Letter Sequence Request |
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TAC:MD3002, Control Room Habitability (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
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MONTHYEARML0733004532003-11-27027 November 2003 Schedule and Response to PSEG Letter (LR-N07-0274) Dated October 23, 2007, Plans Related to Steam Dryer Evaluation Regarding Request for Extended Power Uprate Project stage: Other ML0626900642006-09-0101 September 2006 Attachment 26, C.D.I. Report No. 06-16NP, Rev 1, Estimating High Frequency Flow Induced Vibration in the Main Stream Lines at Hope Creek Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. Project stage: Request LR-N06-0286, Request for License Amendment Extended Power Uprate2006-09-18018 September 2006 Request for License Amendment Extended Power Uprate Project stage: Request ML0626900442006-09-30030 September 2006 Attachment 21, C.D.I. Report No. 06-27, Rev 0, Stress Analysis of Hope Creek Unit 1 Steam Dryer at CLTP and EPU Conditions Using 1/8th Scale Model Pressure Measurement Data. Project stage: Request ML0631101672006-09-30030 September 2006 Attachment 2 - CDI Technical Memo 06-23P (Non-Proprietary) Comparison of Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions, Revision 0, Dated September 2006 Project stage: Request LR-N06-0413, Supplement to License Amendment Request for Extended Power Uprate2006-10-10010 October 2006 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0628303692006-10-13013 October 2006 Supplement to Application for Extended Power Uprate Project stage: Other ML0629003222006-10-18018 October 2006 Extended Power Uprate Accpetance Review Results Project stage: Other LR-N06-0418, Supplement to License Amendment Request for Extended Power Uprate, to Increase the Maximum Authorized Power Level to 3840 Megawatts Thermal2006-10-20020 October 2006 Supplement to License Amendment Request for Extended Power Uprate, to Increase the Maximum Authorized Power Level to 3840 Megawatts Thermal Project stage: Supplement ML0628304722006-11-0808 November 2006 PSEG Nuclear LLC, Withholding from Public Disclosure, NEDC-33076P, Revision 2, Safety Analysis Report for Hope Creek Constant Pressure Power Uprate, Class III, MD3002 Project stage: Other ML0628304532006-11-21021 November 2006 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0633301432006-12-15015 December 2006 11/13-14/2006 Summary of Category 1 Meeting with PSEG Nuclear LLC, Regarding Application for Extended Power Uprate for Hope Creek Project stage: Meeting ML0703002772007-01-26026 January 2007 E-Mail Shea-NRR,to Duke, PSEG, Group1 Draft EPU RAI Project stage: Draft Other ML0716303072007-01-31031 January 2007 C.D.I. Technical Note No. 07-01NP, EPU Conditions in the Main Steam Lines at Hope Creek Unit 1: Additional Subscale Four Line Tests. Project stage: Request LR-N07-0034, C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions.2007-01-31031 January 2007 C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions. Project stage: Request LR-N07-0026, Supplemental to License Amendment Request for Extended Power Uprate2007-02-14014 February 2007 Supplemental to License Amendment Request for Extended Power Uprate Project stage: Supplement LR-N07-0029, Supplement to License Amendment Request for Extended Power Uprate2007-02-16016 February 2007 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0703304152007-02-16016 February 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0706606192007-02-20020 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 5 Project stage: Draft RAI ML0706601992007-02-20020 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 4 Project stage: Draft RAI ML0704602432007-02-23023 February 2007 Ltr Request for Additional Information Related to the Request for Extended Power Uprate Project stage: RAI ML0706606382007-02-23023 February 2007 Draft Request for Additional Information Hope Creek EPU Grp 6 Project stage: Draft RAI ML0706803142007-02-28028 February 2007 Hope Creek, Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0708103652007-02-28028 February 2007 C.D.I. Report No. 07-01NP, Rev. 0, Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz. Project stage: Request ML0706006112007-03-0202 March 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0709200252007-03-0202 March 2007 Slides for Summary of March 2, 2007 Meeting with PSEG Nuclear LLC on an Application for Extended Power Uprate for Hope Creek Generating Station Regarding Steam Dryer Margin Project stage: Meeting ML0706803062007-03-13013 March 2007 Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI LR-N07-0035, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-13013 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0055, Supplement to License Amendment Request for Extended Power Uprate2007-03-13013 March 2007 Supplement to License Amendment Request for Extended Power Uprate Project stage: Supplement ML0708004302007-03-29029 March 2007 Summary of March 2, 2007, Meeting with PSEG Nuclear, LLC, on an Application for Extended Power Uprate for Hope Creek Generating Station Regarding Steam Dryer Margin Project stage: Meeting LR-N07-0060, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-30030 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0069, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-03-30030 March 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0070, Response to Request for Additional Information on Request for License Amendment - Extended Power Uprate2007-04-13013 April 2007 Response to Request for Additional Information on Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0084, Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration2007-04-18018 April 2007 Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration Project stage: Supplement ML0711400912007-04-20020 April 2007 Request for Additional Information Regarding Request for Extended Power Uprate (TAC MD3002) - NON-PROPRIETARY Project stage: RAI ML0713603772007-04-30030 April 2007 C.D.I. Report No. 06-16NP, Rev. 2, Estimating High Frequency Flow Induced Vibration in the Main Steam Lines at Hope Creek, Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. Project stage: Request LR-N07-0099, Response to Request for Additional Information Request for License Amendment, Extended Power Uprate2007-04-30030 April 2007 Response to Request for Additional Information Request for License Amendment, Extended Power Uprate Project stage: Response to RAI ML0710104492007-05-0303 May 2007 Explanation of Hope Creek Nuclear Generating Station Extended Power Uprate and Conclusion of Informal Consultation Project stage: Other ML0712404872007-05-0909 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N07-0102, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate2007-05-10010 May 2007 Response to Request for Additional Information Request for License Amendment - Extended Power Uprate Project stage: Response to RAI ML0712404112007-05-14014 May 2007 RAI, Request for Additional Information Regarding Request for Extended Power Uprate Project stage: RAI ML0712405052007-05-15015 May 2007 Summary of Meeting with PSEG Nuclear LLC, Regarding Technical Aspects of the Licensee'S Application for an Extended Power Uprate (EPU) at the Hope Creek Generating Station (Hope Creek) Project stage: Meeting ML0712404612007-05-17017 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0628605302007-05-17017 May 2007 Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance ML0713707002007-05-17017 May 2007 Request for Additional Information (RAI) Regarding Request for Extended Power Uprate Project stage: RAI ML0712405102007-05-17017 May 2007 PSEG Nuclear LLC, Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N07-0123, Response to Request for Additional Information, Request for License Amendment - Extended Power Uprate2007-05-18018 May 2007 Response to Request for Additional Information, Request for License Amendment - Extended Power Uprate Project stage: Response to RAI LR-N07-0113, Supplement to Request for License Amendment Extended Power Uprate Steam Dryer Limit Curves2007-05-18018 May 2007 Supplement to Request for License Amendment Extended Power Uprate Steam Dryer Limit Curves Project stage: Supplement LR-N07-0122, Supplement to Request for License Amendment Re Extended Power Uprate & C.D.I. Technical Note No. 07-012007-05-24024 May 2007 Supplement to Request for License Amendment Re Extended Power Uprate & C.D.I. Technical Note No. 07-01 Project stage: Supplement ML0717203702007-05-31031 May 2007 Attachment 2, C.D.I. Technical Note No. 07-19NP, Revision 0, Hope Creek, Unit 1, Extended Power Uprate Limit Curve Analysis for Dryer Stress Prediction During Power Ascension Project stage: Request 2007-02-28
[Table View] |
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Category:Report
MONTHYEARML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) LR-N21-0007, Report of Changes, Tests, and Experiments2021-01-28028 January 2021 Report of Changes, Tests, and Experiments ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N18-0056, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-07-25025 July 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) LR-N17-0049, Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.12017-02-0909 February 2017 Submittal of Cycle 21 Summary of Report of Plant Startup in Accordance with the Requirements of Technical Specification 6.9.1.1 LR-N17-0036, License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 202017-02-0707 February 2017 License Renewal Commitment Implementation, 90-Day Report for Refueling Outage 20 ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16256A6412016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. LR-N16-0113, NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses.2016-09-12012 September 2016 NUREG-0800, Appendix 18-A Assessment, Crediting Manual Operator Actions in the Diversity and Defense-in-Depth Analyses. ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6402016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment2016-08-31031 August 2016 Hope Creek Power Range Neutron Monitoring Upgrade - Human Factors Engineering Assessment ML16256A6432016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0113, ISG-06 Enclosure B Roadmap, Phase 2 Documents.2016-07-18018 July 2016 ISG-06 Enclosure B Roadmap, Phase 2 Documents. LR-N16-0099, GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21.2016-05-31031 May 2016 GNF-003N5734-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR Hope Creek Cycle 21. ML16049A6092016-02-29029 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident and Staff Closure LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N14-0248, Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5.2014-12-0909 December 2014 Response to March 12, 2012 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5. ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 LR-N14-0175, CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-92332014-08-11011 August 2014 CFR 71.95 Report for Packaging and Transporting a Shipping Cask (Model TN-RAM) Without Meeting a Required Condition in Certificate of Compliance 71-9233 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 LR-N14-0112, CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station2014-04-25025 April 2014 CFR 20.2206 Report - Apportion the 2013 Site Dose Between Salem and Hope Creek Station LR-N14-0035, PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima...2014-03-28028 March 2014 PSEG Nuclear Llc'S Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima... ML13365A2532014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14028A0742014-02-0606 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Hope Creek Generating Station, TAC No. MF0867 LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic2014-01-29029 January 2014 Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 92012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G2012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G ML13052A6772012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 ML13052A6782012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6792012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 52012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML13052A6802012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J ML13052A6812012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 2023-09-06
[Table view] Category:Technical
MONTHYEARML23249A2622023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021) ML20121A1332020-03-0303 March 2020 Biological Opinion 2019 Annual Incidental Take Report LR-N18-0057, Pressure and Temperature Limits Report, Revision 12018-06-0808 June 2018 Pressure and Temperature Limits Report, Revision 1 LR-N17-0163, License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary2017-11-0909 November 2017 License Amendment Request - Safety Limit Minimum Critical Power Ratio Change, Non-Proprietary LR-N17-0092, Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2017-04-28028 April 2017 Supplemental Information to License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report LR-N17-0044, Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version)2017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) ML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi LR-N17-0044, Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Ve2016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi ML16256A6422016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. LR-N16-0113, NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2.2016-08-31031 August 2016 NED0-33872, Rev. 0, Hope Creek Generating Station Numac Prnm Upgrade Phase 2. ML16256A6442015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. LR-N15-0178, NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary)2015-09-30030 September 2015 NEDO-33864, Revision 0, Hope Creek Generating Station Numac Prnm Upgrade, (Non-Proprietary) LR-N16-0113, NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan.2015-09-30030 September 2015 NED0-33864, Rev. 0, Appendix B, Numac Systems Engineering Development Plan. ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML13365A2532014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14028A0742014-02-0606 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Hope Creek Generating Station, TAC No. MF0867 LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic2014-01-29029 January 2014 Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G2012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G ML13052A6772012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 ML13052A6782012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 ML13052A6792012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 10 Through Appendix G LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 92012-11-30030 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Chapter 6 Through Chapter 9 LR-N12-0366, Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 52012-11-30030 November 2012 Enclosure 1 to LR-N12-0366, Salem - Hope Creek Kld TR-499, Development of Evacuation Time Estimates, Cover Through Chapter 5 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J2012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-752012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-1492012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 ML13052A6802012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix H Through Appendix J ML13052A6812012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75 ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix L Through Appendix N2012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix L Through Appendix N LR-N11-0289, Site-Specific Cost Estimates2011-09-15015 September 2011 Site-Specific Cost Estimates ML1027901062010-09-30030 September 2010 NEDO-33506, Rev 0, Hope Creek, Final Feedwater Temperture Reduction and Feedwater Heaters Out-of-Service. LR-N10-0239, 0000-0119-1728, Revision 0, Hope Creek Cycle 17 Stability Results for GE14i Support, Attachment 12010-06-30030 June 2010 0000-0119-1728, Revision 0, Hope Creek Cycle 17 Stability Results for GE14i Support, Attachment 1 ML1029806222010-04-30030 April 2010 Email from Cahill, Christopher to Burritt, Arthur; Cline, Leonard, FW: AFW Missile Barrier. ML1013903182009-11-15015 November 2009 Calculation 80096650, Revision 0, Leakage Reduction Program Calculation, Attachment 6 to LR-N10-0163 LR-N08-0224, Attachment 6 - Hope Creek Final Stress Assessment of Hope Creek, Unit 1 Steam Dryer at 115% CLTP Conditions, C.D.I. Report No. 08-21NP, Revision 12008-10-31031 October 2008 Attachment 6 - Hope Creek Final Stress Assessment of Hope Creek, Unit 1 Steam Dryer at 115% CLTP Conditions, C.D.I. Report No. 08-21NP, Revision 1 LR-N08-0224, Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 02008-10-31031 October 2008 Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0 ML0831008282008-10-31031 October 2008 Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0 LR-N08-0199, Attachment 4 - C.D.I. Technical Note No. 08-20NP, Rev. 1, Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1.2008-08-31031 August 2008 Attachment 4 - C.D.I. Technical Note No. 08-20NP, Rev. 1, Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1. ML0825403292008-08-31031 August 2008 Attachment 4 - C.D.I. Technical Note No. 08-20NP, Rev. 1, Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1. LR-N08-0199, Attachment 5 - C.D.I. Report.No. 08-29NP, Rev. 0, Final Stress Assessment of Hope Creek Unit 1 Steam Dryer at 111.5% CLTP Conditions.2008-08-31031 August 2008 Attachment 5 - C.D.I. Report.No. 08-29NP, Rev. 0, Final Stress Assessment of Hope Creek Unit 1 Steam Dryer at 111.5% CLTP Conditions. ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 LR-N08-0123, C.D.I. Technical Note No. 07-29NP, Revision 2, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Hope Creek Unit 1.2008-05-31031 May 2008 C.D.I. Technical Note No. 07-29NP, Revision 2, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Hope Creek Unit 1. ML0813604922008-04-30030 April 2008 Attachment 2, C.D.I. Technical Note No. 07-29NP, Revision 1, Limit Curve Analysis with ACM Rev. 4 at Hope Creek Unit 1. ML0804205442008-01-31031 January 2008 CDI Report No. 07-17NP Revision 3 Stress Assessment of Hope Creek Unit 1 Steam Dryer Based on Revision 4 Loads Mode. LR-N08-0033, CDI Report No. 07-17NP, Revision 4, Stress Assessment of Hope Creek Unit I Steam Dryer Based on Revision 4 Loads Model.2008-01-31031 January 2008 CDI Report No. 07-17NP, Revision 4, Stress Assessment of Hope Creek Unit I Steam Dryer Based on Revision 4 Loads Model. ML0726404112007-08-31031 August 2007 CDI Report 07-17NP, Stress Assessment of Hope Creek, Unit 1 Steam Dryer Based on Revision 4 Loads Model Revision 2. 2023-09-06
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Attachment 2 LR-N07-0055 LCR H05-01, Rev. 1 Hope Creek Generating Station Facility Operating License NPF-57 Docket No. 50-354 Supplement to Request for License Amendment Extended Power Uprate C.D.I. Report No. 07-01NP Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz Revision 0 February 2007
This Report Does Not Contain C.D.I. Proprietary Information C.D.I. Report No. 07-01NP Revised Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz Revision 0 Prepared by Continuum Dynamics, Inc.
34 Lexington Avenue Ewing, NJ 08618 Prepared under Purchase Order No. 4500378760 for Nuclear Business Unit, PSEG Nuclear LLC Materials Center, Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Approved by A
jj1dqA4 a/a-lt4 Alan J. Bilanin February 2007
This Report Does Not Contain C.D.I. Proprietary Information Executive Summary Measured in-plant pressure time-history data (acquired in February 2007) in the four main steam lines of Hope Creek Unit I (HC1), at the eight strain gage locations at Current Licensed Thermal Power (CLTP), are processed by a dynamic model of the steam delivery system to predict loads on the steam dryer. These measured data are used with a validated acoustic circuit model to predict the fluctuating pressures anticipated across components of the steam dryer in the reactor vessel. The hydrodynamic load data may then be used by a structural analyst to assess the structural adequacy of the steam dryer in HC 1.
These loads are compared with in-plant time-history data taken previously (in May 2006), in which several strain gages were not working on main steam lines C and D. In addition, measured one-eighth scale pressure time-history data at corrected CLTP conditions are also compared to the recent full-scale pressure time-history data as well.
This effort provides PSEG with a comparison between previous and present in-plant data, and with subscale test data, and the application of a validated acoustic circuit model, at power levels where the pressure data were acquired.
This Report Does Not Contain C.D.I. Proprietary Information Table of Contents Section Page Executive Summary .................................................................. i T able of C ontents ..................................................................... ii
- 1. Introduction ............................................................................ 1
- 2. Modeling Considerations ............................................................ 2
- 3. Input Pressure Data .................................................................. 3 3.1 February 2007 Data ......................................................... 3 3.2 May 2006 Data ............................................................... 8 3.3 January 2007 Subscale Data ................................................ 8 4 . R esults ................................................................................ 18
- 5. C onclusions ........................................................................... 23
- 6. R eferences ............................................................................. 24 ii
This Report Does Not Contain C.D.I. Proprietary Information
- 1. Introduction In Spring 2005 Exelon installed new steam dryers into Quad Cities Unit 2 (QC2) and Quad Cities Unit 1. This replacement design, developed by General Electric, sought to improve dryer performance and overcome structural inadequacies identified on the original dryers, which had been in place for the last 30 years. As a means for confirming the adequacy of the steam dryer, the QC2 dryer was instrumented with pressure sensors at 27 locations. These pressures formed the set of data used to validate the predictions of an acoustic circuit model under development by Continuum Dynamics, Inc. for several years [1]. The results of this benchmark exercise [2] confirmed the predictive ability of the acoustic circuit model for pressure loading across the dryer. This model, validated against the Exelon full scale data, is used in this effort.
This report applies this validated acoustic circuit model to the Hope Creek Unit I (HCI) steam dryer and main steam line geometry. Recent data obtained from the four main steam lines are used to generate predictions of the pressure loading on the HCI dryer at Current Licensed Thermal Power (CLTP) conditions. These data are compared with main steam line data taken previously at HCI, when strain gage failures occurred and main steam line data had to be approximated [3]. In addition, data obtained from a one-eighth scale model of the HC1 steam delivery system are used to generate full-scale predictions of the pressure loading on the HC1 dryer at CLTP conditions as well [4].
This Report Does Not Contain C.D.I. Proprietary Information
- 2. Modeling Considerations The HC1 steam supply system is broken into two distinct analyses: a Helmholtz solution within the steam dome and an acoustic circuit analysis in the main steam lines. The approach followed in the current analysis is identical to the approach discussed and taken in [3] and is not repeated here, with the exception of summarizing the locations of the strain gages on the four main steam lines, as shown in Table 2.1.
Table 2.1. Main steam line lengths at HC 1. The main steam lines are 26 inch Schedule 80 (ID = 23.647 in) to the strain gages.
Main Steam Line Distance to First Distance to Second Strain Gage (ft) Strain Gage (ft)
A 9.71 45.83 B 9.71 45.71 C 9.71 45.71 D 9.71 45.83 2
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- 3. Input Pressure Data Three sets of data are analyzed in this report: strain gage data collected in February 2007, with all eight strain gage locations (two per main steam line) functioning and providing data; strain gage data collected in May 2006 with strain gages failures on main steam lines C and D (separately reported in [3]); and subscale pressure transducer data collected in January 2007 as part of an effort to calibrate the Mach number in the subscale facility (the experiment is separately reported in [4]. All test conditions are at CLTP conditions.
3.1 February 2007 Data Strain gages were mounted on the four main steam lines in HC1. The in-plant data examined here are summarized in Table 3.1, and include eight strain gage measurements [5].
Recorded strain is converted to pressure with the factors provided in [6].
Table 3.1. Data set considered for HC 1.
Data Set Strain Gage Data Rate Pertinent Voltage (V) (samples/sec) Comments 20070208110642 0.01 1024 CLTP 20070208105816 10.0 1024 CLTP Because of the small level of voltage across the strain gages in the first set of data, it is postulated that these data contain only system noise, and that this noise can be removed from the second set of data, which includes the signal plus the noise. Several frequency ranges were also excluded from these data, for the reasons given in Table 3.2.
Table 3.2. Exclusion frequencies for HC1.
Frequency Interval (Hz) Exclusion Cause 0.0 to 2.0 Mean 59.8 to 60.2 60 Hz Line Noise 119.8 to 120.2 120 Hz Line Noise 179.8 to 180.2 180 Hz Line Noise 104.9 to 105.3 B Recirculation Pump 106.5 to 106.9 A Recirculation Pump The resulting main steam line pressures are shown in Figures 3.1, while the coherence between the upper and lower strain gages is shown in Figures 3.2. Pressure levels are shown in Table 3.3.
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This Report Does Not Contain C.D.I. Proprietary Information I((
(3)))
Figure 3.1. Main steam line data collected in February 2007: upper locations are black, while lower locations are red; main steam line A (top); main steam line B (bottom).
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Figure 3.1. Main steam line data collected in February 2007: upper locations are black, while lower locations are red; main steam line C (top); main steam line D (bottom).
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Figure 3.2. Coherence between the upper and lower strain gage locations for the data collected in February 2007: main steam line A (top); main steam line B (bottom).
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Figure 3.2. Coherence between the upper and lower strain gage locations for the data collected in February 2007: main steam line C (top); main steam line D (bottom).
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This Report Does Not Contain C.D.I. Proprietary Information Table 3.3. Pressure levels for the data collected in February 2007.
(3)))
3.2 May 2006 Data Because of the failure of the lower C and D main steam line strain gages in the data collected in May 2006, symmetry of the steam lines was used as a justification for replacing these signals with those on main steam lines B and A, respectively. Geometry considerations supported this substitution with regard to both main steam line length and standpipe location.
Pressure levels are shown in Table 3.4. The main steam line data collected in May 2006 are compared with the main steam line data collected in February 2007 in Figure 3.3.
Since phasing information is lost when main steam line signals are replaced, the time signals on main steam lines C and D (from main steam lines B and A) were shifted in time increments until the maximum dryer load was achieved, as discussed in [3]. The comparison of dryer loads between May 2006 and February 2007 is presented in Section 4.
Table 3.4. Pressure levels for the data collected in May 2006.
((
(3)))
3.3 January 2007 Subscale Data Additional tests were run in January 2007 in the C.D.I. one-eighth scale test facility, in an effort to compare with the previous one-fifth scale test results and refine the flow speed at CLTP conditions [4]. These results (based on a comparison of peak PSD in the standpipes) confirmed that flow conditions run during the one-eighth scale tests, as reported in [7], were high by (( (3))).
Pressure transducer readings - taken at the same main steam line locations as in HC1 - are compared with the February 2007 data in Figure 3.4 for subscale test conditions consistent with
(( )) times the previously assumed CLTP level. Pressure levels are shown in Table 3.5.
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This Report Does Not Contain C.D.I. Proprietary Information It should be noted that the pressure measurements on main steam line D in the subscale rig exhibited a peak near a frequency of (( (3))). As a corresponding peak was not observed on any other lines or in full scale data, this peak was filtered from the pressure readings to provide a more accurate comparison of the subscale test data to plant data.
It may be seen that the average RMS pressure for the February 2007 data (from Table 3.3) is (( (3))) psid, for the May 2006 data (from Table 3.4) is (( (3))) psid, and for the January 2007 subscale data (from Table 3.5 above) is (( (3))) psid. Matching the one-eighth and one-fifth scale tests still resulted in a conservative measurement of the main steam line pressure data, even though several of the pressure locations measured similar minimum, maximum, and RMS pressure levels (comparing Table 3.3 with Table 3.5 entries).
Table 3.5. Pressure levels for the subscale test data collected in January 2007 (corrected to full scale).
(()
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Figure 3.3. Comparison of May 2006 and February 2007 main steam line data: A upper (top);
A lower (bottom).
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Figure 3.3. Comparison of May 2006 and February 2007 main steam line data: B upper (top); B lower (bottom).
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Figure 3.3. Comparison of May 2006 and February 2007 main steam line data: C upper (top); C lower (bottom). B main steam line data are substituted for C main steam line data in the May 2006 data.
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((I (3)))
Figure 3.3. Comparison of May 2006 and February 2007 main steam line data: D upper (top);
D lower (bottom). A main steam line data are substituted for D main steam line data in the May 2006 data.
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This Report Does Not Contain C.D.I. Proprietary Information Er (3)))
Figure 3.4. Comparison of January 2007 subscale test data and February 2007 main steam line data: A upper (top); A lower (bottom). The one-eighth-scale data matched the one-fifth-scale data peak PSD at the valve disc ends of the three standpipes on main steam line B [4]. ((
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[1 (3)))
Figure 3.4. Comparison of January 2007 subscale test data and February 2007 main steam line data: B upper (top); B lower (bottom). The one-eighth-scale data matched the one-fifth-scale data peak PSD at the valve disc ends of the three standpipes on main steam line B [4]. ((
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Figure 3.4. Comparison of January 2007 subscale test data and February 2007 main steam line data: C upper (top); C lower (bottom). The one-eighth-scale data matched the one-fifth-scale data peak PSD at the valve disc ends of the three standpipes on main steam line B [4]. ((
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Figure 3.4. Comparison of January 2007 subscale test data and February 2007 main steam line data: D upper (top); D lower (bottom). The one-eighth-scale data matched the one-fifth-scale data peak PSD at the valve disc ends of the three standpipes on main steam line B [4]. ((
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- 4. Results The three sets of main steam line pressure data were used to drive the verified acoustic circuit model (Rev. 2) for the HCI steam dome and main steam lines. Comparisons are presented on a low-resolution grid (shown schematically in [3]) by summarizing the peak and RMS pressures expected over the time interval provided in the original data, as shown in Figures 4.1 and 4.2. It may be seen that the maximum differential pressure load predicted on the HCI dryer at CLTP conditions is approximately (( (3))) psid (node 99) for the February 2007 full-scale plant data. In comparison, the May 2006 data, with use of the conservative algorithm, resulted in higher differential loads at all nodes, and a maximum differential pressure load (also at node 99) of approximately (( (3))) psid.
Peak loads are predicted on node 7 (opposite the C and D main steam lines) and node 99 (opposite the A and B main steam lines), and are compared in Figures 4.3 and 4.4. Here it may be seen that the highest PSD on the dryer occurs at a frequency of approximately (( (3))).
It may be seen that even with the favorable comparison on the standpipes between the one-fifth and one-eighth scale tests (as reported in [4]), the subscale low resolution comparison with the full scale data demonstrates a conservative prediction of the dryer loads (a maximum differential pressure load at node 7 of approximately (( (3))) psid).
(3)))
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Figure 4.1. Predicted loads at CLTP conditions as developed by the current methodology to 200 Hz, comparing full scale 2007 (red curves) with full scale 2006 (blue curves).
Node 7 is located at the back center edge of the cover plate opposite the C and D main steam lines, while node 99 is located at the back center edge of the cover plate opposite the A and B main steam lines.
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Figure 4.2. Predicted loads at CLTP conditions as developed by the current methodology to 200 Hz, comparing full scale 2007 (red curves) with subscale (black curves). Node 7 is located at the back center edge of the cover plate opposite the C and D main steam lines, while node 99 is located at the back center edge of the cover plate opposite the A and B main steam lines.
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Figure 4.3. PSD comparison of the predicted CLTP pressure. load at the center edge of the cover plate with the outer bank hood for node 7 opposite the C and D side of the dryer (top) and node 99 opposite the A-B side of the dryer (bottom), comparing full scale 2007 (red curves) with full scale 2006 (blue curves).
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Figure 4.4. PSD comparison of the predicted CLTP pressure load at the. center edge of the cover plate with the outer bank hood for node 7 opposite the C and D side of the dryer (top) and node 99 opposite the A-B side of the dryer (bottom), comparing full scale 2007 (red curves) with subscale (black curves).
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- 5. Conclusions The C.D.I. acoustic circuit analysis (Rev. 2), using in-plant measured data from HC I and one-eighth-scale measured data from C.D.I.:
a) Determines that steam dryer differential low-resolution loads at CLTP conditions from plant data are less than (( (3))) psid, when all strain gages are operational. The loads are lower than those predicted by the May 2006 data, and consequently the CLTP finite element analysis [8] is conservative.
b) Shows that the subscale data at CLTP conditions are conservative. The model predicts a maximum load of approximately (( (3))) psid in comparison to a maximum load of
(( (3))) psid from plant data. This comparison shows that the dryer loads predicted at EPU conditions (in [4]) should also be conservative.
c) Predicts that the loads on dryer components are largest for components nearest the main steam line inlets and decrease inward into the reactor vessel.
d) Determines that the highest differential pressure load on the dryer at full scale occurs at approximately (( (3))) Hz.
e) In-plant data indicates no discrete frequency loading is occurring, and suggests that the steam dryer loads, at least up to CLTP conditions, are a result of random flow noise. This finding is supported by the calculation of coherence between the plant upper and lower strain (3))).
gage measurements being low ((
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- 6. References
- 1. Continuum Dynamics, Inc. 2005. Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes (Rev. 6). C.D.I. Report No. 04-09 (Proprietary).
- 2. Continuum Dynamics, Inc. 2006. Bounding Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements (Rev. 2). C.D.I. Report No. 05-28 (Proprietary).
- 3. Continuum Dynamics, Inc. 2006. Hydrodynamic Loads on Hope Creek Unit 1 Steam Dryer to 200 Hz (Rev. 2). C.D.I. Report No. 06-17.
- 4. Continuum Dynamics, Inc. 2007. EPU Conditions in the Main Steam Lines at Hope Creek Unit 1: Additional Subscale Four Line Tests (Rev. 0). C.D.I. Technical Note No. 07-01.
- 5. Structural Integrity Associates, Inc. 2007. Hope Creek Main Steam Line Strain Gage Data:
MSL Channel Combinations.
- 6. Structural Integrity Associates, Inc. 2006. Hope Creek Main Steam Line Strain Gage Data Reduction. Calculation File No. HC-28Q-302.
- 7. Continuum Dynamics, Inc. 2006. Estimating High Frequency Flow Induced Vibration in the Main Steam Lines at Hope Creek Unit 1: A Subscale Four Line Investigation of Standpipe Behavior (Rev. 1). C.D.I. Report No. 06-16.
- 8. Continuum Dynamics, Inc. 2006. Stress Analysis of the Hope Creek Unit 1 Steam Dryer for CLTP (Rev. 3). C.D.I. Report No. 06-24.
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