L-2018-039, License Renewal Application - Supplement 1

License Renewal Application - Supplement 1

ML18044A653
Person / Time
Site:	Turkey Point
Issue date:	02/09/2018
From:	Maher W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML180446A644	List: L-2018-039, License Renewal Application - Supplement 1
References
L-2018-039
Download: ML18044A653 (13)

Text

Attachment 2 contains information requested to be withheld from public disclosure under 10 CFR 2.390 when separated this page is decontrolled

• l=PL.

February 9, 2018 L-2018-039 10 CFR 54.17 10 CFR 2.390 U.S. Nuclear Regulatory Commission Attn : Document Control Desk Washington , D.C. 20555-0001 Re : Florida Power & Light Company Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Turkey Point Units 3 and 4 Subsequent License Renewal Application - Supplement 1 Reference :

1. FPL Letter L-2018-004 to NRC dated January 30, 2018 , Turkey Point Units 3 and 4 Subsequent License Renewal Application Florida Power & Light Company (FPL) submitted a subsequent license renewal application (SLRA) for Turkey Point Units 3 and 4 to NRC on January 30, 2018 (Reference 1). Following discussions with NRC staff concerning apparent discrepancies between the affidavits and the associated proprietary enclosures, FPL performed an additional review of the affidavits and enclosures and identified discrepancies involving some of the reference documents.

Attachment 1 to this letter includes a marked -up copy of the affected non-proprietary pages with corrections .

Attachment 2 to this letter includes a marked -up copy of the affected proprietary pages with corrections .

In addition , based on discussions with EPRI , the original version of SLRA Enclosure 2, Attachment 4 (the EPRI Affidavit) is compliant with 10 CFR 2.390 because the letter provides a unique identifier for the withheld report referenced in the EPRI Affidavit.

FPL has reviewed these changes to the SLRA and determined that they do not have a material impact on the reference evaluations.

FPL will provide a revised submittal which will include a complete version of each of the affected SLRA Enclosures identified in this letter prior to the end of the NRC acceptance review period .

FPL requests Attach ment 2 of this letter to be withheld from public disclosure under 10 CFR 2.390. The affected page markups are excerpts from the proprietary vendor reports included with the FPL SLRA and are covered by affidavits included with the January 30, 2018 SLRA submittal (Reference 1) Enclosure 2 Affidavits , as amended by this submittal.

Florid a Powe r & Light Compa ny 700 Universe Bou levard , Juno Beach, FL 33408 contains information requested to be withheld from public disclosure under 10 CFR 2.390 when separated this page is decontrolled Turkey Point Units 3 and 4 Docket Nos . 50-250 and 50-251 L-2018-039 Page 2 If you have any questions, or need additional information, please contact William Maher, Senior Licensing Director, at 561-691-2294.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on February 9, 2018.

Sincerely, William D. Maher Senior Licensing Director Florida Power & Light Company Attachments :

1. Non-proprietary Affected Pages, FPL Letter L-2018-004 dated 01 2018

2. Proprietary Affected Pages, FPL Letter L-2018-004 dated 01 2018 Withhold under 10 CFR 2.390 WDM/GRM cc: w/o Attachment 2 Regional Administrator, USNRC, Region II Project Manager, USNRC , Turkey Point Nuclear Plant Project Manager, USNRC, SLRA Senior Resident Inspector, USNRC , Turkey Point Nuclear Plant Project Manager, USNRC , SLRA Environment Ms. Cindy Becker, Florida Department of Health contains information requested to be withheld from public disclosure under 10 CFR 2.390 when separated this page is decontrolled Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page t of 15 Non-proprietary Affected Pages FPL Letter L-2018-004 dated 01-30-2018 1 Encl. 1, Listing for Enclosure 4 Item k., Title of Attachment 11 - (1 Page) 2 Encl. 2, Att. 4 , Cover Page - (1 Page) 3 Encl. 2, Att. 6, Framatome (nee , AREVA) Replacement Affidavit - (4 Pages) 4 Encl. 3, SLRA Section 4, Reference 4 .7. 7.6 - (1 Page) 5 Encl. 4 , Att. 4, SIA Report No.1700109.402P.R3 - REDACTED, Reference 26 - (1 Page)

Encl. 4 , Att. 5, SIA Report No. 1700109.401 P.R3 - REDACTED , References 22 , 32 , 33, 6

35, 36, 37 , 38, 39 , & 40 - (2 Pages)

Encl. 4, Att. 6, SIA Calculation No. 1700804-313P - REDACTED , Revision 1 References 7

5 & 9 - (1 Page)

Encl. 4, Att. 6, SIA Calculation No. 1700804-315P - REDACTED , Revision 1, Reference 8

10 - (1 Page) 9 Encl. 4, Att., 11 , Cove r Page - (1 Page) 10 Encl. 5, Att. 1, SLRA Section 4, Reference 4.7.7.6 - (1 Page)

Turkey Point Units 3 and 4 Docket Nos. 50-2 50 and 50-251 L-201 8-039 Attachment 1 Pag e 2 of 15 Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-004 Enclosure 1

f. Attachment 6 - SIA Environmentally Assisted Fatigue Calculations

i. Pressurizer Lower Head - 1700804.316P Revision O REDACTED, 1700804.317 Revision 0, and 1700804.318 Revision 0, ii. Pressurizer Spray - 1700804.313P Revision 1 REDACTED, 1700804.314P Revision 1 REDACTED, and 1700804.315P Revision 1 REDACTED

g. Attachment 7 - Westinghouse Environmentally Assisted Fatigue Calculations

i. LTR-SDA-11-17-13-NP, Rev. 2, Pressurizer Upper Head , RV Core Support Blocks ii. LTR-CEC0-17-025-NP, Rev. 1, Replacement Steam Generators

h. Attachment 8 - Areva Environmentally Assisted Fatigue Calculations:

Areva Letter No. AREVA-17-02742 , dated December 6, 2017, Final CUFEN Results - Turkey Point 3 & 4 - SLR EAF Analyses

i. 32-9280707, Rev. 0, CROM Nozzle to Adapter Weld Connection ii. 32-9280708 , Rev. 0, Replacement RVCH J Groove iii. 32-9280709, Rev. 0, CROM Latch Housing iv. 32-9280710, Rev. 0, Vent Nozzle

v. 32-9280711 , Rev. 0, Reactor Vessel Flange vi. 32-9280712 , Rev. 0, CROM Lower Joint

i. Attachment 9 - PWROG-17031-NP, Rev. O - Update for Subsequent License Renewal : WCAP-15338-A

j. Attachment 10 - PWROG-17011-NP, Rev. 0- Update for Subsequent License Renewal : WCAP-14535A and WCAP-15666-A

k. Attachment 11 - WCAP-15354-NP, Rev. 1, Technical Justification for Eliminating Primary Loop Pipe Rupture as a the Structural Design Basis I. Attachment 12 - SIA Leak-Before-Break Evaluation for Auxiliary Lines 0901350-401 Rev. 3 and 0901350-304 Rev. 3

m. Attachment 13 - PWROG-17033-NP, Rev. 0, Update for Subsequent License Renewal : WCAP-13045 Enclosure 5 - 10 CFR 2.390 Withheld Proprietary Documents

a. Attachment 1 - Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application (Proprietary Version)

b. Attachment 2 -Areva Topical Report ANP-3646P Revision 0

c. Attachment 3 - Areva Topical Report ANP-3647P Revision O

d. Attachment 4 - SIA Task 1 Report - SIA Report No. 1700109.402P Revision 3

e. Attachment 5 - SIA Task 2 Report- SIA Report No. 1700109.401 P Revision 3

f. Attachment 6 - SIA EAF Calculations

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page 3 of 15 Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-004 Enclosure 2 Attachment 4 Page 1 of 3 Applications for Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)

Attachment 4:

Affidavit for withholding for EPRI letter dated December 14, 2017, Affidavit for MRP 2017-038 (Enclosure 5 Attachment 1- SLRA Appendix C & Attachment 11)

1. Materials Reliability Program Letter MRP 2017-038 to MRP members, entitled ,

Transmittal of Preliminary Results from MRP-191 Expert Panel Review in Support of Subsequent License Renewal at U.S. PWR Plants.

This is a request under 10 C.F.R. §2.390(a)(4) that the U.S. Nuclear Regulatory Commission (NRC) withhold from public disclosure the information identified in the enclosed Affidavit consisting of the commercial information owned by Electric Power Research Institute, Inc. (EPRI) identified above (the "Report") . Copies of the Report and the Affidavit in support of this request are enclosed.

EPRI desires to disclose these preliminary results in confidence to supplement previously submitted information as requested by the NRC in a letter dated 9/6/2017

[Ref. ML17220A008]. The preliminary results reported herein are not to be divulged to anyone outside of the NRC nor shall any copies be made of the information provided herein. EPRI welcomes any discussions and/or questions relating to the information enclosed.

If you have any questions about the legal aspects of this request for withholding, please do not hesitate to contact Steven Swilley at (704) 595-2630. Questions on the content of the Report should be directed to Kyle Amberge of EPRI at (704) 595-2039.

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page 4 of 15 Turkey Poi nt Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-004 Enclosure 2 Attachment 6 Page 1 of 4 Enclosure 2 Applications for Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390(a)(4)

Attachment 6:

Affidavit dated December 15, 2017 February 8, 2018 for withholding for Areva CUFs in SLRA tables (Enclosure 5 Attachment 1- SLRA Section 4, Attachment 4 & Attachment 5)

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page 5 of 15 AFFIDAVIT COMMONWEALTH OF VIRGINIA 55.

CITY OF LYNCHBURG

1. My name is Gayle Elliott. I am Deputy Director, Licensing & Regulatory Affairs, for Framatome Inc. (Framatome) and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.

3. I am familiar with the Framatome information contained in Table 4.3-1 , "PTN Unit 3 and Unit 4 60-Year Fatigue Cumulative Usage Factors for Reactor Coolant System Components," Table 4.3.3-2, "80-Year Environmentally Assisted Fatigue CUFs," and pages 4.3-

. I 22 and 4.3-23 of Section 4, "Time-Limited Aging Analyses ," of Turkey Point Units 3 and 4 Subsequent License Renewal Application and referred to herein as "Document. " Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confiden ce with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page 6 of 15 requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."

6. The following criteria are customarily applied by Framatome to determine whether information shou ld be classified as proprietary:

(a) The information reveals details of Framatome's research and development plans and programs or their results .

(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a sim ilar product or service.

(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.

(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.

(e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.

The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(d) and 6(e) above.

7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside Framatome on ly as required and under suitable agreement providing for nondisclosure and limited use of the information .

8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page 7 of 15

9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.

<1-/A SUBSCRIBED before me this --'Q_...___ __

day of £e,hrt,tqr) , 2018.

Ella Carr-Payne NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2 01 8-039 Attach ment 1 Page 8 of 15 Section 4 - Time-Limited Aging Analyses 4.7.7 .5 WCAP-15354, "Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Turkey Point Units 3 and 4 Nuclear Power Plant For the 60 Year Plant Life (License Renewal Program) ," Revision 0, January 2000 .

4.7.7.6 WCAP-15354-P/NP, "Technical Justification for Eliminating Primary Loop Pipe Rupture as a the Structural Design Basis for Turkey Point Units 3 and 4 Nuclear Power Plants for the Subsequent License Renewal Time-Limited Aging Analysis Program (80 Years) Leak-Before-Break Evaluation ," Revision 1, ~ eptem berAugust 2017 (Enclosure 4, Attachment 11 ).

4.7.7.7 NUREG/CR-4513, "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems, " Revision 2, U.S. Nuclear Regulatory Commission ,

Washi ngton, DC , May 2016 .

4.7.7 .8 Structu ral Integrity Associates Engineering Report No. 0901350.401, Revision 3, "Leak-Before-Break Evaluation - Accumulator, Pressurizer Surge, and Residual Heat Removal Lines, Turkey Point Units 3 and 4," September 2017 (Enclosure 4, Attachment 12).

4.7 .7.9 NUREG-1061 , Volumes 1-5, "Report of the U.S. Nuclear Regulatory Commission Piping Review Committee," prepared by the Piping Review Committee, NRC, April 1985.

4.7.7.10 NUREG-0800, "U.S. Nuclear Regulatory Commission Standard Revision Plan, Office of Nuclear Reactor Regulation , Section 3 ..6.3, Leak-Before-Break Evaluation Procedure,"

August 1987.

4.7 .7 .11 ASME Boiler and Pressure Vessel Code, Section XI, 2001 Edition with Addenda through 2003.

4.7.7.12 WCAP-13045 , Compliance toASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems.

4.7 .7 .13 WCAP-15355, A Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings of the Turkey Point Units 3 and 4.

4.7.7 .14 PWROG-17033-P/NP, Revision 0, Update for Subsequent License Renewal :

WCAP-13045, "Compliance to ASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems", October 2017 (Enclosu re 4, Attachment 13).

4.7.7. 15 Specification E.O.C.1.-61, Electric Overhead Crane Institute, Inc. , 1961 .

4.7 .7.16 AISC , Manual of Steel Construction, 6th Edition.

4.7.7.17 Specificati on CMAA-70, Crane Manufacturers Association of America , Inc. , 1994.

Turkey Point Nuclear Plant Units 3 and 4 Page 4.7-11 Subsequent License Renewal Application

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page 14 of 15 Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-004 Enclosure 4 Attachment 11 Enclosure 4 Non-proprietary Reference Documents and Redacted Versions of Proprietary Reference Documents (Public Version)

Attachment 11 WCAP-15354-NP, Revision 1 Technical Justification for Eliminating Primary Loop Pipe Rupture as a the Structural Design Basis for Turkey Point Units 3 and 4 Nuclear Power Plants for the Subsequent License Renewal Time-Limited Aging Analysis Program (80 Years) Leak-Before-Break Evaluation, August 2017 (59 Total Pages, including cover sheets)

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 1 Page 15 of 15 Section 4 - Time-Limited Aging Analyses 4.7.7 .5 WCAP-15354 , "Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Turkey Point Units 3 and 4 Nuclear Power Plant For th e 60 Year Plant Life (License Renewal Program) ," Revision 0, January 2000 .

4.7.7 .6 WCAP-15354-P/NP, "Technical Justification for Eliminating Primary Loop Pipe Rupture as a the Structural Design Basis for Turkey Point Units 3 and 4 Nuclear Power Plants for the Subsequent License Renewal Time-Limited Aging Analysis Program (80 Years) Leak-Before-Break Evaluation ," Revision 1, SeptemberAugust 2017 (Enclosure 5, Attachment 9).

4.7.7 .7 NUREG/CR-4513 , "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems," Revision 2, U.S. Nuclear Regulatory Commission, Washington , DC , May 2016 .

4.7.7.8 Structural Integrity Associates Engineering Report No. 0901350.401 , Revision 3, "Leak-Before-Break Evaluation -Accumulator, Pressurizer Surge, and Residual Heat Removal Lines, Turkey Point Units 3 and 4," September 2017 (Enclosure 4, Attachment 12).

4.7. 7.9 NUREG-1061 , Volumes 1-5, "Report of the U. S. Nuclear Regulatory Commission Piping Review Committee ," prepared by the Piping Review Committee , NRC , April 1985.

4.7.7.10 NUREG-0800, "U.S. Nuclear Regulatory Commission Standard Revision Plan , Office of Nuclea r Reactor Regulation , Section 3.6.3, Leak-Before-Break Evaluation Procedure ,"

August 1987.

4.7.7.11 ASME Boiler and Pressure Vessel Code , Section XI , 2001 Ed ition with Addenda through 2003 .

4.7.7.12 WCAP-13045, Compliance to ASME Code Case N-481 of the Primary Loop Pump Casing s of Westinghouse Type Nuclear Steam Supply Systems .

4.7.7.13 WCAP-15355 , A Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings of the Turkey Point Units 3 and 4.

4.7.7.14 PWROG-17033-P/NP, Revision 0, Update for Subsequent License Renewal :

WCAP-13045 , "Compliance to ASME Code Case N-481 of the Primary Loop Pump Casings of Westinghouse Type Nuclear Steam Supply Systems", October 2017 (Enclosure 5, Attachment 10).

4.7.7.15 Specification E.O.C .1.-61 , Electric Overhead Crane Institute, Inc., 1961 .

4.7.7.16 AISC , Manual of Steel Construction , 6th Edition .

4.7.7.17 Specification CMAA -70 , Crane Manufacturers Association of America , Inc., 1994.

Tu rkey Point Nuclear Plant Units 3 and 4 Page 4.7-11 Subsequent License Renewal Application

Attachment 2 contains information requested to be withheld from public disclosure under 10 CFR 2.390 when separated this page is decontrolled Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 L-2018-039 Attachment 2 Page 1 of 16 Proprietary Affected Pages FPL Letter L-2018-004 dated 01-30-2018 1 Encl . 5, Proprietary Document List - (1 Page) 2 Encl. 5, Att. 4, SIA Report No.1700109.402P.R3 , Reference 26 - (1 Page)

Encl. 5 Att. 5, SIA Report No. 1700109.401 P.R3 , References 22 , 32, 33, 35, 36 , 37 , 38 , 39, 3

& 40 - (2 Pages) 4 Encl. 5, Att. 6, SIA Calculation No . 1700804-313P, Revision 1 References 5 & 9 - (1 Page) 5 Encl. 5, Att. 6, SIA Calculation No. 1700804-315P, Revision 1, Reference 10- (1 Page) 6 Encl. 5, Att. 9, Cover Page - (1 Page)

Encl. 5, Att. 11 , EPRI Letter No. MRP 2017-038 dated 12-15-2017, Added 10 CFR 2.390 7

Withholding header & footer - (8 Pages)