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Category:Report
MONTHYEARL-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-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-22-211, 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-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.... ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments ML17026A0082016-12-31031 December 2016 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) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In ML14353A0602014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 ML13340A1592013-11-26026 November 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1472013-11-26026 November 2013 Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0 ML13340A1632013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G ML13340A1622013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1602013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13135A2452012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379 ML13135A2442012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379 ML13135A2432012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2422012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176 2023-08-07
[Table view] Category:Technical
MONTHYEARL-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-22-211, 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-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years ML17026A0082016-12-31031 December 2016 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) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. ML13008A0612012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-By Checklists, Sheet 21 of 139 Through End L-15-328, Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 72012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 7 ML15299A1502012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 6 of 7 ML15299A1492012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 5 of 7 ML15299A1482012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 4 of 7 ML15299A1472012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 3 of 7 ML15299A1462012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 2 of 7 ML15299A1442012-07-30030 July 2012 Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 1 of 7 ML12209A2602012-07-26026 July 2012 Attachment 31, Fauske & Associates, Inc. Technical Bulletin No. 1295-1, BWR MSIV Leakage Assessment: NUREG-1465 Vs. MAAP 4.0.2 ML1017400422010-06-0404 June 2010 0800368.407, Rev. 0, Summary of Design and Analysis of Weld Overlays for Reactor Coolant Pump Suction and Discharge, Cold Leg Drain, and Core Flood Nozzle Dissimilar Metal Welds for Alloy 600 Primary Water Stress Corrosion Cracking Mitigati L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds2010-04-25025 April 2010 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds ML1002501322010-01-11011 January 2010 0800368.404, Revision 1, Leak-Before-Break Evaluation of Reactor Coolant Pump Suction and Discharge Nozzle Weld Overlays for Davis-Besse Nuclear Power Station, Enclosure B ML11301A2222008-12-0101 December 2008 Reference: Combined Heat and Power Effective Energy Solutions for a Sustainable Future ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 L-08-105, Reactor Head Inspection Report2008-04-11011 April 2008 Reactor Head Inspection Report L-08-005, Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse2008-01-27027 January 2008 Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse ML0726105652007-09-17017 September 2007 Confirmatory Order, 2007 Independent Assessment of Corrective Action Program (FENOC) ML0708602802007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 10. the Unique Nature of the Davis-Besse Nozzle 3 Crack and the RPV Head Wastage Cavity ML0708602762007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 9. Cfd Modeling of Fluid Flow in CRDM Nozzle and Weld Cracks and Through Annulus ML0708602712007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 8. Stress Analysis and Crack Growth Rates for Davis-Besse CRDM Nozzles 2 and 3 ML0708602682007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 7. FENOC/Davis-Besse Response to CRDM Cracking and Boric Acid Corrosion Issues ML0708602612007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 5. Worldwide Industry Response to CRDM and Other Alloy 600 Nozzle Cracking ML0708602562007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 4. the Davis-Besse March 2002 Event ML0708602532007-03-15015 March 2007 Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 3. Background 2023-01-10
[Table view] |
Text
Enclosure F L-22-141 Areva document 32-9344638-000 Updated inputs to 52 EFPY P-T Operating Curves.
(32 Pages Follow)
0402-01-F01 (Rev. 021, 03/12/2018)
PROPRIETARY CALCULATION
SUMMARY
SHEET (CSS)
Document No. 32 - 9344638 - 000 Safety Related: Yes No Title Updated Inputs to 52 EFPY P-T Operating Curves PURPOSE AND
SUMMARY
OF RESULTS:
The purpose of this calculation is to provide a Non-Proprietary version of Reference [1].
The purpose of Reference [1] is to generate inputs to the procedural NDT/LTOP limits using the location corrected NDT/LTOP PT curves from Reference [2] and the uncertainties in pressure and temperature measurement from Reference [3].
The results of Reference [1] are presented in Section 4.
FRAMATOME INC. PROPRIETARY This document and any information contained herein is the property of Framatome Inc. (Framatome) and is to be considered proprietary and may not be reproduced or copied in whole or in part. This document shall not be furnished to others without the express written consent of Framatome and is not to be used in any way which is or may be detrimental to Framatome. This document and any copies that may have been made must be returned to Framatome upon request.
If the computer software used herein is not the latest version per the EASI list, THE DOCUMENT CONTAINS AP 0402-01 requires that justification be provided.
ASSUMPTIONS THAT SHALL BE THE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT: VERIFIED PRIOR TO USE CODE/VERSION/REV CODE/VERSION/REV Yes No Page 1 of 32
0402-01-F01 (Rev. 021, 03/12/2018)
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Review Method: Design Review (Detailed Check)
Alternate Calculation Does this document establish design or technical requirements? YES NO Does this document contain Customer Required Format? YES NO Signature Block P/R/A/M Name and Title and Pages/Sections (printed or typed) Signature LP/LR Date Prepared/Reviewed/Approved Trevor Connell, TD CONNELL LP ALL Engineering Supervisor 4/7/2022 Pascal Brocheny, PO BROCHENY LR ALL Advisory Engineer 4/7/2022 Darren Wood, DH WOOD A ALL Engineering Manager 4/8/2022 Notes: P/R/A designates Preparer (P), Reviewer (R), Approver (A);
LP/LR designates Lead Preparer (LP), Lead Reviewer (LR);
M designates Mentor (M)
In preparing, reviewing and approving revisions, the lead preparer/reviewer/approver shall use All or All except
___ in the pages/sections reviewed/approved. All or All except ___ means that the changes and the effect of the changes on the entire document have been prepared/reviewed/approved. It does not mean that the lead preparer/reviewer/approver has prepared/reviewed/approved all the pages of the document.
With Approver permission, calculations may be revised without using the latest CSS form. This deviation is permitted when expediency and/or cost are a factor. Approver shall add a comment in the right-most column that acknowledges and justifies this deviation.
Project Manager Approval of Customer References and/or Customer Formatting (N/A if not applicable)
Name Title (printed or typed) (printed or typed) Signature Date Comments Beverly Watson Project Manager BJ WATSON 4/8/2022 Page 2
0402-01-F01 (Rev. 021, 03/12/2018)
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Record of Revision Revision Pages/Sections/Paragraphs No. Changed Brief Description / Change Authorization 000 ALL Non-Proprietary version of 32-9271138-001.
Page 3
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Table of Contents Page SIGNATURE BLOCK................................................................................................................................ 2 RECORD OF REVISION .......................................................................................................................... 3 LIST OF TABLES ..................................................................................................................................... 5 LIST OF FIGURES ................................................................................................................................... 6 1.0 PURPOSE ..................................................................................................................................... 7 2.0 ANALYTICAL METHODOLOGY ................................................................................................... 7 3.0 ASSUMPTIONS ............................................................................................................................ 8 3.1 Unverified Assumptions ..................................................................................................... 8 3.2 Justified Assumptions ........................................................................................................ 8 4.0 CALCULATIONS ........................................................................................................................... 9 4.1 NDT Limit Curves............................................................................................................... 9 4.2 LTOP Limit Curves...........................................................................................................22 4.3 Surge Line Limit ...............................................................................................................23
5.0 REFERENCES
............................................................................................................................32 Page 4
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves List of Tables Page Table 2-1: Summary of Inputs.................................................................................................................. 7 Table 2-2: Nomenclature ......................................................................................................................... 8 Table 4-1: Normal Heatup (PI-RC2A4 or PI-RC2B4).............................................................................10 Table 4-2: ISLH Heatup (PI-RC2A4 or PI-RC2B4) ................................................................................13 Table 4-3: Normal Cooldown (PI-RC2A4 or PI-RC2B4) ........................................................................16 Table 4-4: ISLH Cooldown (PI-RC2A4 or PI-RC2B4)............................................................................19 Table 4-5: 10 EFPY and 52 EFPY P-T Limit Comparison .....................................................................23 Table 4-6: Surge Line Limits ..................................................................................................................23 Page 5
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves List of Figures Page Figure 4-1: Normal Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4).......................................24 Figure 4-2: Normal Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4).......................................25 Figure 4-3: ISLH Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4) ...........................................26 Figure 4-4: ISLH Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4) ..........................................27 Figure 4-5: Normal Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4) ................................................................................................................................. 28 Figure 4-6: Normal Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4) ................................................................................................................................. 29 Figure 4-7: ISLH Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4) ................................................................................................................................. 30 Figure 4-8: ISLH Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4) ................................................................................................................................. 31 Page 6
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves 1.0 PURPOSE The purpose of this calculation is to provide a Non-Proprietary version of Reference [1]. The content is identical to Reference [1], which includes the original revision levels of the calculation references at the time the document was approved.
The purpose of Reference [1] is to generate inputs to the procedural NDT/LTOP limits using the location corrected NDT/LTOP PT curves from Reference [2] and the uncertainties in pressure and temperature measurement from Reference [3].
The results of Reference [1] are presented in Section 4.
2.0 ANALYTICAL METHODOLOGY The calculation is performed by applying the appropriate pressure and temperature measurement uncertainties from Reference [3] to the location corrected PT limits developed in Reference [2]. Table 2-1 presents a summary of the inputs used in this calculation.
Table 2-1: Summary of Inputs Parameter Value Source Wide Range Pressure [ ] Page 34 of Reference [3] and Measurement Uncertainty Read @ Page 12 of Reference [4]
Pressure Taps PI-RC2A4 or PI-RC2B4 Low Range Pressure Measurement [ ] Page 34 of Reference [3] and Uncertainty Read @ Pressure Tap Page 12 of Reference [4]
PI-RC2A6.
Temperature Measurement 18°F Page 34 of Reference [2]
Uncertainty Read @ Wide Range Temperature TIRC4A2 and TIRC4B2 DH-4849 Lift Pressure 330 psig Page 32 of Reference [3]
(Uncorrected)
LTOP Enable Temperature 280°F Page 32 of Reference [3]
(Uncorrected)
LTOP Allowable Pressure Limit [ ] Section 6.2 of Reference [2]
(RV @ 70°F, Uncorrected)
Minimum LTOP Enable 243°F Section 6.2 of Reference [2]
Temperature (Corrected)
Largest P Between Locations of [ ] Section 6.2 of Reference [2]
Interest in the RCS and DH-4849 when TRCS is below 140°F Technical Specification Basis P=f(T) Table 6-5 of Reference [2]
Normal HU PT Curves (Location Corrected)
Page 7
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Parameter Value Source Technical Specification Basis P=f(T) Table 6-7 of Reference [2]
Normal CD PT Curves (Location Corrected)
Technical Specification Basis P=f(T) Table 6-12 of Reference [2]
ISLH HU PT Curves (Location Corrected)
Technical Specification Basis P=f(T) Table 6-13 of Reference [2]
ISLH CD PT Curves (Location Corrected)
Maximum LCF from PI-RC2A6 to [ ] Case DB-D11.OUT, DH-4849 with Three or Fewer Table 4-15 of Reference [5]
RCPs Operational Table 2-2: Nomenclature Acronym Definition CD Cooldown DHR Decay Heat Removal HU Heatup ISLH In-Service Leak and Hydrostatic (Pressure Test)
LCF Location Correction Factor LTOP Low Temperature Over-Pressure NDT Nil-Ductility Transition PT Pressure-Temperature RCP Reactor Coolant Pump RCS Reactor Coolant System 3.0 ASSUMPTIONS The assumptions employed during the development of the inputs to the procedural NDT/LTOP limits calculated herein, if any, are described below.
3.1 Unverified Assumptions There are no unverified assumptions requiring verification prior to using the results of this calculation.
3.2 Justified Assumptions
- 1. The starting temperature for plant heatup and the ending temperature for plant cooldown are assumed to be 70oF. [
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves
- 2. [
]
4.0 CALCULATIONS The development of the procedural NDT/LTOP limits inputs is presented below. Unless otherwise noted, all inputs (and sources) used herein are summarized in Table 2-1.
4.1 NDT Limit Curves The inputs to the procedural NDT limits are developed by applying the pressure and temperature measurement uncertainties to the location corrected values. [
] These calculations are presented in Table 4-1 through Table 4-4 for the normal HU, ISLH HU, normal CD, and ISLH CD, respectively. These data are also presented in Figure 4-1 through Figure 4-8. Per Justified Assumption 1, the HU/CD transients are considered to begin/end at 70oF for the transients with the temperature uncertainty applied.
Unmodified starting/ending temperatures were left as-is (i.e., @ 70oF).
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Table 4-1: Normal Heatup (PI-RC2A4 or PI-RC2B4)
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Page 11
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Note: Refer to 77-2718NP-006/007 Table 8-6 for Non-Proprietary data.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Table 4-2: ISLH Heatup (PI-RC2A4 or PI-RC2B4)
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Page 14
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Note: Refer to 77-2718NP-006/007 Table 8-3 for Non-Proprietary data.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Table 4-3: Normal Cooldown (PI-RC2A4 or PI-RC2B4)
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Page 17
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Note: Refer to 77-2718NP-006/007 Table 8-3 for Non-Proprietary data.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Table 4-4: ISLH Cooldown (PI-RC2A4 or PI-RC2B4)
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Note: Refer to 77-2718NP-006/007 Table 8-7 for Non-Proprietary data.
[
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves 4.2 LTOP Limit Curves The LTOP input to the procedural curves is developed below, and is plotted with the NDT limits presented in Figure 4-1 through Figure 4-8. [
]
[
]
[
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Improved Technical Specification (ITS) Figure 3.4.12-1, RCS Pressure Versus Pressurizer Level Limit for Inoperable DHR System Relief Valve in MODE 4, and Figure 3.4.12-2, RCS Pressure Versus Pressurizer Level Limit for Inoperable DHR System Relief Valve in MODE 5 and MODE 6 when the reactor vessel head is on, provide operating restrictions in Mode 4 through Mode 6 to protect against a postulated LTOP event (i.e., failed open MU valve) with an inoperable DHR System relief valve (single failure). The pressurizer level restrictions ensure that the P-T limits reported in the PTLR are not exceeded during the assumed [ ] of the LTOP event [ ]. ITS Figure 3.4.12-1 and Figure 3.4.12-2 are based on corrected cooldown P-T limits at 10 EFPY presented in Figure 5 of Reference [8]. Table 4-5 presents these data alongside the corresponding 52 EFPY data for comparison [
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Table 4-5: 10 EFPY and 52 EFPY P-T Limit Comparison Since the 10 EFPY pressures in Reference [8] are more restrictive than the 52 EFPY pressure limits calculated in Reference [2] and presented in Table 4-3, ITS Figures 3.4.12-1 and 3.4.12-2 remain unchanged for 52 EFPY.
4.3 Surge Line Limit The surge line limits, which are taken from Figure 8-1 of Reference [9], are added for convenience to Figure 4-1 through Figure 4-8 and tabulated below. These data are not corrected herein for location or measurement uncertainty.
Table 4-6: Surge Line Limits Page 23
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-1: Normal Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable. Also, refer to 77-2718NP-006 for the Non-Proprietary Normal Heatup plot without uncertainty.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-2: Normal Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-3: ISLH Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-4: ISLH Heatup NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-5: Normal Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable. Also, refer to 77-2718NP-006 for the Non-Proprietary Normal Cooldown plot without uncertainty.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-6: Normal Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-7: ISLH Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable.
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Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves Figure 4-8: ISLH Cooldown NDT Limits, [ ] (PI-RC2A4 or PI-RC2B4)
Note: ITS Figure 3.4.12-1 and Figure 3.4.12-2 control RCS pressure/temperature if DH-4849 is unavailable Page 31
Document No. 32-9344638-000 PROPRIETARY Updated Inputs to 52 EFPY P-T Operating Curves
5.0 REFERENCES
References identified with an (*) are maintained within Davis-Besse Records System and are not retrievable from Framatome Records Management. These are acceptable references per Framatome Administrative Procedure 0402-01, Attachment 7. See page 2 for Project Manager Approval of customer references.
- 1. Framatome Document 32-9271138-001, Updated Inputs to 52 EFPY P-T Operating Curves.
- 2. [ ]
- 3. [
]
- 4. *Davis-Besse Plant Procedure DB-PF-06703, Revision 23, Miscellaneous Operation Curves.
- 5. [
]
- 6. [ ]
- 7. [
]
- 8. [ ]
- 9. Framatome Document 77-2127-003, Report BAW-2127, Pressurizer Surge Line Thermal Stratification-Supplement 3.
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