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Category:Meeting Summary
MONTHYEARML23152A2552023-06-0505 June 2023
Summary of the May 17, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station
ML22178A2312022-06-28028 June 2022
Summary of the June 22, 2022, Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Davis Besse Nuclear Power Station
ML22088A1972022-03-30030 March 2022
Summary of March 11, 2022, Call Regarding the Spring 2022 Steam Generator Tube Inspections
ML22084A1022022-03-27027 March 2022
Reissue Summary of the February 1, 2022, Regulatory Conference Between Energy Harbor, Davis-Besse Nuclear Power Station and the Nuclear Regulatory Commission
ML22077A8062022-03-23023 March 2022
Summary of the February 1, 2022, Regulatory Conference Between Energy Harbor, Davis-Besse Nuclear Power Station and the Nuclear Regulatory Commission
ML21314A5362021-11-18018 November 2021
Summary of November 8, 2021, Meeting with Energy Harbor Nuclear Corp. Regarding Its Proposed Alternate for Examination of Steam Generator Welds at
ML21180A4632021-06-29029 June 2021
Summary of the June 22, 2021, Public Outreach to Discuss the NRC 2020 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant
ML20240A2942020-08-27027 August 2020
July 23, 2020 Summary of Public Webinar to Discuss the Nrc 2019 End-Of-Cycle Plant Performance Assessment of the Davis-Besse Nuclear Power Station and the Perry Nuclear Power Plant
ML19249C7112019-09-0404 September 2019
Summary of the July 18, 2019 Public Outreach/Open House to Discuss the NRC 2018 End-Of-Cycle Plant Performance Assessment of the Davis-Besse Nuclear Power Station
ML18313A1982018-11-14014 November 2018
Summary of Meeting with Firstenergy Nuclear Operating Company Regarding Planned Submittal of Post-Shutdown Emergency Plan for Davis-Besse Nuclear Power Station
ML18192A6522018-07-10010 July 2018
Summary of Public Meeting to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station
ML17258A1462017-09-20020 September 2017
Summary of September 12, 2017, Meeting with Firstenergy Nuclear Operating Company Regarding Its Licensing Amendment Request to Adopt National Fire Protection Association Standard 805 at Davis-Besse Nuclear Power Station, Unit No. 1
ML17229B1362017-08-16016 August 2017
Summary of July 19, 2017, Open House to Discuss the 2016 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station
ML17087A1882017-03-28028 March 2017
Summary of Closed Meeting with Firstenergy Nuclear Operating Company Regarding Changes to the Davis-Besse Nuclear Power Station, Unit No. 1, Security Plan
ML16197A0522016-07-14014 July 2016
Summary of June 21, 2016, Public Meeting with Firstenergy Nuclear Operating Company to Discuss the 2015 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Station
ML16130A7502016-05-12012 May 2016
Summary of April 12, 2016, Teleconference Regarding Steam Generator Tube Inservice Inspection
ML14177A5782016-02-22022 February 2016
November 13, 2013, Summary of Meeting with Firstenergy Nuclear Operating Company to Discuss Delay in Submittal of Fire Risk Reduction Amendment Request
ML16006A3512016-01-20020 January 2016
December 17,2015 Summary of Meeting with Firstenergy Nuclear Operating Company on Its License Amendment Request to Revise the Emergency Diesel Generator Surveillance Requirements at Davis-Besse Nuclear Power Station, Unit 1
ML16007A3962016-01-12012 January 2016
Summary of January 5, 2016, Meeting with Firstenergy Nuclear Operating Company on Its Planned License Amendment Request to Revise the Emergency Action Level Scheme at Davis-Besse Nuclear Power Station, Unit No. 1
ML15196A5162015-07-24024 July 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
ML15170A2862015-06-18018 June 2015
Summary of the Public Open House Regarding Davis-Besse Nuclear Power Station
ML15089A1642015-04-27027 April 2015
Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis
ML15056A4562015-04-20020 April 2015
Summary of Teleconference Call Held February 20, 2015, Between U.S. Nuclear Regulatory Commission and First Energy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power Station
ML14325A7782014-12-16016 December 2014
October 6, 2014, Summary of Pre-Application Meeting with Firstenergy Nuclear Operating Company to Discuss Proposed Combination of Site Emergency Plans
ML14224A6142014-08-12012 August 2014
Summary of Public Meeting to Discuss the 2013 Performance of Davis-Besse Nuclear Power Station
ML14160B1032014-07-10010 July 2014
June 6, 2014 Summary of Meeting with FENOC Flooding Hazard Reevaluation Extension Request for Beaver Valley Power Station, Units 1 and 2 and Flooding Hazard Reevaluation Report for Davis-Besse Nuclear Power Station, Unit 1
ML14099A4642014-05-0606 May 2014
Summary of Public Meetings to Discuss Draft Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Davis-Besse Nuclear Generating Station, Unit 1
ML14099A3392014-04-22022 April 2014
March 27, 2014, Summary of Telephone Conference Call Held Between Nuclear Regulatory Commission and First Energy Nuclear Operating Company Concerning Commitment 13 of the Safety Evaluation Report Pertaining to the Davis Besse Unit 1, Licens
ML14080A1842014-03-21021 March 2014
Summary of Webinar Meeting to Discuss NRC Inspection Activities Associated with the Davis-Besse Nuclear Power Station Installation of Two New Steam Generators
ML13240A0702013-08-29029 August 2013
8 22 2013 DB NRC Telecon Summary License Condition
ML13225A2932013-08-12012 August 2013
7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop
ML13197A2572013-07-17017 July 2013
5 28 2013 DB Hs Bolts Telecon Summary
ML13182A4082013-07-17017 July 2013
Summary of Telephone Conference Call Held on October 16, 2012, Between NRC and FENOC, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station, LRA (TAC No. ME640)
ML13149A2862013-07-12012 July 2013
Summary of Telephone Conference Call Held on May 2, 2013, Between the NRC and FENOC, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station License Renewal Application
ML13182A4432013-07-12012 July 2013
Summary of Telephone Conference Call Held on April 11, 2013, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Powe
ML13149A2882013-07-0909 July 2013
May 9, 2013, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power Stat
ML13168A2422013-06-14014 June 2013
6/11/2013 - Summary of Open House to Discuss the 2012 Davis-Besse Nuclear Power Station End-Of-Cycle Performance
ML13091A3272013-03-29029 March 2013
Summary of Public Meeting to Discuss the Davis-Besse Replacement Activities
ML13051A6602013-03-26026 March 2013
Summary of Telephone Conference Call Held on January 23, 2013, Between the NRC and FENOC, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station, LRA
ML13051A0682013-03-26026 March 2013
January 16, 2013 Summary of Telephone Conference Call Held Between U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company
ML13025A0272013-02-14014 February 2013
October 23, 2012 Summary of Telephone Conference Call Held Between the Nuclear Regulatory and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power Station, License
ML12277A4082012-10-0303 October 2012
September 26, 2012, Summary of Public Meeting to Discuss FENOC Fleet Performance
ML12243A2832012-08-30030 August 2012
Summary of Public Meeting to Discuss Nrc'S Review of Fenoc'S Root Cause Analysis of Davis-Besse Shield Building Cracks
ML12237A0432012-08-24024 August 2012
August 15, 2012 - Summary of Public Meeting to Discuss the Davis-Besse Nuclear Power Station, Unit 1, End-Of-Cycle Plant Performance Assessment
ML12195A1132012-07-16016 July 2012
Summary of Public Meeting with FENOC Regarding Licensing Practices and Processes
ML12165A3502012-07-16016 July 2012
Summary of Conference Call for Stream Generator Tube Inservice Inspections for Spring 2012 Refueling Outage
ML12052A1792012-05-15015 May 2012
July 19, 2011, Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power Station
ML12059A0782012-04-0202 April 2012
Summary of Telephone Conference Call Held on February 9, 2012, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Pow
ML12061A2582012-04-0202 April 2012
Summary of Telephone Conference Call Held on July 12,2011, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power
ML12031A1832012-03-0202 March 2012
Summary of Telephone Conference Call Held on July 13, 2011, Between the U.S. Nuclear Regulatory Commission and Firstentergy Nuclear Operating Company, Concerning Request for Additional Information Pertaining to the DA7 13 2011 DB NRC Teleco
2023-06-05
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Text
November 18, 2021 LICENSEE: ENERGY HARBOR NUCLEAR CORP.
FACILITY: DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1
SUBJECT:
SUMMARY
OF NOVEMBER 8, 2021, MEETING WITH ENERGY HARBOR NUCLEAR CORP. REGARDING ITS PROPOSED ALTERNATE FOR EXAMINATION OF STEAM GENERATOR WELDS AT DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 (EPID L-2021-LLR-0067)
By application dated September 13, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21256A119), Energy Harbor Nuclear Corp. (the licensee) submitted a request for a proposed alternative to certain requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a, Codes and standards, for Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse). Specifically, in accordance with 10 CFR 50.55a(z)(1),
the application requests U.S. Nuclear Regulatory Commission (NRC) approval to increase the inservice inspection (ISI) interval for the steam generator (SG) welds and nozzle inner radii from 10 years to 30 years. These ISI requirements are specified in the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code),Section XI, as incorporated by reference in 10 CFR 50.55a.
The proposed alternative is based on the methodology described in Electric Power Research Institute (EPRI) Report No. 3002015906, Technical Bases for Inspection Requirements for PWR [Pressurized-Water Reactor] Steam Generator Class 1 Nozzle-to-Vessel Welds and Class 1 and Class 2 Vessel Head, Shell, Tubesheet-to-Head, and Tubesheet-to-Shell Welds, 2019 (ADAMS Accession No. ML20225A141), and EPRI Report No. 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections, April 2019 (ADAMS Accession No. ML19347B107) (collectively, the EPRI Reports).
On November 8, 2021, an observational public meeting was held between the NRC staff and representatives for the licensee to discuss the draft NRC staff request for addition information (RAI) for the proposed alternative (ADAMS Accession No. ML21301A099). Specifically, the meeting focused on draft RAI-3, RAI-6, and RAI-12. The meeting notice and agenda are available in ADAMS at Accession No. ML21300A145. A list of attendees is enclosed.
The Davis-Besse SGs were replaced in 2014. The SG welds and nozzle inner radii were subject to preservice inspection (PSI), but the first set of ISIs has not been completed. The licensee stated that two weld inspections have not been completed. In draft RAI-12, the NRC staff stated, in part, that:
By letters dated January 11 and July 16, 2021 (ADAMS Accession Nos.
ML20352A155 and ML21167A355, respectively), the NRC approved proposed alternatives to extend the inspection interval for SG welds and nozzle inner radii at Vogtle Electric Generating Plant, Units 1 and 2 (Vogtle), and Millstone Power
Station, Unit No. 2 (Millstone), respectively. These approved alternatives were both based, in part, on the EPRI Reports and were identified as precedents in Section 7 of the proposed alternative for Davis-Besse. Vogtle, Millstone, and EPRI generally concluded that the ISI interval for SG welds and nozzles could be extended when only PSI without any other post-PSI examinations had been performed. However, in the associated NRC safety evaluations, the NRC staff found that these general conclusions were unacceptable because, in part, these general conclusions do not account for the effect of the combination of the most significant parameters or the added uncertainty of low probability events.
During the public meeting, the licensee stated that its application addressed the significant parameters and uncertainties discussed in the NRC safety evaluations for the precedents. The licensee noted that its application conservatively assumed that only PSI had been performed.
In addition, the licensee stated that the ISIs have not found any indications for the SG welds and nozzle inner radii that have been performed. Therefore, the licensee concluded that there was a small likelihood of finding anything during the ISI of the remaining welds. The licensee stated that Tables E-1, E-2, and E-3 in the application include all the important parameters. The licensee also stated that the probabilities of leakage and rupture of a SG weld are several orders of magnitude below the acceptance criteria of 10-6 per year and the change in risk associated with extending the ISIs from 10 years to 30 years is small.
The NRC staff stated that it appears the licensee is making a risk-based argument, whereas the NRC staff uses risk-informed decision-making. The NRC staff stated that, consistent with the NRCs risk-informed principles, there needs to be some performance monitoring (i.e., ISI) of the SG welds and nozzle inner radii. The NRC staff further stated there are still some unknowns and, therefore, the probabilities determined by the PROMISE code used by the licensee may be impacted.
In draft RAI-6, the NRC staff requests that the licensee provide the following information:
Discuss the acceptability of the KIC value used for the beginning and ending of heatup and cooldown transients for calculating the probability of failure and probability of leakage of the Davis-Besse SG welds and nozzle inside radii.
During the meeting, the NRC staff stated that it would be acceptable for the licensee to reference acceptable KIC values used for other plants.
In draft RAI-3, the NRC staff requests that the licensee provide the plant-specific analysis used to support its application. The licensee clarified that the plant-specific analysis is provided in Tables E-1, E-2, and E-3 of the application. The licensee stated that the plant-specific analysis used representative components and stress multipliers. The licensee also stated it performed plant-specific runs of the PROMISE code, and that it could provide the input and output files in response to draft RAI-3. The NRC staff stated that it would consider whether performing an audit of the input and output files through an online portal would be beneficial.
The licensee stated that it would let the NRC project manager know in a few days how long it would take to respond to the RAI. The NRC project manager noted that the licensee requested approval by March 2022, and, if the licensee took an extended amount of time to respond to the RAI, the NRC staff may not be able to complete its review within the requested timeframe.
There were no public comments and no public meeting feedback forms were received. No regulatory decisions were made at this meeting.
Please direct any inquiries to me at 301-415-1380 or Blake.Purnell@nrc.gov.
/RA/
Blake Purnell, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES NOVEMBER 8, 2021, MEETING WITH ENERGY HARBOR NUCLEAR CORP.
Name Affiliation Blake Purnell NRC John Tsao NRC Angie Buford NRC David Rudland NRC Dan Widrevitz NRC Carolyn Wolf NRC Jack Bell NRC David Dijamco NRC Phil Lashley Energy Harbor Kathleen Nevins Energy Harbor Alan Scheanwald Energy Harbor Daniel Patten Energy Harbor Andrew Bishop Energy Harbor Kevin Allen Energy Harbor Scott Chesworth Structural Integrity Dedhia Dilip Structural Integrity Mo Uddin Structural Integrity Nat Cofie Structural Integrity Enclosure
Notice ML21300A145; Summary ML21314A536 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME BPurnell SRohrer NSalgado BPurnell DATE 11/17/21 11/17/21 11/18/21 11/18/21
