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MONTHYEARML0702603952007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections - Handouts Project stage: Other ML0702602122007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections Project stage: Other 2007-01-31
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Category:Letter
MONTHYEARIR 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 License Amendment Request to Remove the Table of Contents from the Technical Specifications 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 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements 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 Occupational Radiation Exposure Report for Year 2023 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) 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 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 ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 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 IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 2024-08-01
[Table view] 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
[Table view] Category:Note to File incl Telcon Record
MONTHYEARML22088A1972022-03-30030 March 2022 Summary of March 11, 2022, Call Regarding the Spring 2022 Steam Generator Tube Inspections 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 ML12200A2542012-01-26026 January 2012 Root Cause Review - Status Call 1-26-2012 ML12200A2512012-01-19019 January 2012 Root Cause Review - Status Call 1/19/2012 ML11327A0792011-12-0202 December 2011 Summary of Telephone Conference Call Held on 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 ML0702602122007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections ML0403401322003-07-16016 July 2003 Telephone Message for Chairman Nils Diaz from Peter Berg, First Energy, Providing Name of New President and Chief Nuclear Officer 2022-03-30
[Table view] Category:Verbal Comm
MONTHYEARML22088A1972022-03-30030 March 2022 Summary of March 11, 2022, Call Regarding the Spring 2022 Steam Generator Tube Inspections 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 ML12200A2542012-01-26026 January 2012 Root Cause Review - Status Call 1-26-2012 ML12200A2512012-01-19019 January 2012 Root Cause Review - Status Call 1/19/2012 ML11327A0792011-12-0202 December 2011 Summary of Telephone Conference Call Held on 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 ML0702602122007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections ML0403401322003-07-16016 July 2003 Telephone Message for Chairman Nils Diaz from Peter Berg, First Energy, Providing Name of New President and Chief Nuclear Officer 2022-03-30
[Table view] |
Text
January 31, 2007 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS BESSE -
SUMMARY
OF CONFERENCE TELEPHONE CALL REGARDING THE SPRING 2006 STEAM GENERATOR INSPECTIONS (TAC NO. MD0529)
Dear Mr. Bezilla:
On March 21, 2006, the Nuclear Regulatory Commission (NRC) participated in a conference call with Davis Besse Nuclear Power Station representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the spring 2006 outage. The NRC follows the results of the industrys steam generator inspections in order to maintain an awareness of the condition of the steam generators and the types of tube degradation mechanisms that are active.
The enclosed documentation of the phone call is provided to FirstEnergy Nuclear Operating Company (FENOC) for information. Also, included is a copy of the information provided by FENOC in support of the conference call. If there are any questions, please contact me at 301-415-4037.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Conference Call Summary cc w/encls: See next page
Mr. Mark B. Bezilla January 31, 2007 Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Mail Stop A-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS BESSE -
SUMMARY
OF CONFERENCE TELEPHONE CALL REGARDING THE SPRING 2006 STEAM GENERATOR INSPECTIONS (TAC NO. MD0529)
Dear Mr. Bezilla:
On March 21, 2006, the Nuclear Regulatory Commission (NRC) participated in a conference call with Davis Besse Nuclear Power Station representatives regarding the ongoing steam generator (SG) tube inspection activities conducted during the spring 2006 outage. The NRC follows the results of the industrys steam generator inspections in order to maintain an awareness of the condition of the steam generators and the types of tube degradation mechanisms that are active.
The enclosed documentation of the phone call is provided to FirstEnergy Nuclear Operating Company (FENOC) for information. Also, included is a copy of the information provided by FENOC in support of the conference call. If there are any questions, please contact me at 301-415-4037.
Sincerely,
/RA/
Thomas J. Wengert, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Conference Call Summary cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsNrrDorlLpL3-2 RidsNrrLAEWhitt LPL3-2 R/F RidsAcrsAcnwMail RidsNrrPMTWengert RidsOgcRp RidsNrrDorl KKarwoski, NRR RidsNrrDciCsgb Package accession no ML070260225 ADAMS Accession Number: ML070260212 (Letter) Handouts accession no.ML070260395 OFFICE LPL3-2 LPL3-2/PM LPL3-2/LA CSGB/BC LPL3-2/BC (A)
NAME AShaikh TWengert:mw EWhitt AHiser MMarshall DATE 1/30/2007 1/30/2007 1/30/2007 1/31/2007 1/31/2007 OFFICIAL RECORD COPY
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 2006 STEAM GENERATOR TUBE INSPECTION ACTIVITIES CONFERENCE CALL
SUMMARY
On March 21, 2006, the Nuclear Regulatory Commission (NRC) staff conducted a phone call with representatives from Davis-Besse Nuclear Power Station, Unit 1 (Davis-Besse) to discuss their on-going steam generator (SG) tube inspections during their 14th refueling outage.
Davis-Besse has two Babcock and Wilcox once-through SGs. The tubes are sensitized Alloy 600 in the mill annealed condition. The last inspection of the SG tubes was performed in January and February 2005, during a mid-cycle outage. The mid-cycle outage was performed as a result of an extended shutdown.
In support of the phone call, Davis-Besse provided a table summarizing the SG tube inspections performed during the 2006 outage. This table, along with five other tables summarizing the results of the inspections, are attached to this summary. Additional clarifying information and information not included in the documents is summarized below:
The plant has operated approximately 380 effective full power days since the last examination.
In the ?2A SG, there are 569 tubes plugged, 199 Alloy 690 sleeves installed, and 108 tubes repaired by re-rolling. In the ?1B SG, there are 237 tubes plugged, 212 Alloy 690 sleeves installed, and 8 tubes repaired by re-rerolling.
All sleeves were installed in the 1994-1996 timeframe in the lane/wedge region as a preventive measure against high-cycle fatigue. All sleeves are manufactured from Alloy 690 thermally-treated material. The licensee has no plans to install sleeves this outage.
There was no measurable primary-to-secondary leakage during the prior cycle.
The detection limit for primary-to-secondary leakage is approximately 3x10-3 gallons per day. As a result of not observing any leakage, no secondary side pressure test was performed.
The periphery gap analysis is performed to confirm that the stabilized auxiliary feedwater header remains at least 0.25-inch from the tube tubing. There was no evidence of movement of the header. The technique used for performing this examination was qualified.
The full length bobbin examination for the sleeved tubes were from the lower tube end to the bottom of the sleeve.
The +PointTM examination performed on 67 percent of the sleeved tubes included not only 6-inches past the sleeve but also included the lower roll joints of the sleeve.
The inspections below the sleeve roll (and below the sleeve) are for the purposes of detecting any potential parent tube defects in this region since the sleeve interferes with the ability to detect degradation in the parent tube with the bobbin probe.
Enclosure
Approximately 21 percent of the tubes were examined with a +PointTM probe from the upper tube end to the upper tubesheet secondary face.
There is only one tube that has a non-stress relieved lower tubesheet roll expansion.
This tube was inspected with a rotating probe during the 2006 inspections.
The +PointTM and pancake coil examinations of the tubes bordering the sleeve region were performed at the 15th tube support and at the upper tubesheet secondary face.
Regarding the dent examinations, 100 percent of the dents greater than 2.5 volts and located below the 14th tube support plate were inspected with a rotating probe; 100 percent of the dents greater than 0.5 volts and located at or above the 14th tube support plate and located in the periphery of the tube bundle were inspected with a rotating probe; and 100 percent of the dents greater than 1.0 volt and located at or above the 14th tube support plate and located in the center of the tube bundle were inspected with a rotating probe. There are approximately 17 dents in each SG that are greater than 0.5 volts, located at or above the 14th tube support plate, and located in the periphery of the tube bundle.
Approximately 20 percent of the tubes in the sludge pile region were inspected with a rotating probe from the top of the sludge pile (typically approximately 3-inches above the lower tubesheet secondary face with a maximum of approximately 5-inches above the lower tubesheet secondary face) to 3-inches below the top of the lower tubesheet secondary face. These examinations focused on dented tubes and tubes with higher sludge pile heights. Automated data screening of the bobbin coil data is used to determine the sludge pile height. The region of the tube bundle where the sludge height for the majority of the tubes is in excess of 0.5-inches is designated as the sludge pile.
There are approximately 4000 tubes in the sludge pile region in each SG.
A +PointTM probe examination will be performed at the following locations exhibiting wear in order to monitor for the initiation of cracking: (1) all wear indications measuring greater than 20 percent through-wall, (2) all new indications classified as wear, and (3) indications of wear whose depth estimate has changed by more than 5 percent through-wall since the last inspection. There are approximately 300 wear indications in SG 1B and 485 wear indications in SG 2A.
There are 39 sleeves that were scored during installation. These sleeves are in SG 1B and are referred to as gross mean distortions. There are an additional three non-sleeved tubes that have ferrous deposits on the inside diameter of the tube. The deposits are a result of wire bristles that inadvertently entered these tubes in 2000 and subsequently oxidized to the point that only the corrosion products from the wire bristles remain. These tubes are also referred to as ?gross mean distortions, although the licensee may rename them in the future with a more descriptive name.
All hot-leg rolled plugs at Davis Besse are made from Alloy 690.
The visual inspection of the welded plugs is performed since some welded plugs had indications in 2002.
The visual inspection of the plugs in the upper and lower channel head includes looking for foreign material and tube-end damage.
Axial outside diameter stress corrosion cracking and intergranular attack (IGA) associated with grooves were found in several tubes. None of these indications are structurally significant and the number of indications were consistent with expectations.
All of these indications were found with the bobbin probe. Most of these indications are low voltage indications, located near the 15th tube support plate, and in the periphery of the tube bundle. This degradation mechanism (groove IGA) was first found in the 13th refueling outage in 2002 (approximately 3 or 4 indications were found in each SG). The indications found in the 2006 inspection are shallower than those found in 2002 in terms of the depth of degradation. The lengths of the indications found in 2006 are longer than those found in prior inspections. The results of these inspection are consistent with the expected probability of detection for this degradation mechanism.
Approximately 12 tubes in each SG will be repaired by re-rolling. This process will be employed to address indications in the upper tube end and in the roll transition in the upper tubesheet. Tubes will be stabilized, as necessary and all other crack indications (not repaired by re-rolling) will be plugged.
The number of indications in the tube ends was less than expected.
There were no potential loose part indications identified by eddy current examination in 2006. This is consistent with past inspections. No loose parts were found on the primary side of the SG and no evidence of new tube end damage was identified.
There were no secondary side inspections performed in 2006. The secondary side of the SG was maintained in wet layup during the outage. The last foreign object search and retrieval was performed in 2000, when chemical cleaning was performed.
The largest primary water stress corrosion crack indication at the roll transition measured 2.25 volts. This tube was last inspected in 2002. The accident induced leak rate for this indications is estimated at approximately 0.12 gallons per minute. Roll transition primary water stress corrosion cracking was first observed during the mid-cycle outage in 2005.
The circumferential indications found during this outage were located near the tube-to-tubesheet weld in the upper tubesheet or in the secondary shop roll in the lower tubesheet. Based on a preliminary evaluation, none of these circumferential indications are expected to structurally fail under the loads imposed during a large break loss of coolant accident and no leakage is expected from these indications. This information was provided in accordance with License Condition 2.C(7).
The volumetric indication that initiated from the outside diameter in the upper tubesheet is similar to indications detected previously.
The 2006 depth estimates for several wear indications were less than the 2005 depth estimates. This was attributed to technique and analyst variability.
No tube plugs are near their service-life limit as a result of tubesheet hole dilation.
Actions taken in response to NRC Information Notice 2002-02 (including supplement 1) were completed in the 2005 mid-cycle outage.
The replacement of the SGs is being pursued with a targeted installation date of 2014.
At the time of the call, Davis-Besse expected to be complete with the inspections and repairs in the SGs by March 25, 2006.
ATTACHMENT 1 Information provided by the Licensee regarding RFO14 Steam Generator Tube Inspections.
Davis-Besse Nuclear Power Station, Unit 1 cc:
Manager, Site Regulatory Compliance Attorney General FirstEnergy Nuclear Operating Company Office of Attorney General Davis-Besse Nuclear Power Station 30 East Broad Street Mail Stop A-DB-3065 Columbus, OH 43216 5501 North State Route 2 Oak Harbor, OH 43449-9760 President, Board of County Commissioners of Ottawa County Director, Ohio Department of Commerce Port Clinton, OH 43252 Division of Industrial Compliance Bureau of Operations & Maintenance President, Board of County 6606 Tussing Road Commissioners of Lucas County P.O. Box 4009 One Government Center, Suite 800 Reynoldsburg, OH 43068-9009 Toledo, OH 43604-6506 Regional Administrator The Honorable Dennis J. Kucinich U.S. Nuclear Regulatory Commission United States House of Representatives 801 Warrenville Road Washington, D.C. 20515 Lisle, IL 60523-4351 The Honorable Dennis J. Kucinich Resident Inspector United States House of Representatives U.S. Nuclear Regulatory Commission 14400 Detroit Avenue 5503 North State Route 2 Lakewood, OH 44107 Oak Harbor, OH 43449-9760 Gary R. Leidich Stephen Helmer President and Chief Nuclear Officer Supervisor, Technical Support Section FirstEnergy Nuclear Operating Company Bureau of Radiation Protection Mail Stop A-GO-19 Ohio Department of Health 76 South Main Street 35 East Chestnut Street, 7th Floor Akron, OH 44308 Columbus, OH 43215 Joseph J. Hagan Carol OClaire, Chief, Radiological Branch Senior Vice President of Operations and Ohio Emergency Management Agency Chief Operating Officer 2855 West Dublin Granville Road FirstEnergy Nuclear Operating Company Columbus, OH 43235-2206 Mail Stop A-GO-14 76 South Main Street Zack A. Clayton Akron, OH 44308 DERR Ohio Environmental Protection Agency David W. Jenkins, Attorney P.O. Box 1049 FirstEnergy Corporation Columbus, OH 43266-0149 Mail Stop A-GO-18 76 South Main Street State of Ohio Akron, OH 44308 Public Utilities Commission 180 East Broad Street Columbus, OH 43266-0573
Davis-Besse Nuclear Power Station, Unit 1 cc:
Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GHE-115 395 Ghent Road Akron, OH 44333 Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GHE-315 395 Ghent Road Akron, OH 44333 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Richard Anderson Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308