|
---|
Category:Letter
MONTHYEARML24303A3282024-10-29029 October 2024 Information Request for the Cyber Security Baseline Inspection Identification to Perform Inspection ML24281A0662024-10-0404 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 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-24-072, 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-24-111, 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-24-031, 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 ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) IR 05000346/20230062024-02-28028 February 2024 Re-Issue 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 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 2024-09-06
[Table view] Category:Memoranda
MONTHYEARML23129A6062023-05-0404 May 2023 Special Inspection Team Charters to Evaluate the Circumstances Surrounding the Ground Settling at the Davis-Besse Nuclear Power Station ML23044A3662023-02-15015 February 2023 Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III ML21096A2282021-03-30030 March 2021 FEMA Disapproval of Davis-Besse Exercise Exemption ML19182A3562019-07-23023 July 2019 Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019 ML19162A0102019-06-0707 June 2019 Memorandum to File Environmental Assessment and Finding of No Significant Impact for Firstenergy Nuclear Operating Company'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(B) and 72.30(C) for Davis Besse ISFSI ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML15205A1692015-08-0707 August 2015 ACRS Review of the Davis Besse Nuclear Plant LRA - Transmittal of the Sser ML15182A1912015-07-16016 July 2015 Annual Financial Test for a Parent Company Guarantee Given by Firstenergy Solutions Corporation and Firstenergy Corporation 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 IR 05000334/20004122014-07-0808 July 2014 NRC Staff'S Spot-Check Review of First Energy Nuclear Operating Company'S Ownership Interest in Beaver Valley, Units 1 and 2, Perry, and Davis-Besse, Docket No. 05000334, 05000412, 05000440, and 05000346, on June 10, 2014-Finding of No Pote 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 ML13280A9062013-10-21021 October 2013 Forthcoming Meeting with Firstenergy Nuclear Operating Company (FENOC) to Discuss Voluntary Risk Informed Fire Protection Amendment for Davis-Besse ML13142A5122013-07-0202 July 2013 Summary of Telephone Conference Call Held on May 21, 2013, Between NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station, LRA ML13171A2922013-06-13013 June 2013 LTR-13-0540 - Bill Hawkins and Vinod Arora Email San Onofre Nuclear Generating Station (SONGS) Lessons Learn for Davis-Besse ML13154A4442013-06-0404 June 2013 Rai'S Following Ifib Analysis of Fenoc'S 2013 Decommissioning Funding Status Report for Davis-Besse and Perry ML12199A2072012-07-17017 July 2012 Public Meeting Notice to Discuss the 2011 End-of-Cycle Performance Assessment ML12158A4002012-06-0808 June 2012 6/26/2012 Forthcoming Meeting Firstenergy Nuclear Operating Company (FENOC) ML1206901652012-03-0909 March 2012 Memo - Summary of Public Meeting with Industry Regarding Pwrog'S Boric Acid Corrosion Test Program ML12018A1652012-01-27027 January 2012 Summary of Telephone Conference Call Held on November 9, 2011, Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, LRA ML14028A5462012-01-25025 January 2012 NRC Telecon Regarding Davis-Besse License Renewal Severe Accident Mitigation Alternatives Analysis Questions ML11363A1712012-01-23023 January 2012 Summary of Telephone Conference Call Held on December 12, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Request for Additional Information ML11355A0952011-12-29029 December 2011 Summary of Telephone Conference Call Held on December 8, 2011, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning RAIs Pertaining to the Davis-Besse Nuclear Power Station, LRA ML11348A0212011-12-21021 December 2011 Summary of Telephone Conference Call Held on November 1, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis Besse Nuclear Pow ML11341A1182011-12-14014 December 2011 Summary of Telephone Conference Call Held on June 15, 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 ML11339A0862011-12-13013 December 2011 Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning RAIs Pertaining to the Davis-Besse Nuclear Power Station LRA ML11327A0082011-12-0202 December 2011 Summary of Telephone Conference Call Held on September 29, 2011, Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, LRA 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 ML11327A0872011-12-0202 December 2011 Summary of Telephone Conference Call Held on July 27, 2011, Between the NRC and Firstenergy Nuclear Operating Company Concerning RAI Pertaining to the Davis-Besse, LRA ML11279A2182011-10-0606 October 2011 Memo - Task Interface Agreement - Evaluation of Compliance with Code for Examination of Flange Stud Holes on the Replacement Vessel Head at the Davis-Besse Nuclear Power Station (TIA 2011-015) ML11242A0032011-09-12012 September 2011 Summary of Conference Call Held on August 4, 2011, Between the NRC and FENOC Concerning Requests for Additional Information Pertaining to the Davis-Besse License Renewal Application ML1122701392011-08-15015 August 2011 Request for Additional Information Response Clarification from Davis-Besse Nuclear Power Station in Support of License Renewal Application Review ML11173A2002011-08-0101 August 2011 Summary of Public Scoping Meetingsconducted Related to the Review of the Davis-Besse Nuclear Power Station, Unit 1, LRA ML11193A2032011-07-26026 July 2011 Final Response to TIA 2011-001, Davis-Besse Nuclear Power Station Safety-Related Batteries Electrical Separation Design and Licensing Bases ML11174A2322011-06-21021 June 2011 for the Record-06-21-2011: NRC Ensures Public Safety Through Rigorous Oversight of Nuclear Power Plant Safety Standards ML1108202762011-06-0303 June 2011 Summary of Site Audit Related to the Review of the License Renewal Application for Davis-Besse Nuclear Power Station, Unit 1 ML11174A2472011-05-31031 May 2011 for the Record-05-31-2011: NRC Chairman Gregory B. Jaczko'S Statement on Nrc'S Commitment to Safety ML1110806902011-04-20020 April 2011 Notice of Meeting with First Energy Nuclear Operating Company (FENOC) to Discuss a Proposed LAR to Delete Technical Specification 5.5.8g, Steam Generator (SG) Program Auxiliary Feedwater Header Inspections ML1028702612010-10-22022 October 2010 11/04/10 Notice of Meeting to Discuss the License Renewal Process and Environmental Scoping for Davis-Besse Nuclear Power Station License Renewal Application Review ML1029106182010-10-14014 October 2010 Documentation of Telephone Conversation Between Mr. David Lochbaum Regarding Follow-Up Questions Related to NRC Letter Dated July 28, 2010 (ML102040807) ML1028503032010-10-12012 October 2010 Acceptance of License Renewal Application, Davis-Besse Nuclear Power Station ML0935101922009-12-14014 December 2009 Completion of Davis-Besse Lessons Learned Task Force Recommendation 3.3.4(8) ML0825606772008-09-15015 September 2008 Presentation Disc ML0814207532008-05-20020 May 2008 Summary of Public Meeting with Firstenergy Nuclear Operating Company to Discuss the 2008 Davis-Besse End-of-Cycle Performance Assessment ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0723302222007-08-28028 August 2007 09/12/2007 Notice of Meeting with Firstenergy to Discuss the August 3, 2007 License Amendment Request for Conversion to Improved Technical Specifications for Davis-Besse, Unit 1 ML0722108432007-08-0707 August 2007 Request for Renewal of Deviation to the Reactor Oversight Process Action Matrix for Davis-Besse Nuclear Power Station ML0717103462007-06-21021 June 2007 Revised Notice of Meeting with Firstenergy to Discuss Response to Nrc'S 05/14/2007, Demand for Information Regarding Fenoc'S Re-analysis of the Timeline and Root Causes for the 2002 Davis-Besse Reactor Pressure Vessel Head Degradation Event ML0716202122007-06-13013 June 2007 Notice of Meeting with Firstenergy Regarding May 14, 2007 Demand for Information Davis-Besse ML0712803322007-05-18018 May 2007 April 2007 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations (10 Cfr), Section 2.206 2023-05-04
[Table view] |
Text
D A -f-V-A subsimn of Pnmndr West Canlal Corpmhm*
DATE: 03/21/02 Company Correspondence L*tw# 476-00348-MJW/MAM TO: C. D. Mauldin Sta. # 7605 Ext.# 82-5553 FROM M. J. Winsor Sta. # 7669 Ext. # 82-5102
SUBJECT:
RVH CEDM NOZZLE EXAMINATIONS The following is a description of our CEDM Nozzle inspection plan in response to NRC Bulletin 2001-01. The plan has been refined due to the recent boric acid corrosion issue at Davis Besse and resulting NRC Bulletin 2002-01 concerning Reactor Vessel head degradation.
The current under-the-head inspections call for inspecting 97 CEDM nozzles with remote tooling using a combination of surface eddy current (ET) and volumetric ultrasonic (UT) techniques. The ET scans will be applied from the ID of the nozzle using Westinghouse's open probe scanner. The UT will also be applied from the ID with the same scanner. The ET and UT scans will be performed at the samn time and gives us the capability of examining the ID and OD nozzle wall. The scan area includes all wetted surfaces below the j-weld and up to two (2) inches above the j-weld.
The UT technique has been refined to include two zero degree transducers with different gain settings to capture near surface and j-weld crack indications. The Westinghouse NDE techniques have been qualified using the Entergy/EPRI nozzle mock-up.
In response to Bulletin 2002-01, potential or through-wall crack indications in the nozzle at or above the j-weld area will require additional examinations:
- 1) Full length UT of the nozzle OD to assess nozzle OD cracking
- 2) Low Frequency eddy current interference fit NDE to assess potential bore corrosion (currently under final qualification)
- 3) Top of head visual examination for leakage if the nozzle is accessible. It is expected that the bore assessment using ET may justify us to not perform a top head visual fbr inaccessible nozzles.
Indications in the j-weld, or potential indications will result in the j-weld being surface ET examined using the Westinghouse ,grooveman" tool. This will allow confirmation of any crack defect.
If there is no confirmation of a linear defect, then the weld is considered acccptable;
If there is a confirmed weld defect, then further examination is required before repairs may commence. The further examinations include:
- 1) Full length UT of the nozzle to assess the OD of the nozzle;
- 2) Low Frequency eddy current interference fit NDE to assess potential bore corrosion;
- 3) Top of head visual examination for leakage if the nozzle is accessible. It is expected that the bore assessment using ET mayjustify us to not perform a top bead visual for inaccessible nozzles.
Note that weld cracks are not planned for excavation for depth sizing, therefor, we are assuming through-wall extension and performing NDE to asses potential damage to the nozzle OD and to the Bore. We have the capability to perform deep crack repair, however, the evolution is expected to be very dose intensive.
The additional examinations have been incorporated into the schedule adding time to "special interest" testing. APS Engineering personnel will have the final approval repair recommendations associated with the reactor of all NDE data and vessel head penetration examinations.
There have been no changes to the current vent line inspection plan, which is 1: perform visual exam from the top of the vessel head, or 2: perform under the head ultrasonic examinations. If the top of head visual examination can be performed and if acceptable, then no under the head examination for the vent nozzle will be performed. The visual examination is the preferred method based on machining necessary to access the vent nozzle from under the head and the resulting limited examination area due the EDM machining. In addition, inspection experience to-date, including European cxpcrience, has shown no vent line leakage due to primary water stress corrosion cracking.
Therefore, Engineering believes top of-head visual examination to be justified.
Note that should top-of-head visual examinations become necessary in light of equipment reliability issues with Westinghouse equipment, then any nozzles with indications of leakage will need to be addressed individually for damage as.sessment.
Any questions or comments please let me know.
MJW/MAM Ce. 0. Overbeck J. Hessser J. Compas D. Weber M. Powell D. Smith J. Gaffney C. Seaman D. Hansen D. Fan S. Bauer T. Weber S. Bums
P T
.PENETRATION TUBE OD FLAWS EVALUATION No
0 PWSCC TYPE SIGNALS Lin= in ono direction, TOF like in the other hyperboli ecNNnamic imadnaai ampliude, does not follow weld ilrerfaee OR Linrrcgion with loss of blackwall fur PWSCC >0.5- dcep from OD False positives can be caused by Weld repmirs S Reflective weld inter-face gin stnrtu=
0 I.& of fusion Suspect signals are categorized as:
Special interest fbr additional surface inspection on the J groove weld surface PWSCC, by definition must stmn on a wetted surface. The tube ID & OD surface flaws are detected with the open housing probe. l'he J groove weld surface exam is performed with the groovem an ET somner.
FENETRTION TUBE lp FLAW EVALUATION 0/0 ;;Rp,-j 010
'ml -