Letter Sequence Response to RAI |
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TAC:ME1476, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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
- Meeting
Results
Other: ML092460553, ML092460595, ML092460596, ML100190073, ML100190074, ML100190075, ML100190076, ML100190077, ML101300006, ML101900448, ML101900449, ML101900450, ML101950497, ML101950498, ML103050187, ML110460160, ML110880302, ML11171A060, ML111920326, ML111950133, ML112031112, ML112081701, ML112160736, ML11221A013, ML112450479, ML112460008, ML112460009, ML113340186, ML120050150, ML120250137, ML12313A203, ML12313A204, ML12313A206, NRC-2010-0117, Final Environmental Assessment and Finding of No Significant Impact - Federal Register Notice - Related to the Proposed License Amendment to Increase the Maximum Reactor Power Level
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MONTHYEARML1001900772004-03-31031 March 2004 GE-NE-0000-0024-6517-R0, Safer/Gestr Loss-of-Coolant Accident Analysis for GE14 Fuel. Project stage: Other ML0916101032009-05-27027 May 2009 License Amendment Request (LAR) Pursuant to 10 CFR 50.90: Extended Power Uprate Project stage: Request ML0918906662009-07-0808 July 2009 E-mail from R. Guzman to J. Dosa Acceptance Review Results of NMP2 Extended Power Uprate Application Project stage: Acceptance Review ML0919402542009-07-15015 July 2009 Acceptance Review of License Amendment Request Extended Power Uprate Project stage: Acceptance Review ML0924605502009-08-28028 August 2009 Response to Acceptance Review Comments License Amendment Request for Extended Power Uprate Project stage: Request ML0924605962009-08-28028 August 2009 Attachment 2 - CDI Report 09-26NP, Revision 0, (Non-Proprietary) Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Part 2 of 2 Project stage: Other ML0924605952009-08-28028 August 2009 Attachment 2 - CDI Report 09-26NP, Revision 0, (Non-Proprietary) Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Part 1 of 2 Project stage: Other ML0924605532009-08-28028 August 2009 Attachment 3 - CDI Report 08-08NP, Revision 2, (Non-Proprietary) Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point, Unit 2 Steam Dryer to 250 Hz Project stage: Other ML0924502742009-09-0202 September 2009 Acceptance Review Determination of Amendment Request and Supplemental Information Extended Power Uprate Project stage: Acceptance Review ML1019704202009-09-18018 September 2009 E-mail from R. Guzman to J. Dosa Request for Additional Information - Clarification of Applicability of GEH Methods Project stage: RAI ML0928100032009-10-0808 October 2009 Request for Additional Information Nine Mile Point Unit 2 (NMP2) Extended Power Uprate Application License Amendment Request Project stage: RAI ML0930800012009-11-13013 November 2009 Request for Additional Information Extended Power Uprate Project stage: RAI ML0931900032009-11-18018 November 2009 Request for Additional Information the License Amendment Request for Extended Power Uprate Project stage: RAI ML0934300032009-12-10010 December 2009 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement Dated August 28, 2009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML0932706132009-12-10010 December 2009 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation Dated May 27, 2009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML0934106852009-12-10010 December 2009 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation Dated May 27, 2009 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML0935110252009-12-23023 December 2009 Request for Additional Information Extended Power Uprate License Amendment Request Project stage: RAI ML1001900722009-12-23023 December 2009 Response to Request for Additional Information, Regarding License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1001900732009-12-31031 December 2009 C.D.I. Technical Note No. 09-17NP, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Nine Mile Point, Unit 2, Revision 0 Project stage: Other ML1001900742009-12-31031 December 2009 C.D.I. Report No. 08-08NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz, Revision 3 Project stage: Other ML1001900752009-12-31031 December 2009 CDI Report No. 09-26NP, Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Cover to Page 62, Revision 1 Project stage: Other ML1001900762009-12-31031 December 2009 CDI Report No. 09-26NP, Stress Assessment of Nine Mile Point, Unit 2 Steam Dryer at CLTP and EPU Conditions, Page 63 Through 130, Revision 1 Project stage: Other ML1019704362010-01-12012 January 2010 E-mail from R. Guzman to T. Darling Request for Additional Information - Extended Power Uprate LAR Standby Liquid Control System Project stage: RAI ML1019704452010-01-27027 January 2010 E-mail from R. Guzman to T. Darling Request for Additional Information Extended Power Uprate - Clarification for Piping NDE Review Project stage: RAI ML1019704532010-02-0101 February 2010 E-mail from R. Guzman to T. Darling Request for Additional Information Extended Power Uprate LAR - Clarification in Fire Protection Review RAI D1, D3 Project stage: RAI ML1005505992010-02-19019 February 2010 Response to Request for Additional Information Regarding License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1006301122010-03-10010 March 2010 Request for Additional Information - Extended Power Uprate License Amendment Request Mechanical & Civil Engineering Review Project stage: RAI ML1006902762010-03-10010 March 2010 E-mail from R.Guzman to T.Darling Request for Additional Information - Containment & Ventilation Branch - Extended Power Uprate Project stage: RAI ML1006301082010-03-10010 March 2010 Request for Additional Information Steam Dryer Review of the License Amendment Request for Extended Power Uprate Operation Project stage: RAI ML1005508412010-03-16016 March 2010 Letter Transmitting the Draft Environmental Assessment for Nine Mile Point Nuclear Station Extended Power Uprate for Unit No. 2 Project stage: Draft Other ML1006804292010-04-0202 April 2010 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement Dated December 23, 2009 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML1006804412010-04-0202 April 2010 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement December 23,2 009 C.D.I Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML1006804482010-04-0202 April 2010 Request for Withholding Information from Public Disclosure - Proposed License Amendment for Extended Power Uprate Operation, Supplement February 19, 2010 GEH Proprietary Documents - Nine Mile Point Nuclear Station Unit No. 2 Project stage: Withholding Request Acceptance ML1008500412010-04-0202 April 2010 Summary of Audit Related to the Review of the Extended Power Uprate License Amendment Request of Nine Mile Point Nuclear Station, Unit No. 2 Project stage: Approval ML1008500512010-04-0202 April 2010 Correction Notice to Draft Environmental Assessment for Nine Mile Point Nuclear Station Proposed Extended Power Uprate Amendment for Unit No. 2 Project stage: Draft Other ML1008501072010-04-0202 April 2010 Letter Transmitting Correction to the Notice for the Draft Environmental Assessment and Finding of No Significant Impact for Nine Mile Point Nuclear Station, Unit No. 2 Project stage: Draft Other ML1013000062010-04-14014 April 2010 Follow-Up Questions - EPU Vessels and Integrity Review Project stage: Other ML1011206582010-04-16016 April 2010 Response to Request for Additional Information Re License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1013803072010-05-0707 May 2010 Response to Request for Additional Information Regarding Steam Dryer Review of the License Amendment Request for Extended Power Uprate Operation Project stage: Response to RAI ML1013200242010-05-10010 May 2010 E-mail from R. Guzman to T. Darling/J. Dosa Request for Additional Information - LOCA Analysis, Extended Power Uprate Project stage: RAI ML1012504242010-05-11011 May 2010 Request for Additional Information Extended Power Uprate License Amendment Request - Reactor System Review Project stage: RAI ML1016101682010-06-0303 June 2010 Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation- Reactor Systems Review Project stage: Response to RAI ML1015908092010-06-0808 June 2010 Request for Additional Information Extended Power Uprate - Probabilistic Risk Assessment Review Project stage: RAI ML1015906522010-06-10010 June 2010 Review of Extended Power Uprate Application and Revised Review Schedule Project stage: Approval ML1019604812010-06-15015 June 2010 E-mail from R.Guzman to T.Darling Request for Additional Information Follow-up RAI - Reactor Systems/Criticality Analysis Project stage: RAI ML1019004492010-06-30030 June 2010 C.D.I. Report No. 10-10NP, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1, Rev. 1 Project stage: Other ML1019004502010-06-30030 June 2010 Calculation SIA 100632.301, Revision 0, May 2010 Nine Mile Point Unit 2 Main Steam Line Strain Gage Data Reduction. Project stage: Other ML1019004482010-06-30030 June 2010 C.D.I. Report No. 10-09NP, ACM Rev. 4.1: Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, Rev. 1 (Non-Proprietary) Project stage: Other ML1019004472010-06-30030 June 2010 Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation - Steam Dryer and Probabilistic Risk Assessment Project stage: Response to RAI ML1019504952010-07-0909 July 2010 Response to Request for Additional Information Regarding the License Amendment Request for Extended Power Uprate Operation, Non-Proprietary Version of Continuum Dynamics, Inc. Report 10-11 Project stage: Response to RAI 2010-02-01
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Category:Legal-Affidavit
MONTHYEARML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML22320A5592022-11-16016 November 2022 2022 Annual Report - Guarantees of Payment of Deferred Premiums ML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML21307A0542021-11-0202 November 2021 Annual Report - Guarantees of Payment of Deferred Premiums ML21272A2772021-09-29029 September 2021 Update to Application for Order Approving License Transfers and Proposed Conforming License Amendments ML21182A1002021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments NMP1L3371, Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-102021-02-10010 February 2021 Summary of Changes, Quality Assurance Topical Report, NO-AA-10 & Decommissioning Quality Assurance Program, NO-DC-10 ML20310A1152020-11-0404 November 2020 Annual Report - Guarantees of Payment of Deferred Premiums ML19318G1702019-11-14014 November 2019 2019 Annual Report - Guarantees of Payment of Deferred Premiums ML18316A0032018-11-0707 November 2018 Submittal of 2018 Annual Report - Guarantees of Payment of Deferred Premiums NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039) ML18011A6242018-01-0808 January 2018 R. E. Ginna, Unit 1, Submittal of Annual Report of the Nuclear Advisory Committee ML17010A0772017-01-19019 January 2017 Submittal of Annual Report of the Nuclear Advisory Committee ML16092A1942016-03-22022 March 2016 Transmittal of Exelon Nuclear Radiological Emergency Plan Annex Revision ML16039A3032016-01-26026 January 2016 Transmittal of Radiological Emergency Implementing Procedure Revisions ML15288A2482015-10-0808 October 2015 Attachment 1, Response to Request for Additional Information Regarding Post Extended Power Uprate Steam Dryer Inspection Results (Non-Proprietary) and Attachment 2, Affidavit Requesting That CDI Information Be Withheld ML14321A7052014-11-14014 November 2014 2014 Annual Report - Guarantees of Payment of Deferred Premiums ML14204A7092014-07-23023 July 2014 Enclosure 3, Affidavit of Peter M. Yandow RS-14-160, Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package2014-07-0202 July 2014 Co. - Submission of Standard Practice Procedure Plans and Foreign Ownership Control or Influence Package ML14118A1412014-03-28028 March 2014 Independent Spent Fuel Storage Installation, Nine Mile Point Independent Spent Fuel Storage Installation, R.E. Ginna Independent Spent Fuel Storage Installation, Response to Request for Affidavit Supporting Request for Designation Of. ML13316B1072013-11-0101 November 2013 License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus ML15022A6632013-09-27027 September 2013 CDI Non-Conformance Report No. 0343, Non-proprietary Version ML13130A1582013-05-0303 May 2013 Submittal of Evaluation to Establish Inspection Intervals for Jet Pump Holddown Beams Fabricated from Modified Alloy 718 Material - Supplemented Affidavit Justifying Withholding Proprietary Information ML12082A1842012-03-20020 March 2012 License Amendment Request Pursuant to 10 CFR 50.90: Use of Modified Alloy 718 Material in Jet Pump Holddown Beams - Supplemental Information in Response to NRC Request for Additional Information ML1127000682011-09-26026 September 2011 Enclosure 3, Mfn 10-245 R4, Affidavit ML0520003282005-07-14014 July 2005 Surveillance Program for Channel-Control Blade Interference ML0414902132004-05-26026 May 2004 Transmittal of Nine Mile Point Units 1 & 2 Application for Renewed Operating Licenses, Including Environmental Report ML0330401822003-10-29029 October 2003 Transmittal of Report BWRVIP-121: BWR Vessel and Internals Project, RAMA Fluence Methodology Procedures Manual, EPRI Technical Report 1008062, October 2003. ML17037C5081974-04-15015 April 1974 Affidavit of Submission Regarding the Nine Mile Point Unit 1 Quality Assurance Program. ML17037C2291973-11-16016 November 1973 Letter Transmitting Response to Request for Additional Information Concerning the Quality Assurance Program ML17037C2801973-04-13013 April 1973 Letter Responding to the April 9, 1973 Letter Requesting Information Relative to the Evaluation of the Environmental Report Accompanying the Petition for Conversion from Provisional to a Full-Term Operating License ML17037C2811973-03-0202 March 1973 Letter Responding to the February 1, 1973 Letter by Submitting Additional Information Relative to the Evaluation of the Environmental Report Accompanying the Petition for Conversion from Provisional to Full-Term Operating License ML17037C2841972-07-0707 July 1972 Letter Referring to July 5, 1972 Letter Transmitting an Application and Enclosing an Affidavit of Services 2023-11-10
[Table view] Category:Letter
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) 2024-08-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . NMP1L3519, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-30030 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3516, Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-03-29029 March 2023 Submittal of Emergency Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves2021-11-15015 November 2021 Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-06-0404 June 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 22021-01-27027 January 2021 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2 NMP1L3373, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 22021-01-22022 January 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 2 NMP2L2754, Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22021-01-0707 January 2021 Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 NMP2L2749, Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 22020-10-22022 October 2020 Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 2 NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-10-0202 October 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components2020-08-28028 August 2020 Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates2019-11-21021 November 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain2019-02-25025 February 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containm JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre2018-11-0202 November 2018 Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pres NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...2018-10-0101 October 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ... NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039) NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 September 2017 Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017 Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17037A2652017-02-0606 February 2017 Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16131A6542016-05-0404 May 2016 Response to a Question Raised During the Audit ML16131A6552016-05-0404 May 2016 White Paper Prepared in Response to a Question Raised During the Audit NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-03-21021 March 2016 Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual NMP1L3068, Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A....2016-01-25025 January 2016 Supplemental Information to Request for Additional Information - Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to A.... 2024-08-09
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{{#Wiki_filter:IThis letterthis forwards proprietary letter may information be considered in accordance non-proprietary uponwith 10 CFR removal of 2.390. The balance Attachment 3. of
~Exe~on Generation October 8, 2015 NMP2L 2602 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 Docket No. 50-410
Subject:
Response to Request for Additional Information - Nine Mile Point Nuclear Station, Unit 2 - Request for Additional Information Regarding Post Extended Power Uprate Steam Dryer Inspection Results
References:
(1) Letter from R. Guzman (NRC) to K. Langdon (NMPNS), dated December 22, 2011, Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendment RE: Extended Power Uprate (TAC No. ME1476)
(2) Letter from P. Swift (NMPNS) to Document Control Desk (NRC), dated July 28, 2014, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results in Accordance with Operating License Condition 2.C.(20)(f) and 2.C.(20)(g)
(3) Email from B. Vaidya (NRC) to T. Darling (NMPNS), dated August 13, 2014, Request for Additional Information, Nine Mile Point Unit 2, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results in Accordance with Operating License Condition 2.C.(20)(f) and 2.C.(20)(g)
(4) Letter from P. Swift (NMPNS) to Document Control Desk (NRC), dated October 3, 2014, Response to Request for Additional Information - Nine Mile Point Unit 2, Submittal of Post Extended Power Uprate Steam Dryer Inspection Results in Accordance with Operating License Condition 2.C.(20)(f) and 2.C.(20)(g)
(5) Letter from B. Mozafari (NRC) to P. Orphanos (NMPNS), dated August 5, 2015, Nine Mile Point Nuclear Station, Unit 2 - Request for Additional Information Regarding Post Extended Power Uprate Steam Dryer Inspection Results By letter dated December 22, 2011 (Reference 1), the NRC issued Amendment No. 140 to Renewed Facility Operating License No. NPF-69 for Nine Mile Point Unit 2 (NMP2). The amendment authorized an increase in the maximum steady-state reactor core powertlevel for NMP2 to 3,988 megawatts thermal (MWt). By letter dated July 28, 2014 (Reference 2), Nine Mile Point Nuclear Station (NMPNS) provided the steam dryer inspection results in accordance with NMP2 Operating License Condition 2.C.(20)(f) and 2.C.(20)(g). In Reference 3, the NRC requested additional information regarding the results of the steam dryer inspections documented in Reference 2. NMPNS provided a response to the RAIs in Reference 4.
This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of AD12~
pj(?f this letter may be considered non-proprietary upon removal of Attachments 3.
Response to Request for Additional Information October 8, 2015 Page 2 The supplemental information provided in the Attachments to this letter responds to the second request for additional information (RAI) documented by letter dated August 5, 2015 (Reference 5). As indicated via email, NMPNS agreed to submit the RAI responses by October 9, 2015. contains the nonproprietary responses to the RAIs. Attachment 3 contains the proprietary responses to the RAIs. Attachment 2 contains an affidavit to withhold Continuum Dynamics Inc. (CDI) proprietary information contained in Attachment 3.
There are no regulatory commitments contained in this letter.
Should you have any questions regarding the information in this submittal, please contact Dennis Moore, Site Regulatory Assurance Manager, at (315) 349-5219.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 8*" day of October, 2015.
Sincerely, Alexander D. Sterio Director - Site Engineering, Nine Mile Point Nuclear Station Exelon Generation Company, LLC ADS/BTV Attachments: (1) Response to Request for Additional Information (Nonproprietary)
(2) Affidavit Withholding Continuum Dynamics Inc. (CDI) Proprietary Information (3) Response to Request for Additional Information (Proprietary) cc: Regional Administrator, Region I, USNRC Project Manager, USNRC Resident Inspector, USNRC
Attachment 1 Response to Request for Additional Information (Nonproprietary)
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Mechanical and Civil Engineering Branch (EMCB)-NMP2-MF4559-SD-First RFO Post EPU-RAI-4 The licensee has installed the bolted U-channel attached to upper dryer inner side plates connected to inner vane banks to structurally stiffen the steam dryer such that the minimum alternating stress ratio (SR-a) becomes greater than 2.0. The staff is requesting the following clarification regarding the implemented retrofit:
- a. Please provide a comparison of stress ratios (SR-P and SR-a) for the 54 nodes listed in Table 17 (CDI Report 14-08P, Rev. 0) for the dryer with and without the U-channel stiffener and subject to N59 load (Drain Trap out of service).
- b. For the stiffened steam dryer, please provide cumulative stress distributions for the five locations on both the hood and skirt with the SR-a.
- c. Explain how dryer alternating stresses due to Reactor Recirculation Pump (RRP) Vane Passing Frequency (VPF) tones are accounted for in the modified NMP2 dryer. The dryer structural modes may have shifted due to the addition of the U-channel so some may now align with VPF.
Part a The estimated stresses with and without the U-channel stiffeners for the outN59 load are reported in Table 1. The results without the stiffeners are taken directly from Table 17 in [1]. The stresses for the case with the stiffeners added are generated using the same method described in Appendix B of [1]. Only locations located on or near the reinforced inner side plate are shown since these are the only locations for which the scaling technique used to estimate stresses over the full 0-250 Hz range with U-channel stiffeners added, is valid. Recall that (see Appendix B in [1]) the unit solution stresses with the U-channel stiffeners are only generated over the 60-130 Hz range. To estimate the stress for the full frequency range, an adjustment factor f=S(60,130)/S(0,250) is calculated for the model without the U-channel stiffener where S(fl,f2) is the stress intensity computed using only the unit solutions in the frequency interval [fl,f2] Hz. The stress ratios with the U-channel stiffener included are then estimated by multiplying the stress ratio computed for the 60-130 Hz frequency range, by the factor f. For locations "near" the stiffener this approach works well because: (i) the 60-13 0 Hz frequency range was determined to make the largest contribution to the stresses involving the side plate and its attachment welds; and (ii) the stress ratios on these welds and components, with the stiffener are well above the target value of 2.0 so that use of the approximate scaling approach is acceptable. At locations farther away from the reinforced inner side plate a simple scaling is not necessarily applicable particularly if other frequencies outside the 60-130 Hz interval significantly affect local stress or if the stress ratios are already near the target value of 2.0 so that a more accurate analysis is required to obtain stress ratios to achieve higher precision (i.e., on the order of ASR-a=(SR-a -2)).
I (3)
Page 1 of 34
Attachment 1 Response to Request for Additional Information CNonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information r[
(3)]]
Page 2 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Table 1. Comparison of SR-P and SR-a obtained with and without the U-channel stiffeners (see Note (1)), using the N59 load (drain trap out of service) condition.
Entry Node no stiffener with stiffener(i)
SR-P SR-a SR-P SR-a 1 37229 2.5 5.9 2.5 5.9 2 113286 3.3 3.1 3.3 2.8 3 37592 4.9 3.0 12.9 12.2 4 94143 1.5 4.9 1.4 4.1 5 85191 1.8 3.5 6 143795 1.7 4.0 7 113508 2.2 4.0 2.1 3.6 8 98968 1.8 3.2 9 94498 2.1 4.8 10 90468 2.0 3.6 11 101600 2.6 2.6 2.7 3.0 12 88639 1.8 3.0 13 92995 2.5 3.2 14 141237 2.1 3.7 2.0 3.3 15 89317 2.1 6.0 16 87784 4.0 2.6 17 94509 3.4 2.2 18 99635 2.6 2.4 2.7 2.5 19 99200 1.7 2.5 1.6 2.2 20 113554 1.7 2.9 1.7 2.9 21 103080 2.9 2.1 22 113400 3.0 3.0 2.8 2.9 23 95267 1.8 2.3 2.2 2.2 24 90786 1.4 2.4 25 137575 2.0 2.2 26 95172 2.5 6.6 27 91055 3.5 2.0 3.5 2.1 28 93488 3.1 2.9 29 98956 2.0 2.4 30 85631 1.4 2.9 Note: (1) Only locations near to or involving the reinforced side plate are shown.
Page 3 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Entry Node no stiffener with stiffener(1)
SR-P SR-a SR-P SR-a 31 101818 2.6 2.9 32 98624 3.0 2.9 33 94514 4.1 2.7 34 95428 1.5 2.5 35 84090 2.3 2.9 36 99451 2.3 3.1 37 93451 5.2 2.8 38 98172 2.1 3.1 39 90924 3.8 3.1 40 100989 4.7 2.8 11.2 8.9 41 90926 5.2 3.3 42 99931 5.7 3.1 43 91091 1.9 3.3 1.8 2.9 44 88702 2.5 6.4 MIN (1-44) 1.4 2.0 Locations near top of inner vane bank/side plate/tie bar junction 45 101861 3.1 1.8 7.4 4.9 46 95197 3.2 1.7 5.9 3.5 47 99407 2.8 2.4 3.4 3.4 48 98442 3.1 1.8 6.1 4.1 49 98444 2.9 1.8 5.6 5.0 50 98451 3.3 1.7 6.7 3.8 51 98452 2.5 1.9 4.4 5.2 52 99408 3.3 2.0 7.8 6.0 53 91240 2.6 2.1 4.3 5.5 MIN (45-53) 2.5 1.7 3.4 3.4 Added Real Time Node (Non Weld) 54 91651I 4.6 12.4 I 5.0 5.8 MIN (overall)] 1.4 1 .7.
Note: (1) Only locations near to or involving the reinforced side plate are shown.
Page 4 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Part4b As explained in Section 5.8 of [1], unit solutions with the U-channel stiffener were developed over the frequency interval 60-130 Hz. Since the mesh and node numbering on the dryer models with and without the U-channel stiffener differ, the following approach is used to generate the PSDs and cumulative PSDs requested in the RAI. First, the node locations closest to the ones in Section 5.6 of
[1] where the PSDs were produced, are identified. Next PSDs are developed for the entire frequency range with the steam dryer model without the U-channel stiffeners. Also, PSDs over the 60-130Hz frequency range are developed with the U-channel stiffeners in place. The latter results are then used to overwrite those in the 60-130Hz range that were obtained without the U-channel stiffeners. Thus one has a composite PSD distribution consisting of: (i) the original dryer model without U-channel stiffeners (0-60Hz and 130-250Hz), and (ii) the modified dryer model with U-channel stiffeners (60-130 Hz). Finally, the cumulative PSDs are obtained by integrating the PSD curves.
Note that to facilitate comparison between the results of Section 5.6 in [1] and the ones generated here, the same frequency shifts and stress components are plotted. Since the RAI asks for results pertaining to load N59, the plots and limiting frequency shifts will generally differ from those in Figure 21 of [1] which were generated for the baseline N55 load. Note additionally, that in Section 5.6 of [1] no nodes on the skirt were plotted. Since a location on the skirt is mentioned in the RAI, an additional location is plotted for entry 37 (node 93451) which is the location with the lowest alternating stress ratio involving the skirt identified in Table 17 of [1] (see also response to Part 4a, above). This node lies at the bottom of a weld connecting the drain channel to the skirt.
For each of the six locations, the cumulative PSD curves are shown for the steam dryer with the U-channel stiffeners subject to the N59 load. For the location on the skirt, the stress without the stiffeners is also shown since it was not presented previously in [1]. In general, adding the stiffeners either reduces stresses (for locations near the reinforced inner plates) or essentially leaves them unchanged (elsewhere). Any remaining differences between the prior cumulative PSDs can be attributed: to differences in loads (N55 or Baseline in [1] and N59 in the curves shown here in Figure 1); discretization on different meshes and small, but non-zero changes in response at locations away from the reinforced inner side plate.
Page 5 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Node 101861, o, +7.5% shift 350 300 250 Co 0q 200 d1 co 150 E
100 0*
50 0 50 100 150 200 250 Frequency [ Hz ]
Figure la. Cumulative PSD of stress at node 101861 with stiffener at limiting frequency shift.
Node 91651, *y, +2.5% shift 1000 800 Co 0q 600 (U
400 E
0 200 0 50 100 150 200 250 Frequency [ Hz ]
Figure lb. Cumulative PSD of stress at node 91651 with stiffener at limiting frequency shift.
Page 6 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Node 94509, * , +10% shift 500 400
°.0~
300 200 E
0) 100
.* * ....... J*............. .1. ........
0 50 100 150 200 250 Frequency [ Hz ]
Figure ic. Cumulative PSD of stress at node 94509 with stiffener at limiting frequency shift.
Node 99200, *z, +5% shift 450 400 350 0.
300 oo 03 250 200 (U
E 150 0D 100 50 0 50 100 150 200 250 Frequency [ Hz ]
Figure ld. Cumulative PSD of stress at node 99200 with stiffener at limiting frequency shift.
Page 7 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Node 95267, ax +10% shift 700 600 0M 500 dq Co 400 03 (0 300 E
200 100.
050 100 150 200 250 Frequency [ Hz ]
Figure le. Cumulative PSD of stress at node 95267 with stiffener at limiting frequency shift.
Node 93451, a,' +10% shift 800 700 0* 600 500 P4 400 300 E
2O00 100 0 50 100 150 200 250 Frequency [ Hz]
Figure if. Cumulative PSD of stress response at node 93451 with & w/o stiffener at limiting frequency shift.
Page 8 of 34
Attachment I Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Part4c The original evaluation considered the effect of the U-channel stiffener over the 60-130 Hz frequency range as this was the interval making the dominant stress contribution to high stress locations on or near the inner side plates. Since the effect of the U-channel stiffener is localized and contributes minimally at more distant locations it was reasoned that for frequencies outside the 60-130 Hz range, stresses could be approximately accounted for by using the stress results without the U-channel in place. Thus, for distant locations the change in stress due to the stiffener is neglected; whereas for locations near the stiffener, the stress reduction obtained by reinforcement using the U-channel is only credited over the 60-13 0 Hz range so that the final result is conservative.
A potential concern exists as to whether the VPF tone (occurring at 149 Hz) may excite the modified dryer. The specific concerns are two fold: (i) Does the addition of the U-channel affect the stress field at locations away from the inner plate? (ii) Has the addition of the U-channel shifted a mode of the inner plate into the vicinity of the 149 Hz VPF frequency raising the possibility of resonant forcing of this mode?
To address these concerns the unit solution stress response due to a unit (1 psi) monopole pressure over the entrance to MSL A was calculated at 149.4 Hz both with and without the U-channel stiffener. In order to facilitate comparison between stresses, the exact same mesh and finite element set was used for both cases. [[
,*]] However, since the node and element numbering did not change direct comparison of stresses is easily done.
The unit solution stress maps obtained with and without the U-channel stiffeners are virtually identical everywhere except near the stiffeners. In each case the maximum stress occurs at lifting rod brace; the difference between these maximum stress values is less than 1%. Since the meshes are identical the stress results can be readily subtracted from one another within ANSYS. Thus, if
[a]s is the stress tensor with the stiffeners applied and [a]0 is the stress tensor without the stiffeners, one can readily form A[a] =[a]s- [a] 0 . Figure 2 plots the stress intensity SI{[Aar]} obtained by applying the stress intensity operator to the stress difference A[a]. The plot shows that except for the inner plate itself and the nearby structure it is attached to, the stress differences are negligible. No additional modes are excited away from the inner plate.
Page 9 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information NODAL SOLUTION ANSYS 14.0 STEP=9999 SINT (AVG)
DMX =. 00146 514N =.01244 SMX =1956.14 100 300 500 Figure 2. Stress intensity SI{[Aa]} formed form the stress difference tensor obtained from the dryer with and without stiffeners at 149.4 Hz.
Figure 3 plots the difference between the stress intensities with and without the U-channel stiffeners, ASI=SI{[a]s}-SI{[a] 0 } in the vicinity of the inner side plates. The stress differences are plotted on both the upper and lower surfaces of the shell elements and indicate a maximum stress intensity increase of 571 psi. On the middle plane of the shell elements (i.e., the membrane stress) the maximum stress intensity increase is 270 psi. Note however, that these stress increases occur at locations away from the high stress welds that the stiffeners were intended to alleviate. At those locations (near the top of the inner side plates) the stresses are either unchanged or reduced by the addition of the stiffeners.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Referring to the unfiltered MSL strain gage measurement data (where VPF has not been removed) in [2] the highest pressure measurement near 149 Hz is found to occur at the upper strain gage location in MSL A. The pressure PSD of this signal is reproduced in Figure 4 and estimated to have a 149 Hz peak of approximately 7x10 4 psi 2 /Hz. Assuming a SHz width for this peak one can estimate an RMS pressure over this interval of PRMS=[(7x10- 4 )x5/2]1/2 = 0.042 psi. Multiplying the maximum stress difference in the unit solution by this amount implies a change in stress of 0.042x571=23.9 psi. This is the estimate of the change in stress on the dryer due to the MSL exhibiting the highest peak at 149 Hz. If all MSLs make the same contribution to the stress (a conservative assumption since the other MSLs have smaller peaks at 149 Hz), and these contributions are combined additively (also a conservative estimation that assumes all MSLs contributions are in phase) then the net increase in RMS stress becomes Srms = 4x0.0239 ksi = 0.1 ksi occurring at a location that currently does not experience significant stress. One can estimate the peak stress Speak from RMS stress using Speak=21/2Srms=0.14 ksi, which is 1% of the allowable stress margin (13.6 ksi). Therefore the stress change anywhere on the inner plate or its connecting components when adding back in VPF is generally negligible.
Furthermore, at the high stress locations involving the upper connections of the inner side plate the stresses are either the same as or less than those without the reinforcement U-channel so that the stress contributions from this 149 Hz frequency are conservatively bounded by the no-stiffener results.
Reernce
- 1. Continuum Dynamics, I. (2014) Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP. C.D.I. Report No. 14-08P (Proprietary), July.
- 2. Continuum Dynamics, I. (2014) Acoustic and Low Frequency Hydrodynamic Loads at 115% CLTP Target Power Level on Nine Mile Point Unit 2 Steam Dryer to 250 Hz Using ACM Rev. 4.1R. C.D.I.
Report No. 14-09P (Proprietary), December.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Figure 3. Difference, ASI=SI{[a]s}-SI{[ca] 0}, between the stress intensities with and without the stiffeners. Top - stress on upper surface of shell shell top; bottom - stress on lower surface.
Maximum stress increase is 571 psi.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information NMP2: Unfiltered Data 0.1 MSL A Upper 0.01 MSL A Lower_
-o 0.001 0.0001 2
10-5 0 50 100 150 200 250 Frequency (Hz)
Figure 4. PSDs of unfiltered pressure measurements at EPU at the upper and lower measurements stations of MSL A (taken from [2]).
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information EMCB-NMP2-MF4559-SD-First RFO Post EPU-RAI-5
[[
(3)]] The staff has reviewed these reports and results from the reports have been used in subsequent steam dryer analyses. [[
(3) ]] The formal response follows.
1Parta Table 1 compares the stress ratios with and without [[
(3)]] for the configuration without the U-channels installed and N59 load. The locations are the same as Table 17 in CDI stress report 14-08 [1] and indicate a minimum alternating stress ratio of SR-a= 1.2.
[[I References
- 1. Continuum Dynamics, I. (2014) Stress Re-Evaluation of Nine Mile Point Unit 2 Steam Dryer at 115% CLTP. C.D.I. Report No. 14-08P (Proprietary), July.
Page 14 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Table 1. Alternating stress ratios obtained at 54 locations: (i) with [[
(3)]] Results are without U-channel stiffeners installed and for the load N59
[1].
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information EMCB-NMP2-MF4559-SD-First RFO Post EPU-RAI-6
i (3) The staff is requesting the following clarifications related to the modified ACM 4.1 code (ACM 4.1R code) and the associated Main Steam Line (MSL) signals.
- a. Explain why the unfiltered lower MSL C strain gage PSD is so much higher than those of MSL A, B, and D. (See Figures 3.1 a, b and 3.2 A, b in CDI Report 14-09P). Confirm the data acquisition and calibration settings, along with the matching of strain gages and channel numbers.
Part 6a Our review confirmed the data acquisition and calibration settings, along with the matching of strain gages and channel numbers. It may therefore be concluded that the signal contents of MSL C lower were due to actual pressure fluctuations inside the MSL piping. In fact, Figure RAI-6.1 shows that MSL A lower exhibits peak PSD values nearly identical to MSL C lower at frequencies below 25 Hz, not supporting the statement that the MSL C lower strain gage PSD is so much higher than the other three lower strain gage PSDs. We concur that the noise floor of MSL C lower is higher by about a factor of two on the PSD, but have no explanation for this difference.
NMP2: MSL Signals 0.1 N* 0.01 Cl
-oq 0.001 0.0001 10.5 0 50 100 150 200 250 Frequency (Hz)
Figure RAI-6.1: Unfiltered data measured on the NMP2 MSLs at 115% CLTP conditions.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- b. Explain the cause(s) of the sharp (at approximately 125 Hz) peaks in the PSDs of MSL D.
Part 6b Figure RAI-6.2 compares the 123.5 Hz peaks on MSL D at Nine Mile Point Unit 2 to the standpipe excitation peaks at 151 Hz on MSL D at Quad Cities Unit 2.
Figure RAI-6.2: Comparison of peaks seen in Quad Cities Unit 2 around 151 Hz (black curve) to peaks seen in Nine Mile Point Unit 2 around 123.5 Hz (red curve). The peaks are shifted in frequency by 151 Hz for QC2 and by 123.5 Hz for NMP2. The frequency resolution is better than 0.02 Hz.
An examination of the MSL D piping drawings at NMP2 identified numerous drain lines coming off the MSL. Four typical drain lines are compared to the standpipe lengths of the Dresser valves at QC2 in Table RAI-6.1.
Table RAI-6.1: Comparison of standpipe and drain lines between QC2 and NMP2 Dimension QC2 (standpipes) NMP2 (drain lines)
Pipe Diameter 5.76 inches 1.7 inches Pipe Length(s) 2.65 feet (nominal) 8.1, 10.8, 10.9, and 11.1 feet Each MSL at QC2 has two Dresser safety valves where, before the addition of acoustic side branches, their shear-layer-driven vortex shedding frequency was around 151 Hz. Figure RAI-6.2 was generated with higher frequency resolution than is typically done for PSD plots, so that three distinct peaks can be identified. These peaks can also be seen in the other three MSLs and reflect small variations about the nominal length of the field-installed standpipes as given in Table RAI-6.1. It can also be noted from the QC2 PSD that the signal increases by over three orders of magnitude over the baseline of 0.01 psid 2/Hz to 30 psid 2/Hz at the largest peak.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
[3[]
Since there was no apparent reason for excluding the peak, this signal was not filtered from the MSL data and its load was used in the dryer structural analysis.
Reference
- 1. S. Ziada and S. Shine (1999) Strouhal Numbers of Flow-Excited Acoustic Resonance of Closed Side Branches. Journalof Fluids and Structures 13: 127-142.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- c. The iicensee is requested to confirm the labeling of the ACM 4.1 and ACM 4.1R curves in Figures C.la and C.lb to ensure that they are not interchanged. Explain the differences in the sharp peaks near 130 Hz in the Quad Cities Unit 2 (QC2) ACM 4.1 and 4.1R simulations (P3 and P12). [[
Part 6c The labeling of the ACM 4.1 and 4.1R curves in Figures C.la and C.lb is correct, referencing C.D.I. Report No. 10-09, "ACM Rev. 4.1 Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements." [[
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Attachment 1 Response to Request for"Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- d. [[
Part 6d(i)
(3)]]
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary information Figure RAI-6.3: Comparison of ACM 4.1 and 4.IR predictions on the NMP2 dryer at 115%
CLTP power for normal EPU operation: on the outer bank hood opposite MSL C and D (top); on the inner bank hood opposite MSL C and D (bottom).
Page 21 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, inc. Proprietary Information (ii). [[
(3)]]
Part 6d(ii)
(3)]]
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- e. [[
Part Ge The filtered signals shown in Figure 3.4a to d of C.D.l. Report No. 14-09 were taken from the wrong data file. Figures 3.4a to d should have compared the unfiltered signals from Figure 3.1a to d with the filtered signals from Figure 3.3a to d, as shown in the following Figure RAI-6.4a to d.
The filtered signals were used correctly as input into the ACM Rev. 4.1R analysis (defining the steam dryer loads) and the subsequent structural analysis (defining the steam dryer stresses).
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
I (3)
Figure RAI-6.4a: Unfiltered and filtered data comparisons on NMP2 main steam line A at 115%
CLTP target power conditions for upper (top) and lower (bottom) locations.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Figure RAI-6.4b: Unfiltered and filtered data comparisons on NMP2 main steam line B at 115%
CLTP target power conditions for upper (top) and lower (bottom) locations.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Figure RAI-6.4c: Unfiltered and filtered data comparisons on NMP2 main steam line C at 115%
CLTP target power conditions for upper (top) and lower (bottom) locations.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
[[)j Figure RAI-6.4d: Unfiltered and filtered data comparisons on NMP2 main steam line D at 115%
CLTP target power conditions for upper (top) and lower (bottom) locations.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information EMCB-NMP2-MF4559-SD-First RFO Post EPU-RAI-7
- a. [[
Part 7a Recent changes in plant operation have impacted the loads at 89.3 and 92.5 Hz shown in C.D.I.
Report No. 14-09. These changes are the following:
89.3 Hz - RCIC Valve Closed data were previously obtained by closing the inboard MOV on the RCIC line. The isolation valves were closed during periodic surveillances and the plant entered the RCIC out of service LCO. Recent revisions in the surveillance procedures eliminate the need to close the isolation valves during these periodic surveillances, reducing the frequency during which the plant is operated with the isolation valve closed. The closing of the isolation valves will occur only during periods of time where maintenance is required, with the duration restricted to the RCIC out of service limiting condition for operation, which is 14 days.
(3)]
Figure RAI-7.1: Comparison of peaks seen in Quad Cities Unit 2 around 151 Hz (black curve) to peaks seen in Nine Mile Point Unit 2 around 89.3 Hz (red curve) for RCIC Valve Closed. The peaks are shifted in frequency by 151 Hz for QC2 and by 89.3 Hz for NMP2. The frequency resolution is better than 0.02 Hz.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information 92.5 Hz - This condition was observed when the RCIC Drain Trap was bypassed. Investigation into this condition determined that the RCIC drain line that connects to the RCIC steam inlet correlates to this condition. When the drain trap is functioning such that a steady steam flow exists in the drain line, versus a standing water leg in the drain line, the signal at 92.5 Hz is reduced. The normal plant operating condition for the RCIC turbine inlet steam line has steam flow through the drain trap, which is represented as the EPU baseline steam dryer loading. This baseline is considered the normal steady state EPU steam dryer load profile.
(3)]]
Page 29 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information (3[j Also, with regard to the last sentence in the RAI, it has been determined that strain gage channel 4 at the MSL A upper location should have been removed from the RCIC analysis. The inclusion of the signal from this channel is responsible for the additional noise seen in Figure A.2a of C.D.I. Report No. 14-09, reproduced here as Figure RAI-7.4 (top). The corrected signal is shown in Figure RAI-7.4 (bottom).
The removal of this channel from MSL A upper does not impact any of the other calculations provided in C.D.I. Report No. 14-09. Figure A.la from the report shows the consistent behavior of the MSL A upper pressure throughout power ascension. Further investigation, from Table A.1 of C.D.I. Report No. 14-09, can be seen to explain the problem. All of the data collected throughout power ascension and RCIC examination were taken in April and May 2012, with the exception of the ROIC valve closed data at 115% CLTP, taken in September 2012. By this time strain gage channel 4 must have degraded.
Reference
- 1. Continuum Dynamics, Inc. (2014). Computation of Cumulative Usage Factor for the 115%
CLTP Power Level at Nine Mile Point Unit 2 with the Inboard RCIC Valve Closed. C.D.I.
Technical Note No. 14-04P.
Page 30 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, inc. Proprietary Information (3)]
Figure RAI-7.3: Curves for MSL B at 115% CLTP target power conditions, with RCIC drain trap out-of-service (black curves) compared with the corresponding normal EPU operation curves (red curves for data taken on 24 May 2013, blue curves for data taken on 06 August 2015). The curves are nearly identical except at a narrow band around the peak at 92.5 Hz in the 2013 data.
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Attachment 1 Response to Request for Additional information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information Figure RAI-7.4: Curves for MSL A upper with the inboard RCIC valve closed, for target power levels 105% CLTP (black curves), 110% CLTP (red curves), and 115% CLTP (blue curves).
Top: strain gage channel 4 included in MSL A upper; bottom: strain gage channel 4 excluded in MSL A upper.
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Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- b. [[
(3)]]
Part 7b
[[)j Page 33 of 34
Attachment 1 Response to Request for Additional Information (Nonproprietary)
This Document Does Not Contain Continuum Dynamics, Inc. Proprietary Information
- c. [[
(3)]]
Part 7c Page 34 of 34
Attachment 2 Affidavit Withholding Continuum Dynamics Inc. (CD I) Proprietary Information
<z~JIg~ Continuum Dynamics, Inc.
(609) 538-0444 (609) 538-0464 fax 34 Lexington Avenue Ewing, NJ 08618-2302 AFFIDAVIT RE: C.D.J. Response to Request for Additional Information (RAI), Exelon Generation Company, Nine Mile Point Nuclear Station, Unit 2 (NMP2), Post Extended Power Uprate, Steam Dryer Inspection Results, Docket No. 50-4 10 (TAC NO. MF45 59)
I, Alan J. Bilanin, being duly sworn, depose and state as follows:
- 1. I hold the position of President and Senior Associate of Continuum Dynamics, Inc. (hereinafter referred to as C.D.I.), and I am authorized to make the request for withholding from Public Record the Information contained in the document described in Paragraph 2. This Affidavit is submitted to the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 2.390(a)(4) based on the fact that the attached information consists of trade secret(s) of C.D.I. and that the NRC will receive the information from C.D.J. under privilege and in confidence.
- 2. The Information sought to be withheld, as transmitted to Exelon Corporation as attachment to C.D.I. Letter No. 15054 dated 25 September 2015, C.D.I. Response to Request for Additional Information (RAI), Exelon Generation Company, Nine Mile Point Nuclear Station, Unit 2 (NMP2), Post Extended Power Uprate, Steam Dryer Inspection Results, Docket No. 50-410 (TAC NO. MF4559). The proprietary information is identified by its enclosure within pairs of double square brackets ("[[ ]]"). In each case, the superscript notation (3)refers to Paragraph 3 of this affidavit that provides the basis for the proprietary determination.
- 3. The Information summarizes:
(a) a process or method, including supporting data and analysis, where prevention of its use by C.D.I. 's competitors without license from C.D.I. constitutes a competitive advantage over other companies; (b) Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product; (c) Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs 3(a), 3(b) and 3(c) above.
- 4. The Information has been held in confidence by C.D.I., its owner. The Information has consistently been held in confidence by C.D.I. and no public disclosure has been made and, it is not available to the public. All disclosures to third parties, which have been limited, have been
made pursuant to the terms and conditions contained in C.D.I.'s Nondisclosure Secrecy Agreement which must be fully executed prior to disclosure.
- 5. The Information is a type customarily held in confidence by C.D.I. and there is a rational basis therefore. The Information is a type, which C.D.I. considers trade secret and is held in confidence by C.D.I. because it constitutes a source of competitive advantage in the competition and performance of such work in the industry. Public disclosure of the Information is likely to cause substantial harm to C.D.I.'s competitive position and foreclose or reduce the availability of profit-making opportunities.
I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to be the best of my knowledge, information and belief.
Executed on this &* -dayof *- '-ye*-z*, 2015.
Alan J. Bilanin Continuum Dynamics, Inc.
Subscribed and sworn before me this day: *-'*f -- C.
en*urmei//tdeotary Pbl**-*
EILEEN PBURMEISTER NOTARY PUBLIC STATE OF NEW JERSEY My Commission Expires May 06,2017}}