Letter Sequence Supplement |
---|
TAC:MF0536, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection (Approved, Closed) |
|
MONTHYEARL-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.. Project stage: Request ML13044A7652013-02-13013 February 2013 NRR E-mail Capture - Acceptance Review for Davis-Besse LAR to Revise TS 3.4.17, TS 3.7.18, TS 5.5.8, and TS 5.6.6 - TAC No. MF0536 Project stage: Acceptance Review ML13234A3902013-08-29029 August 2013 Request for Additional Information Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) Project stage: RAI L-13-302, Reply to Request for Additional Information Related to Steam Generator Inventory Change2013-09-27027 September 2013 Reply to Request for Additional Information Related to Steam Generator Inventory Change Project stage: Response to RAI ML13311B1932013-11-14014 November 2013 Request for Additional Information Related to Steam Generator Inventory Change Project stage: RAI L-13-373, Reply to Request for Additional Information Related to Steam Generator Inventory Change2013-12-13013 December 2013 Reply to Request for Additional Information Related to Steam Generator Inventory Change Project stage: Response to RAI L-13-404, Supplemental Information Related to Steam Generator Inventory Change2014-01-10010 January 2014 Supplemental Information Related to Steam Generator Inventory Change Project stage: Supplement ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) Project stage: Approval 2013-02-13
[Table View] |
|
---|
Category:Letter type:L
MONTHYEARL-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 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 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 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 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 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-23-101, 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-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection 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-22-092, 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-22-102, Report of Facility Changes, Tests, and Experiments2022-05-16016 May 2022 Report of Facility Changes, Tests, and Experiments 2024-07-08
[Table view] |
Text
FENOC b50 1 Nortf! Sratc Route?
Oak hCJrbor. O!no .JJ.M9 FirstEnergy Nuclear Raymond A Lieb Vrce Prc:sJcJcmt. Nuclear January 10, 2014 L-13-404 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 Supplemental Information Related to Steam Generator Inventory Change (TAC No. MF0536)
By letter dated January 18, 2013 (Agencywide Documents Access and Management System Accession No. ML13018A350), FirstEnergy Nuclear Operating Company (FENOC) submitted an application for amendment of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The proposed amendment would revise Technical Specifications in support of the steam generator replacement scheduled for the DBNPS spring 2014 refueling outage.
By telephone conversation with the Nuclear Regulatory Commission (NRC) staff on December 18, 2013, FENOC provided additional clarification regarding analyses performed to provide predictions of once through steam generator performance.
Additional information in support of that clarification is attached.
There are no regulatory commitments contained in this letter. If there are any questions, or if additional information is required, please contact Mr. Thomas A. Lentz, Manager- Fleet Licensing, at 330-315-6810.
I declare unqer penalty of perjury that the foregoing is true and correct. Executed on January ;0)~2014.
Davis-Besse Nuclear Power Station L-13-404 Page 2
Attachment:
Supplemental Information Related to Steam Generator Inventory Change cc: Regional Administrator- NRC Region Ill NRC Project Manager NRC Resident Inspector Executive Director - Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
Attachment L-13-404 Supplemental information Related to Steam Generator Inventory Change Page 1 of 1 Predictions of once-through-steam-generator (OTSG) performance were provided using a one-dimensional computer code that was developed to solve thermal-hydraulic equations in the tube bundle region.
The secondary side of the OTSG is divided into a set of nodes that extend from the upper face of the lower tubesheet to the secondary face of the upper tubesheet. The thermal hydraulic conditions are predicted for each of these nodes. The overall heat transfer coefficient is determined using the appropriate thermal-hydraulic conditions for both the primary and secondary sides of the tubes. The overall heat transfer coefficient accounts for the heat transfer coefficient on the primary and secondary side and the conductivity through the tube wall. The analysis uses appropriate heat transfer, pressure drop, and two-phase correlations to calculate output results at each node, including velocity, temperature, density, steam quality, and pressure drop.
For use in determining inventory, the density results for each grid node in the bundle region are multiplied by the secondary side flow area and the height of the control volume corresponding to the grid node. The total inventory within the bundle region is the sum of all control volume inventories.
The steam annulus inventory is calculated by multiplying the tube bundle outlet density and the steam annulus total volume. The downcomer inventory is determined based on the saturation densities and specified Operating Range water level.