03 07/28/03 08/12/03 OFFICIAL RECORD COPY

LaSalle County Station Units 1 and 2 cc:

Site Vice President - LaSalle Robert Cushing, Chief, Public Utilities Division Exelon Generation Company, LLC Illinois Attorney Generals Office 2601 North 21st Road 100 W. Randolph Street Marseilles, IL 61341-9757 Chicago, IL 60601 LaSalle County Station Plant Manager 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 Regulatory Assurance Manager - LaSalle 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 U.S. Nuclear Regulatory Commission Document Control Desk-Licensing 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 Senior Vice President - Nuclear Services Sidley and Austin Exelon Generation Company, LLC One First National Plaza 4300 Winfield Road Chicago, IL 60603 Warrenville, IL 60555 Assistant Attorney General Vice President 100 W. Randolph St. Suite 12 Mid-West Operations Support Chicago, IL 60601 Exelon Generation Company, LLC 4300 Winfield Road Chairman Warrenville, IL 60555 LaSalle County Board 707 Etna Road Senior Vice President Ottawa, IL 61350 Mid-West Regional Operating Group Exelon Generation Company, LLC Attorney General 4300 Winfield Road 500 S. Second Street Warrenville, IL 60555 Springfield, IL 62701 Vice President - Licensing and Regulatory Chairman Affairs Illinois Commerce Commission Exelon Generation Company, LLC 527 E. Capitol Avenue, Leland Building 4300 Winfield Road Springfield, IL 62706 Warrenville, IL 60555

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

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 160 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 December 20, 2002, as supplemented by letter dated May 30, and June 27, 2003, 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 to authorize revision of the Updated Final Safety Analysis Report (UFSAR) as set forth in the application for amendment by the licensee, dated December 20, 2002, as supplemented by letters dated May 30, and June 27, 2003. The licensee shall update the UFSAR by modifying the basis for compliance with the requirements of Appendix H to Title 10 of the Code of Federal Regulations Part 50 (Appendix H to 10 CFR Part 50), Reactor Vessel Material Surveillance Program Requirements, to implement the Boiling-Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program, as authorized by this amendment and in accordance with 10 CFR 50.71(e).

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/

Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Date of Issuance: August 13, 2003

EXELON GENERATION COMPANY, LLC DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 146 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 December 20, 2002, as supplemented by letter dated May 30, and June 27, 2003, 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 to authorize revision of the Updated Final Safety Analysis Report (UFSAR) as set forth in the application for amendment by the licensee, dated December 20, 2002, as supplemented by letters dated May 30, and June 27, 2003. The licensee shall update the UFSAR by modifying the basis for compliance with the requirements of Appendix H to Title 10 of the Code of Federal Regulations Part 50 (Appendix H to 10 CFR Part 50), Reactor Vessel Material Surveillance Program Requirements, to implement the Boiling-Water Reactor Vessel and Internals Project reactor pressure vessel integrated surveillance program, as authorized by this amendment and in accordance with 10 CFR 50.71(e).

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/

Anthony J. Mendiola, Chief, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Date of Issuance: August 13, 2003

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 160 TO FACILITY OPERATING LICENSE NO. NPF-11 AND AMENDMENT NO. 146 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 letter dated December 20, 2002 [1], Exelon Generation Company, LLC (EGC), the licensee for LaSalle County Station (LSCS), Units 1 and 2, submitted a request for Nuclear Regulatory Commission (NRC) review and approval of a license amendment to modify the basis for their compliance with the requirements of Appendix H to Title 10 of the Code of Federal Regulations Part 50 (Appendix H to 10 CFR Part 50), Reactor Vessel Material Surveillance Program Requirements. In their license amendment submittal, EGC requested that they be approved to implement the Boiling-Water Reactor Vessel and Internals Project (BWRVIP) reactor pressure vessel (RPV) integrated surveillance program (ISP) as the basis for demonstrating the compliance of LSCS, Units 1 and 2, with the requirements of Appendix H to 10 CFR Part 50. In response to questions of clarification raised by the NRC staff during a teleconference on April 3, 2003, EGC submitted additional information by letters dated May 30 [2], and June 27, 2003 [3],

respectively, to support their original request.

The BWRVIP RPV ISP was submitted for NRC staff review and approval in topical reports BWRVIP-78, BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan, and BWRVIP-86, BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan [4,5]. Additional information necessary to establish the technical basis for, and proposed implementation of, the BWRVIP ISP was provided in letters from the BWRVIP to the NRC dated December 15, 2000, and May 30, 2001 [6,7]. The NRC staff approved the proposed BWRVIP ISP in a safety evaluation (SE) which was provided to the BWRVIP by letter dated February 1, 2002 [8]. However, the NRC staffs SE required that plant-specific information be provided by BWR licensees who wish to implement the BWRVIP ISP for their facilities. EGCs December 20, 2002, May 30, and June 27, 2003, submittals addressed the plant-specific information required in the NRC staffs February 1, 2002, BWRVIP ISP SE.

The supplemental letters contained clarifying information and did not change the initial no significant hazards consideration determination and did not expand the scope of the original Federal Register Notice.

2.0 REGULATORY EVALUATION

Nuclear power plant licensees are required by Appendix H to 10 CFR Part 50 to implement RPV surveillance programs to monitor changes in the fracture toughness properties of ferritic materials in the reactor vessel beltline region...which result from exposure of these materials to neutron irradiation and the thermal environment. Two specific alternatives are provided with regard to the design of a facilitys RPV surveillance program which may be used to address the requirements of Appendix H to 10 CFR Part 50.

The first alternative is the implementation of a plant-specific RPV surveillance program consistent with the requirements of American Society for Testing and Materials (ASTM)

Standard Practice E 185, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels. In the design of a plant-specific RPV surveillance program, a licensee may use the edition of ASTM Standard Practice E 185 which was current on the issue date of the American Society of Mechanical Engineers (ASME) Code to which the reactor vessel was purchased, or later editions through the 1982 edition.

The second alternative provided in Appendix H to 10 CFR Part 50 is the implementation of an ISP. An ISP is defined in Appendix H to 10 CFR Part 50 as occurring when, the representative materials chosen for surveillance for a reactor are irradiated in one or more other reactors that have similar design and operating features. Five specific criteria are stated in Section III.C.1 of Appendix H to 10 CFR Part 50 which must be met to support approval of an ISP:

a. The reactor in which the materials will be irradiated and the reactor for which the materials are being irradiated must have sufficiently similar design and operating features to permit accurate comparisons of the predicted amount of radiation damage.

b. Each reactor must have an adequate dosimetry program.

c. There must be adequate arrangement for data sharing between plants.

d. There must be a contingency plan to assure that the surveillance program for each reactor will not be jeopardized by operation at reduced power level or by an extended outage of another reactor from which data are expected.

e. There must be substantial advantages to be gained, such as reduced power outages or reduced personnel exposure to radiation, as a direct result of not requiring surveillance capsules in all reactors in the set.

As noted in Section 1.0 of this SE, the NRC staff approved the proposed BWRVIP ISP in a SE which was issued to the BWRVIP by letter dated February 1, 2002 [8]. All of the criteria cited above for approval of the ISP were addressed either completely or partially in Reference 8. For those criteria which could not be fully addressed in Reference 8, plant-specific information would be required from licensees who wished to implement the BWRVIP for their facilities. As stated in Reference 8:

[L]icensees who wish to participate in the BWR ISP must provide, for NRC staff review and approval, information which defines how they will determine RPV and/or surveillance capsule fluences based on the dosimetry data which will be available for their facilities. This information must be submitted concurrently with each licensees submittal to replace their existing plant-specific surveillance program with the BWR ISP as part of their facilitys licensing basis. The information submitted must be sufficient for the staff to determine that:

(1) RPV and surveillance capsule fluences will be established as based on the use of an NRC-approved fluence methodology that will provide acceptable results based on the available dosimetry data, (2) if one methodology is used to determine the neutron fluence values for a licensees RPV and one or more different methodologies are used to establish the neutron fluence values for the ISP surveillance capsules which represent that RPV in the ISP, the results of these differing methodologies are compatible (i.e., within acceptable levels of uncertainty for each calculation).

This plant-specific information was required by the NRC staff to ensure that criterion III.C.1.b of Appendix H to 10 CFR Part 50 for an ISP could be met by each facility, and to confirm that data which would be shared as part of the BWRVIP ISP could be effectively utilized by each licensee for the monitoring of RPV embrittlement for their facility.

3.0 TECHNICAL EVALUATION

In their letters dated December 20, 2002, May 30, and June 27, 2003, EGC submitted information for LSCS, Units 1 and 2, which addressed the information requested in the NRC staffs February 1, 2002, BWRVIP ISP SE [8]. EGC submitted a revised Section 4.1.4.5 of the LSCS, Units 1 and 2, UFSAR by Reference 3, which stated:

More recently, the NRC issued Regulatory Guide (RG) 1.190, which provides state of the art calculation and measurement procedures that are acceptable to the NRC for determining Reactor Pressure Vessel (RPV) neutron fluence. LSCS RPV fluence has been evaluated using a method in accordance with the recommendations of RG 1.190.

Future evaluations of RPV fluence will be completed using a method in accordance with the recommendations of RG 1.190.

The NRC staff has concluded that the inclusion of this statement in the LSCS, Units 1 and 2, UFSAR is sufficient to address both items (1) and (2) from Reference 8. Regarding item (1),

the licensees use of a methodology for determining the LSCS, Units 1 and 2, RPV neutron fluence values which is consistent with the attributes of RG 1.190 and has been approved by the NRC staff will provide acceptable results based upon the available dosimetry data.

Regarding item (2), RPV surveillance capsules tested under the BWRVIP ISP will have their fluences determined by the use of a methodology which is consistent with the attributes of RG 1.190 and has been approved by the NRC staff. The NRC staff has concluded that any two (or more) different fluence methodologies will provide compatible (as defined in Reference 8) results provided that the best estimate fluence values are within each others uncertainty bounds.

Inasmuch as this action was submitted as a license amendment, consistent with the NRC staffs understanding of the decision given in Commission Memorandum and Order CLI-96-13, EGC provided a revised Section 5.3.1.6.1 of the LSCS, Units 1 and 2, UFSAR by Reference 2 which documented the licensees incorporation of the BWRVIP ISP into the LSCS, Units 1 and 2, licensing basis:

A material surveillance program was developed and initiated at the beginning of nuclear operation of LSCS. This surveillance program was designed to be in accordance with the requirements of 10 CFR 50 Appendix H, as discussed in UFSAR Section 5.2.3.3.1.9.

In 2003, the NRC approved LSCS participation in the BWR Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) as described in BWRVIP-78 and BWRVIP-86 (Reference 1) [BWRVIP-86-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP), Final Report, October 2002].

The NRC approved the ISP for the industry in Reference 1 and approved LSCS participation... The ISP meets the requirements of 10 CFR Part 50 Appendix H and provides several advantages over the original program... The current withdrawal schedule is based on the latest NRC-approved revision of BWRVIP-86 (Reference 1).

In addition, EGC provided, in Table 5.2-12 of the LSCS UFSAR, the revised withdrawal schedule for LSCS, Units 1 and 2, in accordance with the NRC staff approved BWRVIP-86.

The NRC staff has concluded that the information provided in the revised LSCS, Units 1 and 2, UFSAR is adequate to document the licensees intent to appropriately implement the BWRVIP ISP as the method for demonstrating the compliance of LSCS, Units 1 and 2, with the requirements of Appendix H to 10 CFR Part 50.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20, or changes an inspection or surveillance requirement. The NRC staff has determined that the amendment involves 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 amendment involves no significant hazards consideration and there has been no public comment on such finding (68 FR 5669). Accordingly, the amendment meets 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 amendment.

6.0 CONCLUSION

The staff 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

7.0 REFERENCES

[1] M. P. Gallagher (EGC and AmerGen) to U.S. NRC Document Control Desk, "Request for License Amendment Regarding Reactor Vessel Specimen Removal Schedule,"

December 20, 2002

[2] K. R. Jury (EGC and AmerGen) to U.S. NRC Document Control Desk, "Additional Information Supporting the Request for License Amendment Regarding Reactor Vessel Specimen Removal Schedule," May 30, 2003

[3] K. A. Ainger (EGC and AmerGen) to U.S. NRC Document Control Desk, "Additional Information Supporting the Request for License Amendment Regarding Reactor Vessel Specimen Removal Schedule," June 27, 2003

[4] C. Terry (BWRVIP) to U.S. NRC Document Control Desk, Project No. 704 - BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan (BWRVIP-78), December 22, 1999

[5] C. Terry (BWRVIP) to U.S. NRC Document Control Desk, "Project No. 704 -

BWRVIP-86: BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan," EPRI Technical Report 1000888, December 22, 2000

[6] C. Terry (BWRVIP) to U.S. NRC Document Control Desk, "PROJECT NO. 704 -

BWRVIP Response to NRC Request for Additional Information Regarding BWRVIP-78,"

December 15, 2000

[7] C. Terry (BWRVIP) to U.S. NRC Document Control Desk, "PROJECT NO. 704 -

BWRVIP Response to Second NRC Request for Additional Information on the BWR Integrated Surveillance Program," May 30, 2001

[8] W. H. Bateman (USNRC) to C. Terry, "Safety Evaluation Regarding EPRI Proprietary Reports "BWR Vessel and Internals Project, BWR Integrated Surveillance Program Plan (BWRVIP-78)" and "BWRVIP-86: BWR Vessel and Internals Project, BWR Integrated Surveillance Program Implementation Plan,"" February 1, 2002 Principal Contributor: J. Honcharik, EMCB/NRR; L. Lois, SRXB/NRR Date: August 13, 2003