ML18299A115

Environmentally Assisted Fatigue Evaluation of the Turkey Point Unit 3 and Unit 4 Pressurizer Upper Head and Shell and Reactor Vessel Core Support Blocks

ML18299A115
Person / Time
Site:	Turkey Point
Issue date:	09/14/2018
From:	Florida Power & Light Co, Westinghouse
To:	Office of Nuclear Reactor Regulation
References
L-2018-174, LTR-SDA-II-17-13-NP, Rev. 4
Download: ML18299A115 (4)

Text

WITHHELD FROM PUBLIC DISCLOSURE UNDER 10 CFR 2.390 Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 FPL Response to NRC RAI No. 4.3.3-3 L-2018-17 4 Attachment 14 Enclosure Page 1 of 4 Enclosure Westinghouse Letter, L TR-SDA-11-17-13-NP (Nonproprietary), "Environmentally Assisted Fatigue Evaluation of the Turkey Point Unit 3 and Unit 4 Pressurizer Upper Head and Shell and Reactor Vessel Core Support Blocks," Revision 4 final approved September 18, 2018 Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Withheld From Public Disclosure Under 1 O CFR 2.390 Westinghouse Non-Proprietary Class 3 @ Westinghouse L-2018-17 4 Attachment 14 Enclosure Page 2 of 4 1000 Westinghouse Drive Cranberry Twp., PA 16066 To: John Ahearn Date: September 14, 2018 From: Structural Design & Analysis II Ext: 412-374-4196 Fax: 724-940-8565 Our ref: LTR-SDA-II-17-13-NP, Rev. 4

Subject:

Environmentally Assisted Fatigue Evaluation of the Turkey Point Unit 3 and Unit 4 Pressurizer Upper Head and Shell and Reactor Vessel Core Support Blocks

References:

1. Westinghouse Letter, LTR-AMER-MKG-17-1375, Rev. 0, "Westinghouse Offer for Evaluation of Environmentally Assisted Fatigue at Turkey Point Units 3 & 4." 2. Westinghouse Calculation, CN-SDA-II-17-003, Rev. 1, "Turkey Point Units 3 and 4 Subsequent License Renewal Environmentally Assisted Fatigue Evaluation of Pressurizer Upper Head." (Westinghouse Proprietary Class 2) 3. Westinghouse Calculation, CN-SDA-17-5, Rev. 1, "Environmentally Assisted Fatigue Analysis of the Turkey Point Units 3 and 4 Reactor Vessel Core Support Blocks for Subsequent License Renewal." (Westinghouse Proprietary Class 2) 4. US Nuclear Regulatory Commission (NRC) Document, NUREG/CR-6909, Rev. 1, "Effect of LWR Water Environments on the Fatigue Life of Reactor Materials," May 2018. 5. Florida Power & Light Letter, NNPWEC-17-0227, Rev. 0, "Formal Transmittal oflnputs for Westinghouse Evaluation of Environmentally Assisted Fatigue at Turkey Point Units 3 & 4." 6. Electric Power Research Institute (EPRI) Document, "Pressurized Water Reactor Primary Water Chemistry Guidelines," Volume 1, Revision 7, EPRI, Palo Alto, CA: 2014.3002000505.

The purpose of this letter is to provide the results from the environmentally assisted fatigue (EAF) analysis performed for the Turkey Point Units 3 and 4 pressurizer (PZR) upper head and shell and the reactor vessel (RV) core support blocks in support of Subsequent License Renewal (SLR). This letter provides the deliverable outlined in Reference

1. Revision 1 of this letter updated Note 1 under Table 1 for clarity. Revision 2 of this letter was generated to identify data considered to be proprietary to Westinghouse consistent with the requirements of Westinghouse procedure BMS-LGL-84 for information to be transmitted to the NRC. A "Proprietary Class 2" and "Non-Proprietary Class 3" version of this document was generated in Revision 2 of this letter with the designator of "-P" and "-NP" added to This document may contain technical data subject to the export control laws of the United States. In the event that this document does contain such information, the Recipient's acceptance of this document constitutes agreement that this information in document form (or any other medium), including any attachments and exhibits hereto, shall not be exported, released or disclosed to foreign persons whether in the United States or abroad by recipient except in compliance with all U.S. export control regulations.

Recipient shall include this notice with any reproduced or excerpted portion of this document or any document derived from, based on, incorporating, using or relying on the information contained in this document.

© 2018 Westinghouse Electric Company LLC All Rights Reserved *** This record was final approved on 9/18/2018 12:02:18 PM. (This statement was added by the PRIME system upon its validation)

Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Withheld From Public Disclosure Under 1 O CFR 2.390 Westinghouse Non-Proprietary Class 3 Page 2 of3 L-2018-174 Attachment 14 Enclosure Page 3 of 4 Our ref: LlR-SDA-II-17-13-NP, Rev. 4 September 14, 2018 the letter number to designate proprietary and non-proprietary, respectively.

There was no change to the Revision 1 data as presented.

Revision 3 of this letter is generated to update References 2 through 4 to use the final version of NUREG-6909 Revision 1. The only significant change between the draft for comment and final versions of NUREG-6909 Revision 1 was to the transformed strain rate term in the Fen equation for stainless steel. Because there were no stainless steel locations evaluated in this work scope, there is no change to the Revision 2 results. Revision 3 changes are marked with a vertical bar in the left margin. Revision 4 of this letter is created to add the export control statement.

The revision.

bars from Revision 3 are maintained for Revision 4. Table 1 summarizes the cumulative usage factors (CUF) considering environmental effects (CUFen) from References 2 and 3 applicable for 80 years of operation.

CUFen was determined conservatively by applying the appropriate environmental fatigue correction factor (Fen) for the material calculated using the methods from Reference 4 considering the pressurized water reactor (PWR) environment.

Dissolved oxygen content was considered in the Fen calculation consistent with the guidelines for PWR primary water chemistry given in Reference

6. Projected .transient cycles for 80 years of operation were also transmitted in Reference

5. It was demonstrated that the current licensing basis transient cycles were bounding for the 80 year projected cycles for all transients.

Therefore, current licensing basis transient cycles were used for all fatigue pairings, except where noted in Table 1. Projected cycles were selectively applied to a limited extent to achieve a CUFen within the allowable, to maintain conservatism in the evaluation.

When projected cycles were applied, the larger number between units was used. Table 1: PZR Upper Head and Shell and RV Core Support Block EAF Results for SLR Equipment Component Material CUF Fen CUFen PZR Upper Head and Shell Low Alloy Steel [ r,c [ t*c 0_974(!) RV Core Support Blocks Low Alloy Steel [ t*c [ t*c 0.910<2) <1 JcUF 0 n was calculated by crediting 80 year projected cycles for station loading at 5% of full power/min and station unloading at 5% of full power/min.

<2 lcUF 0 n was calculated by crediting 80 year projected cycles for the hydrostatic test at 2485 psig pressure and 400°F temperature.

As shown in Table 1, the CUF en values for the PZR upper head and shell and RV core support blocks are below the allowable value of 1.0 for 80 years of operation and are therefore acceptable for SLR. *** This record was final approved on 9/18/2018 12:02:18 PM. (This statement was added by the PRIME system upon its validation)

_J Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Withheld From Public Disclosure Under 1 O CFR 2.390 Westinghouse Non-Proprietary Class 3 L-2018-174 Attachment 14 Enclosure Page 4 of 4 Page 3 of3 Our ref: LTR-SDA-II-17-13-NP, Rev. 4 September 14, 2018 If you have any questions, please contact the undersigned.

Author: Elliott L. Burdwood

• Structural Design & Analysis II Manager: Benjamin A. Leber* Structural Design & Analysis II Verifier:

Donald M. McNutt III* Structural Design & Analysis III *Electronically approved records are authenticated in the electronic document management system. *** This record was final approved on 9/18/2018 12:02:18 PM. (This statement was added by the PRIME system upon its validation)