|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:FE NOCŽ WITHHOLD IN ACCORDANCE WITH 10 CFR 2.390(a)(4) | | {{#Wiki_filter:WITHHOLD IN ACCORDANCE WITH 10 CFR 2.390(a)(4) |
| WHEN SEPARATED FROM ENCLOSURE C, HANDLE THIS DOCUMENT AS DECONTROLLED RrstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor. Ohio 43449 Brian D. Boles Vice President, Nuclear January 23, 2017 L-17-026 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | | FENOC' WHEN SEPARATED FROM ENCLOSURE C, HANDLE THIS DOCUMENT AS DECONTROLLED 5501 North State Route 2 RrstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Brian D. Boles 419-321-7676 Vice President, Fax: 419-321-7582 Nuclear January 23, 2017 L-17-026 10 CFR 50 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 10 CFR 50 419-321-7676 Fax: 419-321-7582 MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years License Renewal Commitment 54, as amended by Davis-Besse Nuclear Power Station (Davis-Besse) | | |
| Updated Final Safety Analysis Report (UFSAR) Change Notice (UCN) 16-145, reads as follows: In response to MRP-227 A Applicant/Licensee Action Item 8, develop a schedule, with completion prior to the period of extended operation, for the update and submittal for NRG review and approval an evaluation for the period of extended operation regarding the effect of irradiation on the mechanical properties and deformation limits of the RV internals that was evaluated for the current term of operation ih Appendix E of Topical Report BAW-10008, Part 1, Revision 1 supplemented by DB-1 [Davis-Besse] | | Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years License Renewal Commitment 54, as amended by Davis-Besse Nuclear Power Station (Davis-Besse) Updated Final Safety Analysis Report (UFSAR) Change Notice (UCN) 16-145, reads as follows: |
| U[F]SAR Appendix 4A. The purpose of this letter is to submit the evaluation identified in License Renewal Commitment | | In response to MRP-227A Applicant/Licensee Action Item 8, develop a schedule, with completion prior to the period of extended operation, for the update and submittal for NRG review and approval an evaluation for the period of extended operation regarding the effect of irradiation on the mechanical properties and deformation limits of the RV internals that was evaluated for the current term of operation ih Appendix E of Topical Report BAW-10008, Part 1, Revision 1 supplemented by DB-1 [Davis-Besse] |
| : 54. The Enclosures listed below provide the Davis-Besse Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years: A. AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" B. AREVA Report ANP-3542NP, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Non-Proprietary)
| | U[F]SAR Appendix 4A. |
| | The purpose of this letter is to submit the evaluation identified in License Renewal Commitment 54. |
| | The Enclosures listed below provide the Davis-Besse Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years: |
| | A. AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" B. AREVA Report ANP-3542NP, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Non-Proprietary) |
| | |
| Davis-Besse Nuclear Power Station, Unit No. 1 L-17-026 Page2 C. AREVA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA} Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Proprietary) | | Davis-Besse Nuclear Power Station, Unit No. 1 L-17-026 Page2 C. AREVA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA} Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Proprietary) |
| AREVA Report ANP-3542P (Enclosure C) documents Davis-Besse reactor vessel internals TLAA analysis details that are considered proprietary information that is to be withheld from public disclosure pursuant to 10 CFR 2.390. A non-proprietary version of the document is provided as Enclosure B. Upon removal of Enclosure C, this letter can be decontrolled. | | AREVA Report ANP-3542P (Enclosure C) documents Davis-Besse reactor vessel internals TLAA analysis details that are considered proprietary information that is to be withheld from public disclosure pursuant to 10 CFR 2.390. A non-proprietary version of the document is provided as Enclosure B. Upon removal of Enclosure C, this letter can be decontrolled. |
| There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Patrick J. McCloskey, Manager-:- | | There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Patrick J. McCloskey, Manager-:- Regulatory Compliance, at (419) 321-7274. |
| Regulatory Compliance, at (419) 321-7274. | | Sincerely, |
| Sincerely, Brian D. Boles | | ~~~ |
| | Brian D. Boles |
|
| |
|
| ==Enclosures:== | | ==Enclosures:== |
|
| |
|
| A. AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" B. AREVA ReportANP-3542NP, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Non Proprietary) | | A. AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" B. AREVA ReportANP-3542NP, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Non Proprietary) * |
| * | | * C. AREVA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Proprietary) cc: w/o Enclosures NRC Region Ill Administrator NRR Project Manager NRC Resident Inspector Utility Radiological Safety Board |
| * C. AREVA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Proprietary) cc: w/o Enclosures NRC Region Ill Administrator NRR Project Manager NRC Resident Inspector Utility Radiological Safety Board Enclosure A Letter L-17-026 Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse) | | |
| AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" 3 pages follow COMMONWEAL TH OF VIRGINIA CITY OF LYNCHBURG | | Enclosure A Letter L-17-026 Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse) |
| *AFFIDAVIT SS. 1. My name is Tom Ryan. I am Manager, Product Licensing, for AREVA Inc. (AREVA) and as such I am authorized to execute this Affidavit.
| | AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" 3 pages follow |
| : 2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary. | | |
| I am familiar with the policies established by AREVA to ensure the proper application of these criteria. | | *AFFIDAVIT COMMONWEALTH OF VIRGINIA SS. |
| | CITY OF LYNCHBURG |
| | : 1. My name is Tom Ryan. I am Manager, Product Licensing, for AREVA Inc. |
| | (AREVA) and as such I am authorized to execute this Affidavit. |
| | : 2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary. I am familiar with the policies established by AREVA to ensure the proper application of these criteria. |
| : 3. I am familiar with the AREVA information contained in the AREVA document "ANP-3542P Revision 0, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years", and referred to herein as "Document." Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA Inc. for the control and protection of proprietary and confidential information. | | : 3. I am familiar with the AREVA information contained in the AREVA document "ANP-3542P Revision 0, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years", and referred to herein as "Document." Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA Inc. for the control and protection of proprietary and confidential information. |
| : 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential. | | : 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA and not made available to the public. |
| : 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. | | Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential. |
| The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information." 6. The following criteria are customarily applied by AREVA to determine whether information should be classified as proprietary: (a) The information reveals details of AREVA's research and development plans and programs or their results. (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service. (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a. competitive advantage for AREVA. (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability. (e) The information is vital to a competitive advantage held by ARE\(A, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA. The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(a), 6(c) and 6(d) above. 7. In accordance with AREVA's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA only as required and under suitable agreement providing for nondisclosure and limited use of the information. | | : 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in |
| : 8. AREVA policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis. 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief. \c:-th SUBSCRIBED before me this ..) ----dayof Sherry L. McFaden NOTARY PUBLIC, COMMONWEAL TH OF VIRGINIA MY COMMISSION EXPIRES: 10/31/18 Reg.# 7079129 SHERRY l. MCFADeN NoJlry Public Common\ivealth or Virginia 7079t29 My Comm111io11 | | |
| &xplr111 Oct 31, 2018 \ I}} | | accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information." |
| | : 6. The following criteria are customarily applied by AREVA to determine whether information should be classified as proprietary: |
| | (a) The information reveals details of AREVA's research and development plans and programs or their results. |
| | (b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service. |
| | (c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a. |
| | competitive advantage for AREVA. |
| | (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability. |
| | (e) The information is vital to a competitive advantage held by ARE\(A, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA. |
| | The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(a), 6(c) and 6(d) above. |
| | : 7. In accordance with AREVA's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA only as required and under suitable agreement providing for nondisclosure and limited use of the information. |
| | : 8. AREVA policy requires that proprietary information be kept in a secured file or I |
| | area and distributed on a need-to-know basis. |
| | : 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief. |
| | c:-th SUBSCRIBED before me this |
| | -\ - |
| | ..) |
| | -- |
| | dayof ~~1 2016.* |
| | Sherry L. McFaden NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 10/31/18 Reg.# 7079129 SHERRY l. MCFADeN NoJlry Public Common\ivealth or Virginia 7079t29 My Comm111io11 &xplr111 Oct 31, 2018 |
| | \}} |
|
|---|
Category:Letter type:L
MONTHYEARL-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
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
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
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
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023
Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002
L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023
CFR 50.55a Request RP-5 Regarding Inservice Pump Testing
L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023
Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023
Energy Harbor Nuclear Corp Retrospective Premium Guarantee
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023
Submittal of Pressure and Temperature Limits Report, Revision 5
L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022
Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)
L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022
Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022
Submittal of Pressure and Temperature Limits Report. Revision 4
L-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022
Occupational Radiation Exposure Report for Year 2021 - Correction
L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022
Submittal of the Updated Final Safety Analysis Report, Revision 34
L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022
Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events
L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022
Submittal of Evacuation Time Estimates
L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022
Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual
L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022
Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan
L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022
Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report
L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022
2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022
Post Accident Monitoring Report
L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022
Readiness for NRC Supplemental Inspection Required for a White Finding
L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022
Withdrawal of Proposed Inservice Inspection Alternative RR-A2
L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022
Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage
L-22-102, Report of Facility Changes, Tests, and Experiments2022-05-16016 May 2022
Report of Facility Changes, Tests, and Experiments
L-22-092, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 20212022-05-16016 May 2022
Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2021
L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022
Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building
L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 12022-05-10010 May 2022
Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1
L-22-127, Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding2022-05-0606 May 2022
Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding
L-22-089, Occupational Radiation Exposure Report for Year 20212022-04-12012 April 2022
Occupational Radiation Exposure Report for Year 2021
L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022
Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage
L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022
Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3
L-22-074, Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-15015 March 2022
Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
L-22-061, Ile Post Exam Letter L-22-0612022-02-24024 February 2022
Ile Post Exam Letter L-22-061
L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022
Retrospective Premium Guarantee
L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022
Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2
L-20-289, Emergency Plan Amendment Request2022-01-19019 January 2022
Emergency Plan Amendment Request
L-21-290, Response to NRC Inspection Report 05000346/2021091, EA-21-1762021-12-21021 December 2021
Response to NRC Inspection Report 05000346/2021091, EA-21-176
2023-09-12
[Table view]
Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-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
CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML22277A6012022-10-14014 October 2022
Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure
L-20-163, License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications2020-07-27027 July 2020
License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications
L-20-188, ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names2020-06-26026 June 2020
ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names
L-19-233, License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b2019-11-14014 November 2019
License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b
L-19-219, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-09-25025 September 2019
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019
ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML19130A1952019-05-0808 May 2019
Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition
L-19-073, ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-04-26026 April 2019
ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-19-062, Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition2019-02-27027 February 2019
Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition
L-18-271, License Amendment Request - Proposed Post-Shutdown Emergency Plan2019-02-0505 February 2019
License Amendment Request - Proposed Post-Shutdown Emergency Plan
L-18-242, License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition2019-02-0505 February 2019
License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition
L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-11-20020 November 2018
Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805
L-18-254, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2018-10-22022 October 2018
License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition
L-18-203, Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2018-08-23023 August 2018
Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement
L-17-159, Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2017-05-18018 May 2017
Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement
L-17-026, Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years2017-01-23023 January 2017
Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years
L-16-304, Supplement to Request for License Amendment Approval Delay2016-10-25025 October 2016
Supplement to Request for License Amendment Approval Delay
L-16-020, Request for Licensing Action to Revise the Emergency Plan2016-02-17017 February 2016
Request for Licensing Action to Revise the Emergency Plan
L-16-030, Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program.2016-02-0909 February 2016
Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program.
L-15-341, License Amendment Request to Modify Technical Specifications 5.3.12015-11-19019 November 2015
License Amendment Request to Modify Technical Specifications 5.3.1
L-15-309, License Renewal Application Amendment No. 602015-10-0606 October 2015
License Renewal Application Amendment No. 60
L-15-214, License Renewal Application Amendment No. 59 - Annual Update2015-06-29029 June 2015
License Renewal Application Amendment No. 59 - Annual Update
L-15-192, Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 582015-06-12012 June 2015
Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 58
L-15-166, Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 562015-05-20020 May 2015
Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 56
L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 552015-04-0808 April 2015
Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55
L-15-117, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2015-04-0101 April 2015
License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements
L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program2014-12-19019 December 2014
Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program
L-14-297, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 532014-09-16016 September 2014
Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 53
L-14-206, License Renewal Application Amendment No. 50 - Annual Update2014-06-23023 June 2014
License Renewal Application Amendment No. 50 - Annual Update
L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 482014-02-19019 February 2014
License Renewal Application (TAC No. ME4640) Amendment No. 48
L-13-330, License Renewal Application Amendment No. 46 - Annual Update2013-09-20020 September 2013
License Renewal Application Amendment No. 46 - Annual Update
L-12-397, Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest2013-02-19019 February 2013
Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest
L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..2013-01-18018 January 2013
License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..
ML12229A1392012-08-0909 August 2012
License Renewal Application Amendment 30 - Annual Update
L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels2012-05-23023 May 2012
License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels
ML1126402462011-09-20020 September 2011
License Amendment Request to Change the Name of an Owner Licensee to Firstenergy Nuclear Generation, LLC
L-11-097, License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program.2011-05-20020 May 2011
License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program.
ML1024505632010-08-31031 August 2010
Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Section 3.5 Through Appendix E, References 2.3-1
L-10-221, Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.112010-08-31031 August 2010
Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.11
L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation.2009-06-0202 June 2009
License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation.
L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr.2009-04-15015 April 2009
License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr.
L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009
ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.
L-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD63982008-05-16016 May 2008
Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398
ML0814804712008-05-16016 May 2008
Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features
ML0814804692008-05-16016 May 2008
Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems
ML0814804682008-05-16016 May 2008
Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS)
ML0814804672008-05-16016 May 2008
Improved Technical Specification Conversion License Amendment Request, Volume 7, (Revision 1), Section 3.2 - Power Distribution Limits
ML0814804662008-05-16016 May 2008
Improved Technical Specification Conversion License Amendment Request, Volume 6, (Revision 1), Section 3.1 - Reactivity Control Systems
2023-09-12
[Table view] |
Text
WITHHOLD IN ACCORDANCE WITH 10 CFR 2.390(a)(4)
FENOC' WHEN SEPARATED FROM ENCLOSURE C, HANDLE THIS DOCUMENT AS DECONTROLLED 5501 North State Route 2 RrstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Brian D. Boles 419-321-7676 Vice President, Fax: 419-321-7582 Nuclear January 23, 2017 L-17-026 10 CFR 50 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years License Renewal Commitment 54, as amended by Davis-Besse Nuclear Power Station (Davis-Besse) Updated Final Safety Analysis Report (UFSAR) Change Notice (UCN)16-145, reads as follows:
In response to MRP-227A Applicant/Licensee Action Item 8, develop a schedule, with completion prior to the period of extended operation, for the update and submittal for NRG review and approval an evaluation for the period of extended operation regarding the effect of irradiation on the mechanical properties and deformation limits of the RV internals that was evaluated for the current term of operation ih Appendix E of Topical Report BAW-10008, Part 1, Revision 1 supplemented by DB-1 [Davis-Besse]
U[F]SAR Appendix 4A.
The purpose of this letter is to submit the evaluation identified in License Renewal Commitment 54.
The Enclosures listed below provide the Davis-Besse Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years:
A. AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" B. AREVA Report ANP-3542NP, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Non-Proprietary)
Davis-Besse Nuclear Power Station, Unit No. 1 L-17-026 Page2 C. AREVA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA} Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Proprietary)
AREVA Report ANP-3542P (Enclosure C) documents Davis-Besse reactor vessel internals TLAA analysis details that are considered proprietary information that is to be withheld from public disclosure pursuant to 10 CFR 2.390. A non-proprietary version of the document is provided as Enclosure B. Upon removal of Enclosure C, this letter can be decontrolled.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Patrick J. McCloskey, Manager-:- Regulatory Compliance, at (419) 321-7274.
Sincerely,
~~~
Brian D. Boles
Enclosures:
A. AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" B. AREVA ReportANP-3542NP, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Non Proprietary) *
- C. AREVA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" (Proprietary) cc: w/o Enclosures NRC Region Ill Administrator NRR Project Manager NRC Resident Inspector Utility Radiological Safety Board
Enclosure A Letter L-17-026 Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse)
AREVA Affidavit to Support the Disclosure Request for the Proprietary AREVA TLAA Report ANP-3542P, "Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years" 3 pages follow
CITY OF LYNCHBURG
- 1. My name is Tom Ryan. I am Manager, Product Licensing, for AREVA Inc.
(AREVA) and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by AREVA to determine whether certain AREVA information is proprietary. I am familiar with the policies established by AREVA to ensure the proper application of these criteria.
- 3. I am familiar with the AREVA information contained in the AREVA document "ANP-3542P Revision 0, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years", and referred to herein as "Document." Information contained in this Document has been classified by AREVA as proprietary in accordance with the policies established by AREVA Inc. for the control and protection of proprietary and confidential information.
- 4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by AREVA and not made available to the public.
Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
- 5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in
accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
- 6. The following criteria are customarily applied by AREVA to determine whether information should be classified as proprietary:
(a) The information reveals details of AREVA's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a.
competitive advantage for AREVA.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for AREVA in product optimization or marketability.
(e) The information is vital to a competitive advantage held by ARE\(A, would be helpful to competitors to AREVA, and would likely cause substantial harm to the competitive position of AREVA.
The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(a), 6(c) and 6(d) above.
- 7. In accordance with AREVA's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside AREVA only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. AREVA policy requires that proprietary information be kept in a secured file or I
area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
c:-th SUBSCRIBED before me this
-\ -
..)
--
dayof ~~1 2016.*
Sherry L. McFaden NOTARY PUBLIC, COMMONWEALTH OF VIRGINIA MY COMMISSION EXPIRES: 10/31/18 Reg.# 7079129 SHERRY l. MCFADeN NoJlry Public Common\ivealth or Virginia 7079t29 My Comm111io11 &xplr111 Oct 31, 2018
\
