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| | issue date = 05/12/2016 | | | issue date = 05/12/2016 |
| | title = Summary of April 12, 2016, Teleconference Regarding Steam Generator Tube Inservice Inspection | | | title = Summary of April 12, 2016, Teleconference Regarding Steam Generator Tube Inservice Inspection |
| | author name = Purnell B A | | | author name = Purnell B |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Boles B D | | | addressee name = Boles B |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000346 | | | docket = 05000346 |
| | license number = NPF-003 | | | license number = NPF-003 |
| | contact person = Purnell B A | | | contact person = Purnell B |
| | case reference number = CAC MF7398 | | | case reference number = CAC MF7398 |
| | document type = Conference/Symposium/Workshop Paper, Letter, Meeting Summary | | | document type = Conference/Symposium/Workshop Paper, Letter, Meeting Summary |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 12, 2016 Mr. Brian D. Boles Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 N. State Route 2 Oak Harbor, OH 43449-9760 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 12, 2016 Mr. Brian D. Boles Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 N. State Route 2 Oak Harbor, OH 43449-9760 |
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| ==SUBJECT:== | | ==SUBJECT:== |
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| ==SUMMARY== | | ==SUMMARY== |
| OF APRIL 12, 2016, TELECONFERENCE REGARDING STEAM GENERATOR TUBE INSERVICE INSPECTION (CAC NO. MF7398) | | OF APRIL 12, 2016, TELECONFERENCE REGARDING STEAM GENERATOR TUBE INSERVICE INSPECTION (CAC NO. MF7398) |
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| ==Dear Mr. Boles:== | | ==Dear Mr. Boles:== |
| | |
| On April 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a teleconference with representatives of FirstEnergy Nuclear Operating Company (the licensee) regarding the inservice inspections of steam generators at Davis-Besse Nuclear Power Station, Unit No. 1. A summary of the teleconference and a list of participants are enclosed. | | On April 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a teleconference with representatives of FirstEnergy Nuclear Operating Company (the licensee) regarding the inservice inspections of steam generators at Davis-Besse Nuclear Power Station, Unit No. 1. A summary of the teleconference and a list of participants are enclosed. |
| By letter dated February 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16057A865), the NRC staff provided questions for the licensee to address during the call. The licensee's handouts used during the call, which addressed the staff's questions, are available under ADAMS Accession No. ML 16117A182. | | By letter dated February 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16057A865), the NRC staff provided questions for the licensee to address during the call. The licensee's handouts used during the call, which addressed the staff's questions, are available under ADAMS Accession No. ML16117A182. |
| If you have any questions, please contact me at (301) 415-1380. | | If you have any questions, please contact me at (301) 415-1380. |
| Docket No. 50-346 cc: Distribution via Listserv | | Sincerely, fl;l ;JVVZ/ |
| | Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Summary of Teleconference | | : 1. Summary of Teleconference |
| : 2. List of Participants Sincerely, fl;l ;JVVZ/ Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | | : 2. List of Participants |
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| ==SUMMARY== | | ==SUMMARY== |
| OF APRIL 12, 2016, TELECONFERENCE SPRING 2016 STEAM GENERATOR INSPECTIONS DAVIS-BESSE NUCLAER POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 On April 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of FirstEnergy Nuclear Operating Company (the licensee) regarding the ongoing steam generator (SG) inspection at Davis-Besse Nuclear Power Station (Davis-Besse), Unit No. 1. By letter dated February 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16057 A865), the staff provided questions for the licensee to address during the call. The licensee's handouts used during the call, which addressed the staff's questions, are available under ADAMS Accession No. ML 16117A182, and this information is not repeated here. Definitions of acronyms used by the licensee in its handouts are provided at the end of this summary. Background Davis-Besse has two once-through SGs designed by Babcock and Wilcox. These replacement SGs were installed in 2014. The tubes were hydraulically expanded for part of the length of the tubesheet and are supported by sixteen carbon steel tube support plates. The licensee stated that a number of adjustments were made in the design of their new SGs to mitigate tube-to-tube wear degradation. | | OF APRIL 12, 2016, TELECONFERENCE SPRING 2016 STEAM GENERATOR INSPECTIONS DAVIS-BESSE NUCLAER POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 On April 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of FirstEnergy Nuclear Operating Company (the licensee) regarding the ongoing steam generator (SG) inspection at Davis-Besse Nuclear Power Station (Davis-Besse), Unit No. 1. By letter dated February 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16057A865), the staff provided questions for the licensee to address during the call. The licensee's handouts used during the call, which addressed the staff's questions, are available under ADAMS Accession No. ML16117A182, and this information is not repeated here. Definitions of acronyms used by the licensee in its handouts are provided at the end of this summary. |
| For example, the length of the tube-to-tubesheet expansion was adjusted to control the amount of preloading on the tubes. The licensee stated that the integral orifice plate is in the downcomer region, and it is adjusted to set the water column height in the feedwater downcomer region of the SG. The licensee stated that tube support plate (TSP) 15S is below the auxiliary feedwater nozzle and has drilled holes in the periphery through which the tubes pass. The remaining portion of TSP 15S and the other TSPs in the SG have trefoil broached holes. The trefoil holes of the even numbered TSPs are offset from centerline to minimize tube wear at the TSP elevations. | | |
| Summary of Inspection Results At the time of the teleconference, SG tube inspections were ongoing and the information provided by the licensee did not represent final inspection results. The information provided by the licensee was for the point when the licensee had completed 65 percent of the inspections for SG 2A and 47 percent of the inspections for SG 1 B. The licensee had identified 358 wear-like indications for SG 2A and 22 wear-like indications for SG 1 B. The licensee believes the higher number of indications found in SG 2A is due to a different length of secondary side piping that runs into SG 2A. The different length is due to the physical configuration of the plant. The licensee stated it had seen similar differences with its previous SGs. The licensee had identified 142 locations in SG 2A and 20 locations in SG 1 B needing special interest exams. No tube-to-tube wear indications had been detected. | | ===Background=== |
| The licensee stated that it Enclosure 1 had identified 182 wear indications at TSP 16S which were distributed amongst tubes in the periphery region. The periphery region has the highest crossflow velocities. | | Davis-Besse has two once-through SGs designed by Babcock and Wilcox. These replacement SGs were installed in 2014. The tubes were hydraulically expanded for part of the length of the tubesheet and are supported by sixteen carbon steel tube support plates. The licensee stated that a number of adjustments were made in the design of their new SGs to mitigate tube-to-tube wear degradation. For example, the length of the tube-to-tubesheet expansion was adjusted to control the amount of preloading on the tubes. |
| The licensee performed as-found visual inspections of the SG channel head, but the inspections were incomplete at the time of the call. The licensee stated it would notify NRC staff if any abnormalities are found. The NRC staff did not identify any issues during the call that required follow-up action. Acronyms Acronyms used in the licensee's document are defined below: * % TW -Percent Through-Wall | | The licensee stated that the integral orifice plate is in the downcomer region, and it is adjusted to set the water column height in the feedwater downcomer region of the SG. The licensee stated that tube support plate (TSP) 15S is below the auxiliary feedwater nozzle and has drilled holes in the periphery through which the tubes pass. The remaining portion of TSP 15S and the other TSPs in the SG have trefoil broached holes. The trefoil holes of the even numbered TSPs are offset from centerline to minimize tube wear at the TSP elevations. |
| * ADI -Absolute Drift Indication | | Summary of Inspection Results At the time of the teleconference, SG tube inspections were ongoing and the information provided by the licensee did not represent final inspection results. The information provided by the licensee was for the point when the licensee had completed 65 percent of the inspections for SG 2A and 47 percent of the inspections for SG 1B. |
| * BLG -Bulge | | The licensee had identified 358 wear-like indications for SG 2A and 22 wear-like indications for SG 1B. The licensee believes the higher number of indications found in SG 2A is due to a different length of secondary side piping that runs into SG 2A. The different length is due to the physical configuration of the plant. The licensee stated it had seen similar differences with its previous SGs. |
| * CAL -Calibration | | The licensee had identified 142 locations in SG 2A and 20 locations in SG 1B needing special interest exams. No tube-to-tube wear indications had been detected. The licensee stated that it Enclosure 1 |
| * CHN -Channel | | |
| * CMOA -Condition Monitoring Operational Assessment | | had identified 182 wear indications at TSP 16S which were distributed amongst tubes in the periphery region. The periphery region has the highest crossflow velocities. |
| * COL -Column | | The licensee performed as-found visual inspections of the SG channel head, but the inspections were incomplete at the time of the call. The licensee stated it would notify NRC staff if any abnormalities are found. |
| * DB -Davis-Besse | | The NRC staff did not identify any issues during the call that required follow-up action. |
| * DOI -Distorted Dent/Ding Indication | | Acronyms Acronyms used in the licensee's document are defined below: |
| * DEG -Degree | | * % TW - Percent Through-Wall |
| * ONG-Ding | | * ADI - Absolute Drift Indication |
| | * BLG - Bulge |
| | * CAL - Calibration |
| | * CHN - Channel |
| | * CMOA - Condition Monitoring Operational Assessment |
| | * COL - Column |
| | * DB - Davis-Besse |
| | * DOI - Distorted Dent/Ding Indication |
| | * DEG - Degree |
| | * ONG- Ding |
| * ONT-Dent | | * ONT-Dent |
| * OSI -Distorted Support Indication | | * OSI - Distorted Support Indication |
| * DTI -Distorted Tubesheet Indication | | * DTI - Distorted Tubesheet Indication |
| * EXT -Extent | | * EXT - Extent |
| * IDC -Inside Diameter Chatter | | * IDC - Inside Diameter Chatter |
| * LPI -Loose Part Indication | | * LPI - Loose Part Indication |
| * L TE -Lower Tube End | | * LTE - Lower Tube End |
| * L TS -Lower Tubesheet | | * LTS - Lower Tubesheet |
| * MRPC -Motorized Rotating Pancake Coil | | * MRPC - Motorized Rotating Pancake Coil |
| * NQI -Non-Quantifiable Indication | | * NQI - Non-Quantifiable Indication |
| * OA -Operational Assessment | | * OA - Operational Assessment |
| * OBS -Obstruction | | * OBS - Obstruction |
| * OD -Outside Diameter | | * OD - Outside Diameter |
| * PLP -Possible Loose Part | | * PLP - Possible Loose Part |
| * PVN -Permeability Variation | | * PVN - Permeability Variation |
| * SG -Steam Generator | | * SG - Steam Generator |
| * SVI -Single Volumetric Indication | | * SVI - Single Volumetric Indication |
| * Tech Spec -Technical Specification | | * Tech Spec - Technical Specification |
| * TSP -Tube Support Plate | | * TSP - Tube Support Plate |
| * TWO -Through-Wall Depth | | * TWO - Through-Wall Depth |
| * UTE -Upper Tube End | | * UTE - Upper Tube End |
| * UTS -Upper Tubesheet | | * UTS - Upper Tubesheet |
| * V-Volts | | * V-Volts |
| * VOL -Volumetric | | * VOL - Volumetric |
| * WAR-Wear LIST OF PARTICIPANTS APRIL 12, 2016, TELECONFERENCE WITH FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC) Name Affiliation Blake Purnell NRC Jennifer Hauser NRC Alan Huynh NRC Andrew Johnson NRC Tom Bilk NRC Thomas Briley NRC Phil Lashley FE NOC William Boudreaux FE NOC Steve Slosnerick FE NOC Victor Newman FE NOC Luke Twarek FE NOC Kevin Zellers FE NOC Alex Cullu FE NOC Kendall Johnson FE NOC Enclosure 2 | | * WAR-Wear |
| Mr. Brian D. Boles Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 N. State Route 2 Oak Harbor, OH 43449-9760 May 12, 2016
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| ==SUBJECT:==
| | LIST OF PARTICIPANTS APRIL 12, 2016, TELECONFERENCE WITH FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC) |
| DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 -
| | Name Affiliation Blake Purnell NRC Jennifer Hauser NRC Alan Huynh NRC Andrew Johnson NRC Tom Bilk NRC Thomas Briley NRC Phil Lashley FE NOC William Boudreaux FE NOC Steve Slosnerick FE NOC Victor Newman FE NOC Luke Twarek FE NOC Kevin Zellers FE NOC Alex Cullu FE NOC Kendall Johnson FE NOC Enclosure 2 |
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| ==SUMMARY==
| | ML16117A182. |
| OF APRIL 12, 2016, TELECONFERENCE REGARDING STEAM GENERATOR TUBE INSERVICE INSPECTION (CAC NO. MF7398)
| |
| | |
| ==Dear Mr. Boles:==
| |
| On April 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a teleconference with representatives of FirstEnergy Nuclear Operating Company (the licensee) regarding the inservice inspections of steam generators at Davis-Besse Nuclear Power Station, Unit No. 1. A summary of the teleconference and a list of participants are enclosed.
| |
| By letter dated February 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16057A865), the NRC staff provided questions for the licensee to address during the call. The licensee's handouts used during the call, which addressed the staff's questions, are available under ADAMS Accession No. ML 16117A182.
| |
| If you have any questions, please contact me at (301) 415-1380. | | If you have any questions, please contact me at (301) 415-1380. |
| Docket No. 50-346 cc: Distribution via Listserv | | Sincerely, IRA/ |
| | Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv |
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| ==Enclosures:== | | ==Enclosures:== |
| : 1. Summary of Teleconference | | : 1. Summary of Teleconference |
| : 2. List of Participants DISTRIBUTION: | | : 2. List of Participants DISTRIBUTION: |
| PUBLIC LPL3-2 r/f RidsNrrDorlLpl3-2 Resource RidsNrrLASRohrer Resource RidsNrrPMDavisBesse Resource RidsRgn3MailCenter Resource ADAMS A ccession N o.M L1613 A750 0 OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA NAME BPurnell SRohrer DATE 5/11/16 5/10/16 Sincerely, IRA/ Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDeEsgb Resource AHuynh, NRR AJohnson, NRR KKarwoski, NRR GKulesa, NRR DHills, Riii *b 1y memo DE/ESGB/BC DORL/LPL3-2/BC (A) GKulesa* GE Miller 4/27/16 5/12/16 DORL/LPL3-2/PM BPurnell 5/12/16 OFFICIAL RECORD COPY}} | | PUBLIC RidsNrrDeEsgb Resource LPL3-2 r/f AHuynh, NRR RidsNrrDorlLpl3-2 Resource AJohnson, NRR RidsNrrLASRohrer Resource KKarwoski, NRR RidsNrrPMDavisBesse Resource GKulesa, NRR RidsRgn3MailCenter Resource DHills, Riii ADAMS A ccession N o.M L1613 0 A750 *b1y memo OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA DE/ESGB/BC DORL/LPL3-2/BC (A) DORL/LPL3-2/PM NAME BPurnell SRohrer GKulesa* GE Miller BPurnell DATE 5/11/16 5/10/16 4/27/16 5/12/16 5/12/16}} |
Letter Sequence Meeting |
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MONTHYEARML16057A8652016-02-29029 February 2016
Upcoming Steam Generator Tube Inservice Inspection
Project stage: Other
ML16117A1822016-04-22022 April 2016
Industry Slides for the Spring 2016 Conference Call Regarding the Steam Generator Tube Inservice Inspections
Project stage: Other
ML16130A7502016-05-12012 May 2016
Summary of April 12, 2016, Teleconference Regarding Steam Generator Tube Inservice Inspection
Project stage: Meeting
2016-04-22
[Table View] |
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|---|
Category:Conference/Symposium/Workshop Paper
MONTHYEARML16130A7502016-05-12012 May 2016
Summary of April 12, 2016, Teleconference Regarding Steam Generator Tube Inservice Inspection
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
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
ML12018A1462012-02-0909 February 2012
June 16, 2011, Summary of Telephone Conference Call Held Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, License Renewal Application
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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, LRA
ML0804306122008-03-0505 March 2008
Summary of Conference Telephone Call Regarding Their 2008 Steam Generator Tube Inspections
ML0618002632006-09-18018 September 2006
Crack Growth Rates in a PWR Environment of Nickel-Base Alloys from Davis-Besse and V. C. Summer Plants
ML0526600162005-08-16016 August 2005
Mantg Conference, 8/16/05 - Plenary - Keynote Speech by Samuel J. Collins, Regional Administrator, Region I, the Changing Roles of the Operators and Trainers
2016-05-12
[Table view]
Category:Letter
MONTHYEARML24281A0662024-10-0404 October 2024
EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components
IR 05000346/20244032024-09-27027 September 2024
Security Baseline Inspection Report 05000346/2024403
ML24269A0552024-09-25025 September 2024
Submittal of the Updated Final Safety Analysis Report, Revision 35
05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024
Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground
ML24134A1522024-09-17017 September 2024
Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter
ML24260A2382024-09-16016 September 2024
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML24255A8032024-09-11011 September 2024
Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24249A1602024-09-0505 September 2024
Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station
L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024
Submittal of Quality Assurance Program Manual, Revision 30
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
IR 05000346/20240052024-08-22022 August 2024
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005)
L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024
Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule
IR 05000346/20240022024-08-0101 August 2024
Integrated Inspection Report 05000346/2024002
IR 05000346/20244012024-07-30030 July 2024
Security Baseline Inspection Report 05000346/2024401
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024
Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report
L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024
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L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024
Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024
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L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024
Unit No.1 - Report of Facility Changes, Tests, and Experiments
ML24142A3532024-05-21021 May 2024
Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024
Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023
L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024
Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage
IR 05000346/20240012024-05-0303 May 2024
Integrated Inspection Report 05000346/2024001
L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024
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L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024
Submittal of Core Operating Limits Report, Cycle 24, Revision 0
ML24089A2582024-04-0101 April 2024
Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010
L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024
Annual Notification of Property Insurance Coverage
ML24036A3472024-03-0707 March 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24057A0752024-03-0101 March 2024
the Associated Independent Spent Fuel Storage Installations
IR 05000346/20230062024-02-28028 February 2024
Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006)
ML24057A3362024-02-28028 February 2024
Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006)
L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024
Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule
CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024
Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions
L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024
Retrospective Premium Guarantee
IR 05000346/20243012024-02-0202 February 2024
NRC Initial License Examination Report 05000346/2024301
IR 05000346/20230042024-01-31031 January 2024
Integrated Inspection Report 05000346/2023004
ML23313A1352024-01-17017 January 2024
Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program
ML23353A1192023-12-19019 December 2023
Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
ML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000346/20234032023-11-0202 November 2023
Security Baseline Inspection Report 05000346/2023403
ML23293A0612023-11-0101 November 2023
Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant
ML24045A0322023-10-26026 October 2023
L-23-221 Proposed Exam Submittal Cover Letter
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
ML23269A1242023-09-27027 September 2023
Request for Withholding Information from Public Disclosure
2024-09-06
[Table view]
Category:Meeting Summary
MONTHYEARML24248A2332024-09-0505 September 2024
Summary of the August 29, 2024, Public Outreach to Discuss the NRC 2023 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station
ML23152A2552023-06-0505 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
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2024-09-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 12, 2016 Mr. Brian D. Boles Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 N. State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 -
SUMMARY
OF APRIL 12, 2016, TELECONFERENCE REGARDING STEAM GENERATOR TUBE INSERVICE INSPECTION (CAC NO. MF7398)
Dear Mr. Boles:
On April 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a teleconference with representatives of FirstEnergy Nuclear Operating Company (the licensee) regarding the inservice inspections of steam generators at Davis-Besse Nuclear Power Station, Unit No. 1. A summary of the teleconference and a list of participants are enclosed.
By letter dated February 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16057A865), the NRC staff provided questions for the licensee to address during the call. The licensee's handouts used during the call, which addressed the staff's questions, are available under ADAMS Accession No. ML16117A182.
If you have any questions, please contact me at (301) 415-1380.
Sincerely, fl;l ;JVVZ/
Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv
Enclosures:
- 1. Summary of Teleconference
- 2. List of Participants
SUMMARY
OF APRIL 12, 2016, TELECONFERENCE SPRING 2016 STEAM GENERATOR INSPECTIONS DAVIS-BESSE NUCLAER POWER STATION, UNIT NO. 1 DOCKET NO. 50-346 On April 12, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff participated in a conference call with representatives of FirstEnergy Nuclear Operating Company (the licensee) regarding the ongoing steam generator (SG) inspection at Davis-Besse Nuclear Power Station (Davis-Besse), Unit No. 1. By letter dated February 29, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16057A865), the staff provided questions for the licensee to address during the call. The licensee's handouts used during the call, which addressed the staff's questions, are available under ADAMS Accession No. ML16117A182, and this information is not repeated here. Definitions of acronyms used by the licensee in its handouts are provided at the end of this summary.
Background
Davis-Besse has two once-through SGs designed by Babcock and Wilcox. These replacement SGs were installed in 2014. The tubes were hydraulically expanded for part of the length of the tubesheet and are supported by sixteen carbon steel tube support plates. The licensee stated that a number of adjustments were made in the design of their new SGs to mitigate tube-to-tube wear degradation. For example, the length of the tube-to-tubesheet expansion was adjusted to control the amount of preloading on the tubes.
The licensee stated that the integral orifice plate is in the downcomer region, and it is adjusted to set the water column height in the feedwater downcomer region of the SG. The licensee stated that tube support plate (TSP) 15S is below the auxiliary feedwater nozzle and has drilled holes in the periphery through which the tubes pass. The remaining portion of TSP 15S and the other TSPs in the SG have trefoil broached holes. The trefoil holes of the even numbered TSPs are offset from centerline to minimize tube wear at the TSP elevations.
Summary of Inspection Results At the time of the teleconference, SG tube inspections were ongoing and the information provided by the licensee did not represent final inspection results. The information provided by the licensee was for the point when the licensee had completed 65 percent of the inspections for SG 2A and 47 percent of the inspections for SG 1B.
The licensee had identified 358 wear-like indications for SG 2A and 22 wear-like indications for SG 1B. The licensee believes the higher number of indications found in SG 2A is due to a different length of secondary side piping that runs into SG 2A. The different length is due to the physical configuration of the plant. The licensee stated it had seen similar differences with its previous SGs.
The licensee had identified 142 locations in SG 2A and 20 locations in SG 1B needing special interest exams. No tube-to-tube wear indications had been detected. The licensee stated that it Enclosure 1
had identified 182 wear indications at TSP 16S which were distributed amongst tubes in the periphery region. The periphery region has the highest crossflow velocities.
The licensee performed as-found visual inspections of the SG channel head, but the inspections were incomplete at the time of the call. The licensee stated it would notify NRC staff if any abnormalities are found.
The NRC staff did not identify any issues during the call that required follow-up action.
Acronyms Acronyms used in the licensee's document are defined below:
- % TW - Percent Through-Wall
- ADI - Absolute Drift Indication
- CMOA - Condition Monitoring Operational Assessment
- DOI - Distorted Dent/Ding Indication
- OSI - Distorted Support Indication
- DTI - Distorted Tubesheet Indication
- IDC - Inside Diameter Chatter
- LPI - Loose Part Indication
- MRPC - Motorized Rotating Pancake Coil
- NQI - Non-Quantifiable Indication
- OA - Operational Assessment
- PLP - Possible Loose Part
- PVN - Permeability Variation
- SVI - Single Volumetric Indication
- Tech Spec - Technical Specification
LIST OF PARTICIPANTS APRIL 12, 2016, TELECONFERENCE WITH FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC)
Name Affiliation Blake Purnell NRC Jennifer Hauser NRC Alan Huynh NRC Andrew Johnson NRC Tom Bilk NRC Thomas Briley NRC Phil Lashley FE NOC William Boudreaux FE NOC Steve Slosnerick FE NOC Victor Newman FE NOC Luke Twarek FE NOC Kevin Zellers FE NOC Alex Cullu FE NOC Kendall Johnson FE NOC Enclosure 2
ML16117A182.
If you have any questions, please contact me at (301) 415-1380.
Sincerely, IRA/
Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv
Enclosures:
- 1. Summary of Teleconference
- 2. List of Participants DISTRIBUTION:
PUBLIC RidsNrrDeEsgb Resource LPL3-2 r/f AHuynh, NRR RidsNrrDorlLpl3-2 Resource AJohnson, NRR RidsNrrLASRohrer Resource KKarwoski, NRR RidsNrrPMDavisBesse Resource GKulesa, NRR RidsRgn3MailCenter Resource DHills, Riii ADAMS A ccession N o.M L1613 0 A750 *b1y memo OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA DE/ESGB/BC DORL/LPL3-2/BC (A) DORL/LPL3-2/PM NAME BPurnell SRohrer GKulesa* GE Miller BPurnell DATE 5/11/16 5/10/16 4/27/16 5/12/16 5/12/16
