ML18081A239

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Summary of Closed Pre-Application Telecon Held on November 6, 2017, Between the NRC and FPL to Discuss MRP-227, Reactor Vessel Internals, and Environmentally Assisted Fatigue Associated with the Turkey Point Subsequent License Renewal Appli
ML18081A239
Person / Time
Site: Turkey Point  
(DPR-031, DPR-041)
Issue date: 01/05/2018
From: Lois James
NRC/NRR/DMLR/MRPB
To:
Florida Power & Light Co
Lois M. James, 301-415-3306
References
L-2018-RNW-0002
Download: ML18081A239 (5)


Text

OFFICIAL USE ONLY - PROPRIETARY INFORMATION January 5, 2018 LICENSEE:

Florida Power & Light Company FACILITY:

Turkey Point Nuclear Generating Units 3 and 4

SUBJECT:

SUMMARY

OF CLOSED PRE-APPLICATION TELECONFERENCE HELD ON NOVEMBER 6, 2017, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND FLORIDA POWER & LIGHT COMPANY REPRESENTATIVES TO DISCUSS MRP-227, REACTOR VESSEL INTERNALS, NEUTRON FLUENCE CALCULATIONS AND ENVIRONMENTALLY ASSISTED FATIGUE ASSOCIATED WITH THE TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4, SUBSEQUENT LICENSE RENEWAL APPLICATION On November 6, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff met with representatives of Florida Power & Light Company in a closed teleconference to discuss the subsequent license renewal application for the Turkey Point Nuclear Generating Units 3 and 4, specifically MRP-227, reactor vessel internals, neutron fluence calculations and environmentally assisted fatigue. The proprietary meeting agenda can be found at the NRCs Agencywide Documents and Access Management System Accession No. ML17320A184, a list of attendees is provided in Enclosure 1, and a summary of the meeting is provided in Enclosure 2.

Sincerely,

/RA/

Lois M. James, Project Manager License Renewal Project Branch Division of Materials and License Renewal Office of Nuclear Reactor Regulation Docket Nos.: 50-250 and 50-251

Enclosures:

1.

Attendance List 2.

Meeting Summary cc w/encls: See next page OFFICIAL USE ONLY - PROPRIETARY INFORMATION FPL submitted the Subsequent License Renewal Application on January 30, 2018 (ADAMS Package Accession No. ML18037A812) therefore, it is no longer necessary to withhold as proprietary.

ML17360A239

  • Concurrence via email OFFICE PM:MRPB:DMLR LA:MRPB:DMLR BC:MVIB:DMLR BC:MRPB:DMLR NAME LJames*

YEdmonds SLent for SRuffin EOesterle DATE 01/02/2018 01/04/2018 01/04/2018 01/04/2018 OFFICE PM:MRPB:DMLR NAME LJames DATE 01/05/2018

OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION CLOSED TELECON BETWEEN THE NRC STAFF AND FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 SUBSEQUENT LICENSE RENEWAL APPLICATION - MRP-227, REACTOR VESSEL INTERNALS, NEUTRON FLUENCE CALCULATIONS AND ENVIRONMENTALLY ASSISTED FATIGUE TELECONFERENCE MEETING ATTENDANCE LIST NOVEMBER 6, 2017 PARTICIPANTS AFFILIATIONS David Alley U.S. Nuclear Regulatory Commission (NRC)

Joseph Donoghue NRC Carolyn Fairbanks NRC Allen Hiser NRC Lois James NRC Bob Lukes NRC James Medoff NRC Seung Min NRC Benjamin Parks NRC Jeffrey Poehler NRC Dave Rudland NRC Steve Ruffin NRC Christopher Sydnor NRC On Yee NRC Scott Boggs Florida Power & Light Co. (FPL)

Ray Burski FPL Steve Franzone FPL Paul Jacobs FPL Mark Joseph FPL William Maher FPL Jay Polavarapu FPL Dave Gerber SIA Stephen Hale Enercon J R Hoffman Enercon James V. Wicks Enercon

OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION CLOSED TELECON BETWEEN THE NRC STAFF AND FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 SUBSEQUENT LICENSE RENEWAL APPLICATION - MRP-227, REACTOR VESSEL INTERNALS, NEUTRON FLUENCE CALCULATIONS AND ENVIRONMENTALLY ASSISTED FATIGUE TELECONFERENCE

SUMMARY

NOVEMBER 6, 2017 On May 17, 2017, Florida Power & Light Company (FPL or the applicant) submitted a Notice of Intent (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML17142A036 (non-public, proprietary) and ML17139D442 (public, non-proprietary)) to submit a subsequent license renewal application (SLRA) for Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). This Notice of Intent was submitted as proprietary information. On May 25, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff issued its approval of FPLs request for withholding information from public disclosure (ADAMS Accession Nos. ML17096A477 (non-public, proprietary) and ML17139D441 (public, non-proprietary)).

On November 6, 2017, the NRC staff participated in a pre-application, closed teleconference with FPL to discuss the content of the Turkey Point SLRA, specifically MRP-227, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, reactor vessel internals (RVI), neutron fluence calculations and environmentally assisted fatigue (EAF). The proprietary meeting notice was issued on October 23, 2017 (ADAMS Accession No. ML17296A527).

The applicant began the discussion by explaining that the RVI aging management program (AMP) was developed in accordance with NRC guidance in NUREG-2191, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report, and NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants. Further, the applicant stated it performed a gap analysis for 60 - 80 years of operation. The main change since the September 6, 2017, meeting (proprietary summary can be found at ADAMS Accession No. ML17348B319) is that the applicant obtained industry generic 80-year neutron fluence data for RVIs. The applicant also indicated that the degradation mechanisms have not changed. Further, the applicant indicated that it did additional screening for fatigue and irradiation-assisted degradation and some additional components have screened in for these degradation mechanisms during the subsequent license renewal (SLR) aging management.

The NRC staff asked if FPL used the staff-approved revision of Material Reliability Program (MRP)-175, PWR Internals Material Aging Degradation Mechanism Screening and Threshold Values, or the revision that is under development. The applicant stated that it used the NRC staff-approved revision of MRP-175. The applicant stated that Revision 1 to MRP-175 had just been issued and was overly conservative for fatigue screening.

OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION The NRC staff pointed out that there is interim guidance regarding baffle bolts and guide cards.

The applicant stated (1) they have performed the required 20 percent sample inspections of the guide cards and have plans to perform 100 percent sample inspections in the future, and (2) they have met the current inspection baffle bolts guidance. The applicant explained that they have not included this guidance in their AMP because the guidance is in flux, however, FPL will capture the final guidance in its AMPs. The NRC staff stated that the information regarding the interim guidance should at least be discussed in the operating experience section of the AMP.

Regarding neutron fluence calculations based on experience from NRC staff review of recent license renewal applications, the applicant explained that Turkey Points current licensing basis uses WCAP-14040-A, Rev. 4, Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves, in its neutron fluence calculations. This same methodology will be use through the time limited aging analysis. The applicant further explained that the Neutron Fluence Monitoring AMP (GALL-SLR AMP X.M2) follows the GALL-SLR Report. The neutron fluence calculations were updated for Turkey Points extended power uprate (EPU) which was submitted in 2010 (ADAMS Accession No. ML103560167). The NRC staffs safety evaluation for the EPU can be found at ADAMS Accession No. ML11293A359.

Regarding EAF, the applicant stated that they used NURG-6260, Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, and added all of the ASME components with cumulative use fatigue (CUF) values to identify components with environmental CUF (CUFEN) values greater than 1. The applicant identified 12 components with CUFEN values greater than 1 and completed analyses to reduce the CUFEN values. The applicant stated that they reduced the CUFEN values for six of the components to less than one. For the remaining six components with CUFEN values that remained greater than one, the applicant state that the SLRA will demonstrate that effects of aging on the intended functions of the will be adequately managed for the period of extended operation in accordance with Title 10 of the Code of Federal Regulations Section 54.21(c)(1)(iii):

Based on a question from the NRC staff, the applicant stated that they updated the CUFs for each component, they did not bin the components and then update the CUFs. The applicant stated that the methodology for how this was completed is described in the SLRA.

The NRC staff ended the meeting by stating that, while the teleconference was a good discussion, the staff reserves judgement on the application until it is submitted by FPL.