ML15196A516

Summary of Telephone Conference Call Held on May 06, 2015, and May 19, 2015 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company

ML15196A516
Person / Time
Site:	Davis Besse
Issue date:	07/24/2015
From:	Richard Plasse License Renewal Projects Branch 1
To:	Office of Nuclear Reactor Regulation
Plasse R, NRR/DLR,415-1427
References
DLR-15-0358, TAC ME4640
Download: ML15196A516 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 24, 2015 LICENSEE:

FirstEnergy Nuclear Operating Company FACILITY:

Davis-Besse Nuclear Power Station, Unit 1

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 06, 2015, AND MAY 19,2015, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FIRSTENERGY NUCLEAR OPERATING COMPANY, TO CLARIFY THE RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1, LICENSE RENEWAL APPLICATION (TAC NO. ME4640)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FirstEnergy Nuclear Operating Company held telephone conference calls on May 06 and May 19, 2015, to clarify information in the applicants responses to requests for additional information (RAIs) concerning the safety review of the Davis-Besse Nuclear Power Station, Unit 1, license renewal application. The teleconference was useful in clarifying the information provided in the applicants recent submittal of the reactor vessel internals inspection plan dated April 21, 2015.

provides a listing of the participants and Enclosure 2 contains a summary of the items discussed with the applicant regarding the submittal.

The applicant had an opportunity to comment on this summary.

Sincerely,

/RA by Jeff Mitchell for /

Richard Plasse, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosure:

As stated cc: Listserv

ML15196A516 *concurred via email OFFICE LA:DLR/RPB1*

PM:DLR/RPB1 BC:DLR/RPB1 PM:DLR/RPB1 NAME YEdmonds*

RPlasse (JMitchell for)

YDiaz-Sanabria RPlasse (JMitchell for)

DATE 7/ 21 /15 7/ 23 /15 7/ 23 /15 7/ 24 /15

Memo to FirstEnergy Nuclear Operating Company from R. Plasse dated July 24, 2015

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MAY 06, 2015, AND MAY 19, 2015, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FIRSTENERGY NUCLEAR OPERATING COMPANY, TO CLARIFY THE RESPONSES TO REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1, LICENSE RENEWAL APPLICATION (TAC NO. ME4640)

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PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrPMDavis-Besse Elaine.Keegan@nrc.gov Richard.Plasse@nrc.gov John.Lamb@nrc.gov David.McIntyre@nrc.gov Brian.Harris@nrc.gov Daniel.Kimble@nrc.gov Adam.Wilson@nrc.gov Jamnes.Cameron@nrc.gov Viktoria.Mitlyng@nrc.gov

ENCLOSURE 1 TELEPHONE CONFERENCE CALL DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS PARTICIPANTS AFFILIATIONS Richard Plasse U.S. Nuclear Regulatory Commission (NRC)

James Medoff NRC Cliff Custer FirstEnergy Nuclear Operating Company (FENOC)

Larry Hinkle FENOC Stephen Slosnerick FENOC Steven Dort FENOC Trent Henline FENOC Bev Watson AREVA Jeff Fleck AREVA Brian Haibach AREVA Ryan Hosler AREVA Hasan Charkas AREVA Tim Wiger AREVA Don Kim AREVA

ENCLOSURE 2 DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REACTOR VESSEL INTERNALS INSPECTION PLAN CLARIFICATIONS The telephone conference calls held on May 06 and May 19, 2015, were initiated by the Nuclear Regulatory Commission staff. The purpose of the calls was to clarify the information provided in the Davis-Besse Nuclear Power Station Reactor Vessel Internals Inspection Plan submitted by letter L-15-139 (ADAMS Accession No. ML15113B134) dated April 21, 2015, as follows:

Identification of Specific AREVA fabrication record that confirmed the upper flange weld in the core support structure of the Davis Besse reactor had been stress relieved during initial weld fabrication.

Identify which reactor vessel internal bolting components were replaced with bolts made from X-750 nickel alloy materials and had been analyzed with a cumulative usage factor (CUF) analysis (i.e., ASME low cycle fatigue analysis). Amend the license renewal application (LRA) (time-limited aging analysis (TLAA) sections and updated safety analysis report (USAR) Supplement sections) for these bolts to change the basis for accepting the CUF analyses under 10 CFR 54.21(c)(1)(iii) from use of the Fatigue Monitoring Program to the use of the Fatigue Monitoring Program and Reactor Vessel Internals Program.

Amend aging management review item on loss of fracture toughness for reactor internal vent valve assembly top and bottom retaining rings in LRA Table 3.1.2-2 to include a plant-specific note that credits the inspections and surveillance testing requirements in Technical Specification 5.5.4 as additional aging management bases for vent valve assembly components.

Identify how many physical measurements of the plenum rib pad-to-reactor vessel seating surface height were performed consistent one-time physical measurement criteria in MRP-227-A and clarify how the average measured compared to the 0.004 inch acceptance criteria set in Table 4-1 of MRP-227-A for these types of measurements.

Update the basis for accepting the reduction of ductility analysis for reactor vessel internals components (i.e., the subject of the TLAA in LRA Section 4.2.7) under 10 CFR 54.21(c)(1)(iii) to reflect the new commitment for this TLAA in Commitment No. 3 of the letter of April 21, 2015, in addition to the use of the Reactor Vessel Internals Program.

Update Commitment Nos. 1, 2, and 3 in the letter of April 21, 2015, to be for NRC review and approval and renumber the amended commitments and incorporate them into Table A-1 of the USAR Supplement.

Following discussion of the information that the NRC staff requested clarification, as noted above, FENOC committed to provide the details in an updated license renewal amendment.