ML11293A367

Additional License Conditions Pages - Issuance of Amendments Regarding Extended Power Uprate

ML11293A367
Person / Time
Site:	Turkey Point
Issue date:	06/18/2012
From:	Leeds E Office of Nuclear Reactor Regulation
To:	Nazar M Florida Power & Light Co
Paige, J C
Shared Package
ML11293A359	List: ML11293A365 ML11293A367 ML11293A368
References
TAC ME4907, TAC ME4908
Download: ML11293A367 (14)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT PLANT. UNIT NO.3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 249 Renewed License No. DPR-31

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

A. The application for amendment by Florida Power and Light Company (the licensee) dated October 21 and December 14,2010, as supplemented by letters dated December 21, 2010, January 7, 2011, January 28, February 22, March 3, March 9 (two letters), March 16 (two letters), March 23, March 25, March 31 (two letters),

April 14 (two letters), April 22 (2 letters), April 26, April 28 (2 letters), April 29, May 11, May 18, May 19 (two letters), May 26 (two letters), June 7, June 9, June 21 (two letters), July 7 (two letters), July 22, July 29, August 5, August 11, August 16 (two letters), August 19, August 25 (two letters), August 29, September 14, September 16, September 30 (two letters), October 6, October 12 (two letters), October 14, October 15, November 9, December 22 (2 letters),

December31, 2011, January 10, 2012, January 16 (two letters), January 17, January 19, January 23 (two letters), January 25, January 31, February 3, February 15, February 23 (two letters), and March 15, 2012, 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.

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2. Accordingly, the license is amended by changes to the Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.A and 3.B of Renewed Facility Operating License No. DPR-31 is hereby amended to read as follows:

A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 249 are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed 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 its date of issuance and shall be implemented prior to Unit 3 startup from the spring 2012 refueling outage.

TORY COMMISSION Eric J. Le (js, Director Office of uclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: June 15, 2012

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT PLANT UNIT NO.4 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 245 Renewed License No. DPR-41

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

A. The application for amendment by Florida Power and Light Company (the licensee) dated October 21 and December 14, 2010, as supplemented by letters dated December 21,2010, January 7,2011, January 28, February 22, March 3, March 9 (two letters), March 16 (two letters), March 23, March 25, March 31 (two letters),

April 14 (two letters), April 22 (2 letters), April 26, April 28 (2 letters), April 29, May 11, May 18, May 19 (two letters), May 26 (two letters), June 7, June 9, June 21 (two letters), July 7 (two letters), July 22, July 29, August 5, August 11, August 16 (two letters), August 19, August 25 (two letters), August 29, September 14, September 16, September 30 (two letters), October 6, October 12 (two letters), October 14, October 15, November 9, December 22 (2 letters),

December 31, 2011, January 10, 2012, January 16 (two letters), January 17, January 19, January 23 (two letters), January 25, January 31, February 3, February 15, February 23 (two letters), and March 15, 2012, 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.

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2. Accordingly, the license is amended by changes to the Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.A and 3.B of Renewed Facility Operating License No. DPR-41 is hereby amended to read as follows:

A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B. Technical Specifications The Technical SpF:'cifications contained in Appendix A, as revised through Amendment No. 245 are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed 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 its date of issuance and shall be implemented prior to Unit 4 startup from the fall 2012 refueling outage.

Eric J. L ds, Director Office 0 Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: June 15, 2012

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 249 RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 245 RENEWED FACILITY OPERATING LICENSE NO. DPR-41 DOCKET NOS. 50-250 AND 50-251 Replace Pages 1, 3, 6, & 7 of Renewed Operating License DPR-31 with the attached Pages 1, 3, 6, and 7.

Replace Pages 1, 3, 6, & 7 of Renewed Operating License DPR-41 with the attached Pages 1, 3, 6, 7, and new page 8.

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove pages Insert pages Remove pages Insert pages Remove pages Insert pages x x 3/4 3-8 3/4 3-8 3/4 7-2 3/4 7-2 xiv xiv 3/4 3-9 3/4 3-9 3/4 7-11 3/4 7-11 1-5 1-5 3/4 3-11 3/4 3-11 -------- 3/4 7-11b 2-2* 2-2 3/4 3-14 3/4 3-14 3/4 8-5 3/4 8-5 2-4 2-4 3/4 3-18 3/4 3-18 3/4 8-6 3/4 8-6 2-5 2-5 3/4 3-23 3/4 3-23 3/4 8-7 3/4 8-7 2-6 2-6 3/4 3-24 3/4 3-24 3/4 8-8 3/4 8-8 2-7 2-7 3/4 3-26 3/4 3-26 3/4 8-9 3/4 8-9 2-8 2-8 3/4 3-27 3/4 3-27 3/4 9-1 3/4 9-1 2-9 2-9 3/4 3-28 3/4 3-28 3/4 9-15 3/4 9-15 2-10 2-10 3/4 3-29 3/4 3-29 5-5 5-5 3/4 1-3* 3/4 1-3 3/4 3-31 3/4 3-31 5-17 5-17 3/4 1-4* 3/4 1-4 3/4 3-31a 3/4 3-31a 5-18 5-18 3/4 1-5* 3/4 1-5 3/4 3-33 3/4 3-33 6-17 6-17 3/4 1-6* 3/4 1-6 3/4 3-34 3/4 3-34 6-22 6-22 3/4 1-8 3/4 1-8 ------- 3/4 3-34a 3/4 1-9 3/4 1-9 3/4 3-37 3/4 3-37 3/4 1-10 3/4 1-10 3/4 4-7 3/4 4-7 3/4 1-11 3/4 1-11 3/4 4-8 3/4 4-8 3/4 1-12 3/4 1-12 3/4 4-18 3/4 4-18 3/4 1-14 3/4 1-14 3/4 4-31 3/4 4-31 3/4 1-14a 3/4 1-14a 3/4 4-32 3/4 4-32 3/4 1-15 3/4 1-15 3/4 4-36 3/4 4-36 3/4 2-16 3/4 2-16 3/4 5-2 3/4 5-2 3/4 3-3 3/4 3-3 3/4 5-10 3/4 5-10 3/4 3-4 3/4 3-4 3/4 6-6 3/4 6-6

• By Letter dated March 15, 2012, FPL identified those COLR TS pages issued in Amendment Nos. 247 and 243 that supersede the EPU application TS pages.

FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO.3 RENEWED FACILITY OPERATING LICENSE NO. DPR-31 The U.S. Nuclear Regulatory Commission (the Commission) having previously made the findings set forth in License No. DPR-31 issued on July 19, 1972, has now found that:

a. The application to renew license No. DPR-31 filed by Florida Power and Light Company, 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 and all required notifications to other agencies or bodies have been duly made;

b. Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21{a)(1), and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21 (c), such that there is reasonable assurance that the activities authorized by this renewed license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for the Turkey Point Unit 3 plant, and that any changes made to the plant's current licensing basis in order to comply with 10 CFR 54.29{a) are in accord with the Act and the Commission's regulations;

c. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission;

d. There is reasonable assurance (i) that the facility can be operated at steady state power levels up to 2644 megawatts thermal in accordance with this renewed operating license without endangering the health and safety of the public, and (n) that such activities will be conducted in compliance with the rules and regulations of the Commission;

e. Florida Power and Light Company is technically and financially qualified to engage in the activities authorized by this renewed operating license in accordance with the rules and regulations of the Commission; Renewed License No. DPR-31 Amendment No. 249

3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.

3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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 below; A. Maximum Power level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.249are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

C. Final Safety Anal'(§is Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.

The licensee shall complete these activities no later than July 19, 2012.

The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71 (e)(4) , following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed license No. DPR-31 I Amendment No. 249

6

3. The CREVS compensatory filtration unit, which is being installed by FPL as part of the AST methodology implementation at Turkey Point. will be designed in accordance with the Class I Structures, Systems, and Equipment Design Requirements defined in Appendix 5A of the Turkey Point UFSAR. As such, the compensatory filtration unit will be designed so that the stress limits found in Table 5A-1 of the Turkey Point UFSAR will not be exceeded due to the loadings imposed by a maximum hypothetical earthquake. FPL shall ensure that the design of the compensatory filtration unit satisfies these stress limits prior to the implementation of the proposed AST methodology at Turkey Point.

I. Control Room Habitability Upon implementation of Amendment No. 248 adopting TSTF-448 Revision 3, the detennination of control room envelope (CRE) unfiltered air inleakage as required by Surveillance Requirement (SR) 4.7.5.g, in accordance with Technical Specification (TS) 6.8.4.k.c.(i), the assessment of CRE habitability as required by Specification 6.8.4.k.c.(ii), and the measurement of CRE pressure as required by Specification 6.8.4.k.d, shall be considered met. Following implementation:

(a) The first performance of SR 4.7.5.g, in accordance with Specification 6.8.4.k.c.(i), shall be within the specified Frequency of 3 years, plus the 9 month allowance of SR 4.0.2, as measured from July 31, 2009, the date of the most recent tracer gas test. *

(b) The first performance of the periodic assessment of CRE habitability, SpeCification 6.8.4.k.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 4.0.2, as measured from July 31 ,2009, the date of the most recent tracer gas test.

(c) The first performance of the periodic measurement of CRE pressure, Specification 6.8.4.k.d, shall be within 36 months on a STAGGERED TEST BASIS, plus the 138 days allowed by SR 4.0.2, as measured from the date of the most recent successful pressure measurement test, or within 138 days of license amendment implementation if not performed previously.

• The most recent tracer gas test (July 31,2009) was unsuccessful in that there was a measured 9 cfm control room inleakage: the acceptance criteria is 0 cfm. In accordance with Regulatory Guide (RG) 1.197 Rev. 0, a recalculation ofthe consequences to the control room operators was peiformed, and the results were acceptable for continued CREVS operability. Consistent with RG 1.197, a full test is to be conducted three years later to ascertain whether the CRE's integrity has continued to degrade.

J. Extended Power Uprate Modifications

1. Prior to completion of the Cycle 26 refueling outage for Unit 3, the licensee shall provide confirmation to the NRC staff that the design and structural integrity evaluations associated with the modifications related to the spent fuel pool supplemental heat exchangers are complete, and that the results demonstrate compliance with appropriate UFSAR and code requirements.

As part of the confirmation, the licensee shall provide a summary of the structural qualification results of the piping, pipe supports, supplemental heat exchanger supports, and the inter-tie connection with the existing heat exchanger for the appropriate toad combinations along with the margins.

Renewed License No. DPR-31 Amendment No. 249

7 K. PAD TCD Safety Analyses

1. PAD 4.0 TCD has been specifically approved for use for the Turkey Point licensing basis analyses. Upon NRC's approval of a revised generic version of PAD that accounts for Thermal Conductivity Degradation (TCD), FPL will within six months:

a. Demonstrate that PAD 4.0 TCD remains conservatively bounding in licensing basis analyses when compared to the new generically approved version of PAD wrrCD, or

b. Provide a schedule for the re-analysis using the new generically approved version of PAD wrrCD for any of the affected licensing basis analyses.

L. Burnable Absorbers in Spent Fuel Pool

1. With respect to Technical Specification 5.5.1.3, FPL shall not credit any burnable absorber other than Integral Fuel Burnable Absorber (IFBA) rods for the storage of fuel assemblies in the Region I spent fuel racks.

4. This renewed license is effective as of the date of issuance, and shall expire at midnight July 19, 2032.

FOR THE NUCLEAR REGULATORY COMMISSION Signed by Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:

Appendix A - Technical Specifications for Unit 3 Appendix B - Environmental Protection Plan Date of Issuance: June 6, 2002 Renewed License No. DPR-31 Amendment No. 249

1 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO.4 RENEWED FACILITY OPERATING LICENSE NO. DPR-41 The U.S. Nuclear Regulatory Commission (the Commission) having previously made the findings set forth in License No. DPR-41 issued on April 10, 1973, has now found that:

a. The application to renew License N,o. DPR-41 filed by Florida Power and Light Company, 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' and all required notifications to other agencies or bodies have been duly made;

b. Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1), and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21 (c), such that there is reasonable assurance that the activities authorized by this renewed license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for the Turkey Point Unit 4 plant, and that any changes made to the plant's current licensing basis in order to comply with 10 CFR 54.29(a) are in accord with the Act and the Commission's regulations;

c. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission;

d. There is reasonable assurance (i) that the facility can be operated at steady state power levels up to 2644 megawatts thermal in accordance with this renewed operating license without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regUlations of the Commission;

e. Florida Power and Light Company is technically and financially qualified to engage in the activities authorized by this renewed operating license in accordance with the rules and regulations of the Commission; Renewed License No. DPR-41 Amendment No. 245

3 E. Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.

3. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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 below:

A. Maximum Power Level The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.245are hereby incorporated into this renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

C. Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d). as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.

The licensee shall complete these activities no later than April 10, 2013.

The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed License No. DPR-41 I Amendment No. 245

6 (d) FPL will not move any fuel assemblies into the Unit 4 SFP subsequent to the successful completion of startup physicS tests for Unit 4 Cycle 25.

J. Alternative Source Term Modifications

1. FPL will relocate the CR Ventilation System emergency air intakes prior to implementation of AST. The relocated intakes and associated ductwork will be designed to seismic criteria, protected from environmental effects, and will meet the requirements of 10 CFR 50 Appendix A, GDC 19. The new intakes will be located near the ground level extending out from the southeast and northeast comers of the auxiliary building and will fall within diverse wind sectors for post-accident contaminants. FPL will perform post-modification testing in accordance with the plant design modification procedures to ensure the TS pressurization flow remains adequate to demonstrate the integrity of the relocated intakes. In addition, FPL will provide to the NRC a confinnatory assessment which demonstrates that the requirements of 10 CFR 50 Appendix A. GDC 19 will be met. The confirmatory assessment will follow the methodology in Amendment 240 [the alternative source term amendment1 including the methods used for the establishment of the atmospheric dispersion factors (X/Q values).

2. FPL will install ten (two large and eight small) stainless steel wire mesh baskets containing NaTB located in the containment basement to maintain pH during the sump recirculation phase following a Design Basis LOCA

3. The CREVS compensatory filtration unit, which is being installed by FPL as part of the AST methodology Implementation at Turkey Point will be designed in accordance with the Class I Structures. Systems, and Equipment Design Requirements defined in Appendix SA of the Turkey Point UFSAR. As such, the compensatory filtration unit will be designed so that the stress limits found in Table SA-1 of the Turkey Point UFSAR will not be exceeded due to the loadings imposed by a maximum hypothetical earthquake. FPL shall ensure that the design of the compensatory filtration unit satisfies these stress limits prior to the implementation of the proposed AST methodology at Turkey Point.

J. Control Room Habitability Upon implementation of Amendment No. 244 adopting TSTF-448 Revision 3. the determination of control room envelope (CRE) unfiltered air inleakage as required by Surveillance Requirement (SR)4.7.5.g. in accordance with Technical Specification (TS) 6.8.4.k.c.(i). the assessment of CRE habitability as required by Specification 6.8.4.k.c.(ii), and the measurement of CRE pressure as required by Specification 6.8.4.k.d. shall be considered met. Following implementation:

(a) The first perfonnance of SR 4.7.5.g, in accordance with Specification 6.8.4.k.c.(i). shall be within the specified Frequency of 3 years, plus the 9-month Renewed License No, DPR-41 Amendment No. 245

7 allowance of SR 4.0.2. as measured from July 31. 2009, the date of the most recent tracer gas test.*

(b) The first performance of the periodic assessment of CRE habitability, Specification 6.8.4.k.c.(ii), shall be within 3 years, plus the 9-month allowance of SR 4.0.2, as measured from July 31.2009, the date of the most recent tracer gas test.

(c) The first performance of the periodic measurement of CRE pressure, Specification 6.B.4.k.d, shall be within 36 months on a STAGGERED TEST BASIS. plus the 138 days allowed by SR 4.0.2, as measured from the date of the most recent successful pressure measurement test, or within 138 days of Ucense amendment implementation if not performed previously.

• The most recent tracer gas test (July 31. 2009) was unsuccessful in that there was a measured 9 cfm control room inleakage: the acceptance criteria is 0 cfm. In accordance with Regulatory Guide (RG) 1.197 Rev. 0, a recalculation ofthe consequences to the control room operators was performed, and the results were acceptablefor continued CREVS operability. Consistent with RG IJ97. afull test is to be conducted three years later to ascertain whether the CRE's integrity has continued to degrade.

K. Extended Power Uprate Modifications

1. Prior to completion of the Cycle 27 refueling outage for Unit 4, the licensee shall provide confirmation to the NRC staff that the design and structural integrity evaluations associated with the modifications related to the spent fuel pool supplemental heat exchangers are complete. and that the results demonstrate compliance with appropriate UFSAR and code requirements.

As part of the confirmation, the licensee shalf provide a summary of the structural qualification results of the piping, pipe supports, supplemental heat exchanger supports, and the inter-tie connection with the existing heat exchanger for the appropriate load combinations along with the margins.

L. PAD TeD Safety Analyses

1. PAD 4.0 TCD has been specifically approved for use for the Turkey POint licensing basis analyses. Upon NRC's approval of a revised generic version of PAD that accounts for Thermal Conductivity Degradation (TCD). FPL will within six months:

a. Demonstrate that PAD 4.0 TCD remains conservatively bounding in licensing basis analyses when compared to the new generically approved version of PAD wfrCD, or

b. Provide a schedule for the re-analysis using the new generically approved version of PAD wfrCD for any of the affected licenSing basis analyses.

Renewed license No. DPR-41 Amendment No. 245

8 M. Burnable Absorbers in Spent Fuel Pool

1. With respect to Technical Specification 5.5.1.3, FPL shall not credit any burnable absorber other than Integral Fuel Burnable Absorber (IFBA) rods for the storage of fuel assemblies in the Region I spent fuel racks.

4. This renewed license is effective as of the date of issuance, and shall expire at midnight April 10, 2033.

FOR THE NUCLEAR REGULATORY COMMISSION Signed by Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:

Append ix A - Technical Specifications for Unit 4 Appendix B - Environmental Protection Plan Date of Issuance: June 6, 2002 Renewed License No. DPR-41 Amendment No. 245