ML090610133

Units, 1 and 2 - License Amendments 158, 158, 163 & 163, Revision to Containment Tendon Surveillance Program

ML090610133
Person / Time
Site:	Byron, Braidwood
Issue date:	03/26/2009
From:	David M Plant Licensing Branch III
To:	Pardee C Exelon Nuclear
David, Marshall - DORL 415-1547
References
TAC MD8515, TAC MD8516, TAC MD8517, TAC MD8518
Download: ML090610133 (27)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 March 26, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS RE: REVISION TO CONTAINMENT TENDON SURVEILLANCE PROGRAM (TAC NOS. MD8515, MD8516, MD8517, AND MD8518)

Dear Mr. Pardee:

The Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 158 to Facility Operating License No. NPF-72 and Amendment No. 158 to Facility Operating License No. NPF-77 for the Braidwood Station, Units 1 and 2, and Amendment No. 163 to Facility Operating License No. NPF-37 and Amendment No. 163 to Facility Operating License No.

NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively. The amendments are in response to your application dated April 9, 2008, as supplemented by letter dated October 1, 2008.

The amendments revise Technical Specifications 5.5.6, "Pre-Stressed Concrete Containment Tendon Surveillance Program," and 5.6.8, "Tendon Surveillance Report," for consistency with the requirements of Title 10 Code of Federal Regulations (10 CFR) Section 50.55a, "Codes and standards," paragraph (g)(4) for components classified as American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Class CC, by replacing the reference to the specific ASNIE Code year for the tendon surveillance program with a requirement to use the applicable ASME Code and addenda as required by 10 CFR 50.55a.

C. Pardee -2 A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/~i~WO Mars~~~. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456, STN 50-457, STI\J 50-454, and STN 50-455

Enclosures:

1. Amendment NO.158 to I\JPF-72

2. Amendment NO.158 to NPF-77

3. Amendment NO.163 to NPF-37

4. Amendment No.163 to NPF-66

5. Safety Evaluation cc w/encls: Distribution via ListServ

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-456 BRAIDWOOD STATION, Ut\IIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 158 License No. NPF-72

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

A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated April 9, 2008, as supplemented by letter dated October 1,2008, 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 the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. t\IPF-72 is hereby amended to read as follows:

-2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 158, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance: 1\1arch 26, 2009

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 158 License No. NPF-77

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

A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated April 9, 2008, as supplemented by letter dated October 1,2008, 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 the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:

-2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.158 , 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. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 11Jwr¥a Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance:March 26, 2009

ATTACHMENT TO LICENSE AMENDMENT NOS158 AND 158 FACILITY OPERATING LICENSE NOS. I\lPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-72 License NPF-72 License Page 3 License Page 3 License NPF-77 License NPF-77 License Page 3 License Page 3 TSs TSs 5.5-5 5.5-5 5.6-6 5.6-6

-3 (3) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation Company, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. The license shall be deemed to contain and is subject to the conditions specified in the 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 Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified.

Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment NO.158 ,and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management 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. 158

-3 material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation Company, LLC pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts are required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. The license shall be deemed to contain and is subject to the conditions specified in the 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 Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified.

Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 1 5~ and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management 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. 158

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC. Determining pre stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1.35.1, July 1990.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

In lieu of Regulatory Position c.4.b(l) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASI'1E Section XI.

BRAI DWOOD - UI~ ITS 1 & 2 5.5 - 5 Amendment158

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASlvlE Secti on XI.

5.6.9 Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.9, Steam Generator (SG) Program.

The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism,

f. Total number and percentage of tubes plugged or repaired to date,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing,

h. The effective plugging percentage for all plugging and tube repairs in each SG,

i. Repai r method uti l i zed and the number of tubes repai red by each repair method, J. For Unit 2, following completion of an inspection performed in Refueling Outage 13 (and any inspections performed in the subsequent operating cycle), the number of indications and location, size, orientation, and whether initiated on primary or secondary side for each service induced flaw detected within the thickness of the tubesheet, and the total of the circumferential components and any circumferential overlap below 17 inches from the top of the tubesheet, as determined in accordance with TS 5.5.9 c.4.i, BRAIDWOOD - UI~ ITS 1 & 2 5.6 - 6 Amendment 158

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELOI\J GENERATION COMPANY, LLC DOCKET NO. STN 50-454 BYRON STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. I\JPF-37

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

A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated April 9, 2008, as supplemented by letter dated October 1,2008, 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 the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:

-2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 163, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance: ~1arch 26, 2009

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GEt\IERATION COMPANY, LLC DOCKET NO. STN 50-455 BYRON STATION, UNIT NO.2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. NPF-66

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

A. The application for amendment by Exelon Generation Company, LLC (the licensee) dated April 9, 2008, as supplemented by letter dated October 1,2008, 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 the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-66 is hereby amended to read as follows:

-2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG 1113), as revised through Amendment No. 163, and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. NPF-37, dated February 14, 1985, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Russell Gibbs, Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications and Facility Operating License Date of Issuance: March 26, 2009

ATTACHMENT TO LICENSE AMENDMENT NOS.163 AND 163 FACILITY OPERATING LICENSE NOS. NPF-37 AND I\IPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert License NPF-37 License NPF-37 License Page 3 License Page 3 License NPF-66 License NPF-66 License Page 3 License Page 3 TSs TSs 5.5-5 5.5-5 5.6-6 5.6-6

-3 (4) Pursuant to the Act and 10 CFR Parts 30,40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. The license shall be deemed to contain and is subject to the conditions specified in 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 Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent power) in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.1 63 , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Deleted.

(4) Deleted.

(5) Deleted.

(6) The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the 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 protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

Amendment No. 163

-3 (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 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) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. The license shall be deemed to contain and is subject to the conditions specified in the 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 Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3586.6 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG 1113), as revised through Amendment No. 163, and the Environmental Protection Plan contained in Appendix B, both of which are attached to License No. t\lPF-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. 163

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the I~RC. Determining pre stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1.35.1, July 1990.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

In lieu of Regulatory Position c.4.b(1) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.

BYRON - UNITS 1 &2 5.5 - 5 Amendment 163

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.8 Tendon Surveillance Report Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50.55a and ASME Section XL 5.6.9 Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with Specification 5.5.9, Steam Generator (SG) Program.

The report shall include:

a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism,

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications,

e. Number of tubes plugged or repaired during the inspection outage for each active degradation mechanism,

f. Total number and percentage of tubes plugged or repaired to date,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing,

h. The effective plugging percentage for all plugging and tube repairs in each SG, and

i. Repair method utilized and the number of tubes repaired by each repair method.

j. For Unit 2, following completion of an inspection performed in Refueling Outage 14 (and any inspections performed in the subsequent operating cycle), the number of indications and location, size, orientation, and whether initiated on primary or secondary side for each service-induced flaw detected within the thickness of the tubesheet, and the total of the circumferential components and any circumferential overlap below 17 inches from the top of the tubesheet, as determined in accordance with TS 5.5.9 c.4.i, BYRON - UNITS 1 &2 5.6 - 6 Amendment 163

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.158TO FACILITY OPERATING LICENSE NO. NPF-72, AMENDMENT NO.158TO FACILITY OPERATING LICENSE NO. NPF-77, AMENDMENT NO.163TO FACILITY OPERATING LICENSE NO. NPF-37, AND AMENDMENT NO.163TO FACILITY OPERATING LICENSE NO. NPF-66 EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION, UNITS 1 AND 2 BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457, STN 50-454, AND STN 50-455

1.0 INTRODUCTION

By letter to the Nuclear Regulatory Commission (NRC, the Commission) dated April 9, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081010540), as supplemented by letter dated October 1, 2008 (ADAMS Accession No. ML082750420), Exelon Generation Company, LLC (EGC, the licensee) submitted a license amendment request (LAR) for Braidwood Station, Units 1 and 2 (Braidwood), and Byron Station, Unit Nos. 1 and 2 (Byron). The LAR proposed to revise Technical Specification (TS) 5.5.6, "Pre-stressed Concrete Containment Tendon Surveillance Program," and TS 5.6.8, "Tendon Surveillance Report," for consistency with the requirements of paragraph (g)(4) of Title 10 Code of Federal Regulations (10 CFR), Section 50.55a, "Codes and standards," for components classified as Code Class CC. Specifically, the proposed changes would replace or delete the reference to the specific American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) year for the tendon surveillance program with a requirement to use the applicable ASME Code edition and addenda as required by 10 CFR 50.55a(g)(4).

The supplemental letter dated October 1, 2008, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change NRC staff's original proposed no signiIicant hazards consideration determination published in an individual notice in the Federal Register on July 1, 2008 (73 FR 37504).

-2

2.0 BACKGROUND

These amendments affect TS 5.5.6 and TS 5.6.8 as stated below.

TS 5.5.6 Pre-stressed Concrete Containment Tendon Surveillance Program The relevant part of the existing TS 5.5.6 reads as follows:

"... The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in conformance with requirements of 10 CFR 50.55a(b)(2)(vi), 10 CFR 50.55a(b)(2)(ix), ASME Boiler and Pressure Vessel Code Subsection IWL, 1992 Edition with the 1992 Addenda and Regulatory Guide 1.35.1, July 1990.

The provisions of SR [Surveillance Requirement] 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies."

The proposed change, as shown in Attachment 2 (Braidwood) and Attachment 3 (Byron) of the October 1, 2008, supplement, revised the corresponding TS 5.5.6 sentences to read as follows:

"... The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC. Determining pre-stressing forces for inspections shall be consistent with the recommendations of Regulatory Guide 1.35.1, July 1990.

The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies."

The licensee included, for information, the markup of corresponding changes to TS Bases Pages B3.6.1-5 (for SR 3.6.1.2) and B 3.6.1-6 (References) in Attachment 3 (Braidwood) and (Byron) of the October 1, 2008, supplement.

TS 5.6.8 Tendon Surveillance Report The existing TS 5.6.8 reads as follows:

"Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10 CFR 50 .55a and ASME Section XI, 1992 Edition with the 1992 Addenda."

The proposed change, as shown in Attachment 2 (Braidwood) and Attachment 3 (Byron) of the April 9, 2008, request, revised TS 5.6.8 to read as follows:

"Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Inspection Summary Report in accordance with 10CFR 50.55a and ASME Section XI."

-3

3.0 REGULATORY EVALUATION

The licensee's LAR relates to its containment tendon surveillance program, which is classified as ASME Code Class CC.

In the Federal Register (Volume 61, Number 154, pages 41303-41312) dated August 8, 1996, the Commission amended 10 CFR 50.55a to incorporate by reference for the first time Subsection IWE and Subsection IWL of the 1992 Edition with the 1992 Addenda of the ASME Code,Section XI, Division 1, with specified modifications and a limitation for performing containment inservice examinations (refer to paragraphs (b)(2) and (b)(2)(vi) of the amended rule). The amended final rule became effective on September 9, 1996. Paragraph (g)(4) of the rule required licensees to incorporate Subsection IW E and Subsection IW L into their containment inservice inspection (CISI) program. Paragraph g(6)(ii)(B) of the amended rule required licensees to expedite implementation of the containment examinations in accordance with Subsection IWE and Subsection IWL by September 9, 2001. Subsection IWL of the ASIVlE Code,Section XI, provides rules for inservice inspection and repair of the reinforced concrete and the post-tensioning systems of Class CC components and applies to the containment tendon surveillance program. For Class CC components, paragraph (g)(6)(ii)(B)(2) of the amended 1996 rule, required licensees of all operating nuclear power plants to implement the inservice examination which corresponds to the number of years of operation which are specified in Subsection IWL of the 1992 Edition with the 1992 Addenda in conjunction with the modifications specified in 10 CFR 50.55a(b)(2)(ix) by September 9, 2001.

In accordance with paragraph (g)(4) and g(6)(ii)(B) of the amended 1996 10 CFR 50.55a rule, the 1992 Edition with 1992 Addenda of the ASME Code, Subsection IWE and Subsection IWL, became the Code of Record for the expedited examination and the initial (first) 120-month interval of the CISI program for Braidwood and Byron. However, 10 CFR 50.55a(g)(4)(ii) requires that the inservice examination during successive 120-month inspection intervals must be updated to comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of 10 CFR 50.55a, 12 months prior to the start of the 120-month inspection interval, subject to the limitations and modifications listed in paragraph (b).

By this LAR, the licensee is proposing an administrative change to update TS Sections 5.5.6 and 5.6.8 related to containment tendon surveillance program to delete the reference to the specific ASME Code (Section XI) edition and addenda (i.e., 1992 Edition with 1992 Addenda) with a requirement to be consistent with 10 CFR 50.55a(g)(4) with regard to the ASME Code (Section XI) edition and addenda for initial and successive 120-month intervals of the containment tendon surveillance program, which is part of the CISI program.

4.0 TECHNICAL EVALUATION

The licensee stated that the containments at Braidwood and at Byron are post-tensioned reinforced concrete structures which are classified as Class CC components. The post tensioning system for the cylindrical shell and the dome consists of unbonded tendons installed in ducts that are tensioned in a predetermined sequence and anchored at the ends. The containment post-tensioning tendons are subject to a tendon surveillance program, which is part of the CISI program. The SRs and reporting requirements for the post-tensioning tendons are specified in TS 5.5.6 and TS 5.6.8, respectively.

-4 As discussed in Section 3.0, the licensee's Code of Record for the containment tendon surveillance program for the expedited examination and during the intial (first) 120-month interval of its CISI program is the 1992 Edition and 1992 Addenda of the ASME Code,Section XI. This code edition and addenda are explicitly specified in the current TS 5.5.6 and TS 5.6.8.

The licensee stated that for Braidwood, the next successive (second) 1O-year CISI interval for Unit 1 and Unit 2 began on July 29,2008 and October 17, 2008, respectively. For Byron, the second 120-month CISI interval for Unit 1 and Unit 2 began on January 16, 2006. However, 10 CFR 50.55a(g)(4) requires that the CISI program for successive 120-month intervals must be updated to comply with the latest ASME Code edition and addenda incorporated by reference as specified in paragraph (g)(4)(ii). Therefore, the language of the existing TS 5.5.6 and TS 5.6.8, which makes specific reference to the 1992 Edition and 1992 addenda of the ASME Code, is not consistent with the requirement in 10 CFR 50.55a(g)(4) for successive 120-month intervals.

By this LAR, the licensee is proposing an administrative change to update TS 5.5.6 and TS 5.6.8 related to the containment tendon surveillance program to remove the reference to the specific ASME Code edition and addenda and to be consistent with 10 CFR 50.55a(g)(4) with regard to the code edition and addenda for successive 120-month intervals of the CISI program.

Additionally, the licensee stated that, because the tendon inspection frequencies will be in accordance with the ASME Code, Subsection IWL, the provisions of SR 3.0.2, with regard to extending the surveillance frequency, are not applicable and are deleted from TS 5.5.6. The licensee stated that, as discussed in the TS Bases for SR 3.0.2, the regulations take precedence over the TS. Therefore, 10 CFR 50.55a requires the implementation of the ASME Code, Subsection IWL, which specifies the requirements for extending inspection frequencies.

The licensee stated that "The proposed change adopts wording that is identical to NUREG-1431

["Standard Technical Specifications Westinghouse Plants," Revision 3.1] ... for the containment tendon surveillance program."

During its review of the licensee's April 9,2008, submittal, the NRC staff identified areas where additional information was needed to complete its review. The I\lRC staff made its request for additional information (RAI) by letter dated September 9, 2008 (ADAMS Accession No. ML082460568). By letter dated October 1, 2008, the licensee provided responses to the NRC staff's RAls, which are discussed below.

In RAI 1, the NRC staff noted an inconsistency in the April 9, 2008, submittal when comparing the wording used in the second sentence of revised TS Bases Section SR 3.6.1.2 and the wording in revised TS 5.5.6. Revised TS Bases Section SR 3.6.1.2 stated that "Testing and Frequency are consistent with the requirements of 10 CFR50.55a, "Codes and standards" (Ref. 4)." Revised TS Section 5.5.6 stated that "The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC."

Because the licensee stated that the wording of its TS for the tendon surveillance program was identical to NUREG-1431 , the NRC staff also noted another inconsistency when comparing the wording used in the second sentence of revised TS Bases Section SR 3.6.1.2 and in Bases Section SR 3.6.1.2 of NUREG-1431. Bases Section SR 3.6.1.2 of NUREG-1431 states that "Testing and Frequency are in accordance with the ASME Code,Section XI, Subsection IWL

-5 (Ref. X), and applicable addenda as required by 10 CFR 50.55a." The NRC staff requested the licensee to resolve these inconsistencies.

In its October 1, 2008, response to RAI 1, the licensee stated that, to be consistent, the proposed wording describing acceptance criteria for testing and frequency are changed to "The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC," for both the second sentence of revised TS Bases Section SR 3.6.1 .2 and TS 5.5.6. The licensee provided revised markup TS Bases to reflect this change as Attachments 4 (for Braidwood) and Attachment 5 (for Byron) of its October 1, 2008, response.

In its response to RAI 1, the NRC staff finds that the licensee has revised the language of TS Bases Section SR 3.6.1.2 to be consistent with the language in revised TS 5.5.6 as well as Bases Section SR 3.6.1.2 of NUREG-1431, Revision 3.1. The NRC staff finds the response acceptable because the inconsistencies are resolved.

In RAI 2, the NRC staff noted that in the April 9,2008, submittal, the reference to Regulatory Guide (RG) 1.35.1, "Determining Prestressing Forces For Inspection Of Prestressed Concrete Containments," July 1990 edition, had been removed from revised TS 5.5.6 and the revised TS Bases Section SR 3.6.1.2. The NRC staff noted that the last sentence of Bases Section SR 3.6.1.2 was revised to read: "Predicted tendon lift off forces will be determined in accordance with the ASME Code,Section XI, Subsection IWL (Ref. 5), and applicable addenda as required by 10 CFR 50.55a." The NRC staff pointed out that the ASME Code,Section XI, Subsection IWL does not provide guidance with regard to the determination of predicted tendon forces. The NRC staff requested the licensee to resolve this inconsistency and to also provide information regarding the method that will be used for determining the predicted prestressing tendon forces for the tendon surveillance programs at Braidwood and Byron.

In its October 1, 2008, response to RAI 2, the licensee stated that predicted tendon lift off forces have been and will continue to be determined in accordance with RG 1.35.1. The licensee fu rther stated that reference to RG 1.35.1 will be retained in TS 5.5.6 and in the References for Bases Section 3.6.1. The license stated that the calculation for determining prestressing tendon forces utilizes the following inputs when determining prestressed losses: "Initial Seating Force and [D]ate, Tendon Properties, Tendon Length, Elastic Shortening Losses, Minimum Design Stresses, Concrete Properties, Initial Stressing Date, Shrinkage Creep and Losses, Creep Function, Predicted Prestressed Losses, and Upper Bound Stresses." The licensee included revised markups of TS and Bases pages, which retained the reference to RG 1.35.1 in TS 5.5.6 and associated Bases section.

The NRC staff finds the response to RAI 2 acceptable because RG 1.35.1 is appropriate guidance for determining predicted tendon forces and because the licensee provided appropriately-revised TS pages (for the amendments) and Bases pages (for information) as attachments to its October 1, 2008, response.

In the proposed amendments to TS 5.5.6, the licensee has removed the reference to the specific code edition and addenda (1992 edition and 1992 addenda) of the ASME Code,

-6 Subsection IWL for its tendon surveillance program. The TS wording ensures that the code edition and addenda for each successive 120-month inspection interval will be updated in accordance with 10 CFR 50.55a and, specifically, 10 CFR 50.55a(g)(4)(ii). In TS 5.5.6, the licensee has also deleted the reference to SR 3.0.2, which is the TS provision that relates to extending surveillance frequencies. Because the tendon inspection frequencies and the requirements for extending inspection frequencies will be in accordance with ASME Code,Section XI, Subsection IWL, the provisions of SR 3.0.2 are no longer necessary. Therefore, it is acceptable to delete the reference to SR 3.0.2 in the tendon surveillance program. Thus, the NRC staff finds that the proposed change to TS 5.5.6 is consistent with the regulations in 10 CFR 50.55a(g)(4) for Class CC components and is, therefore, acceptable.

Consistent with the change to TS 5.5.6, the proposed amendments also deleted the reference to the specific code edition and addenda (1992 Edition and 1992 Addenda) of the ASME Code, Subsection IWL in TS Section 5.6.8, "Tendon Surveillance Report." Reporting requirements for abnormal degradation findings from the tendon surveillance program are contained in articles IWA-6000 and IWL-3300 of the ASME Code,Section XI. The amended wording of TS 5.6.8 ensures that abnormal degradation conditions of the containment found during inspection requirements of the tendon surveillance program will be reported in accordance with the requirements of 10 CFR 50.55a and the appropriate edition of the ASME Code,Section XI.

Therefore, the NRC staff also finds the proposed change to TS 5.6.8 acceptable.

The NRC staff also reviewed the licensee's identified changes to the TS Bases that were included in the application dated April 9, 2008, as supplemented by letter dated October 1, 2008, and finds that they are consistent with the proposed changes to the TSs. Based on the above findings and the consistency of the proposed amendments to Section XI of the ASME Code and to 10 CFR 50.55a(g)(4), the NRC staff concludes that the proposed amendments are acceptable.

5.0 STATE CONSULTATION

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

6.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to installation or use of a facility's components located within the restricted area, as defined in 10 CFR Part 20, or changes SRs.

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 (73 FR 37504; July 1, 2008). 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.

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7.0 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 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: G. Thomas, NRR Date: M:lrch 26, 2009

ML 0610133 *SE Memo Dated OFFICE LPL3-2/PM LPL3-2/LA DE/EMCB/BC OGC NAME MDavid M EWhitt' KManoly*

DATE ~ I 109 109 12/24/08