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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: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) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 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 ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 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 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 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 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 2024-08-09
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This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachment 4.
Ken Langdon P.O. Box 63 Vice President-Nine Mile Point Lycoming, New York 13093 315.349.5205 315.349.1321 Fax CENGS.
a joint venture of 0 Constellation <nergy'leDF Energy- &1 NINE MILE POINT NUCLEAR STATION November 1, 2011 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 License Amendment Request for Extended Power Uprate Operation - Supplemental Information Responding to Open Items from the Review by the Advisory Committee on Reactor Safeguards Subcommittee on Power Uprates and Related NRC Staff Questions (TAC No. ME1476)
REFERENCE:
(a) Letter from K. J. Polson (NMPNS) to Document Control Desk (NRC), dated May 27, 2009, License Amendment Request (LAR) Pursuant to 10 CFR 50.90:
Extended Power Uprate By letter dated May 27, 2009 (Reference a), as supplemented, Nine Mile Point Nuclear Station, LLC (NMPNS) proposed an amendment to Nine Mile Point Unit 2 (NMP2) Renewed Operating License (OL)
NPF-69 that would increase the power level authorized by OL Section 2.C.(1), Maximum Power Level, from 3467 megawatts-thermal (MWt) to 3988 MWt. The application for the NMP2 extended power uprate (EPU) was subsequently reviewed by the Advisory Committee on Reactor Safeguards (ACRS)
Subcommittee on Power Uprates at a meeting held on October 5, 2011. During that meeting, NMPNS indicated that answers to certain ACRS questions (hereafter referred to as open items) would be provided prior to the full ACRS committee review of the NMP2 EPU application, which is scheduled for November 3, 2011. to this letter provides the NMPNS responses to the open items, as clarified by the additional information communicated to NMPNS in a conference call with the NRC staff on October 20, 2011. In addition, certain open items and related NRC staff questions indicate the need for NMPNS to: (1) confirm the basis for the EPU environmental qualification, and (2) provide regulatory commitments regarding This letter forwards proprietary information in accordance with 10 CFR 2.390. The balance of this letter may be considered non-proprietary upon removal of Attachment 4.
Document Control Desk November 1, 2011 Page 2 (a) fatigue monitoring and (b) steam dryer analysis during the EPU power ascension. This additional information is provided in Attachments 1 and 2, respectively. (proprietary) provides Continuum Dynamics, Inc. (CDI) Technical Memo No. 11-24NP, "Nine Mile Point Velocity Squared Data Analysis," Revision 2 (Proprietary) to support the response to certain open items in Attachment 1. Attachment 4 is considered to contain proprietary information exempt from disclosure pursuant to 10 CFR 2.390. CDI has requested that this document be considered proprietary in its entirety; thus, a non-proprietary version is not provided. Therefore, on behalf of CDI, NMPNS hereby makes application to withhold Attachment 4 from public disclosure in accordance with 10 CFR 2.390(b)(1). The affidavit from CDI detailing the reasons for the request to withhold the proprietary information is provided in Attachment 3.
Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.
Very truly yours, STATE OF NEW YORK TO WIT:
COUNTY OF OSWEGO I, Ken Langdon, being duly sworn, state that I am Vice President-Nine Mile Point, and that I am duly authorized to execute and file these responses on behalf of Nine Mile Point Nuclear Station, LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Nine Mile Point employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.
Subscribed and sworn before me, a Notary Public in and for the State of New York and County of
- .Q .this _ dayof blNq bc4r" ,2011.
WITNESS my Hand and Notarial Seal: ( .
Notary Public My Commission Expires:
Date KL/JEB hbftM&l m Mt1*aslateNNAM 09wep County PA9. ft 81008== l myconnds"OphutAgms
Document Control Desk November 1, 2011 Page 3 Attachments:
- 1. Responses to Open Items from the Review by the ACRS Subcommittee on Power Uprates and Related NRC Staff Questions
- 2. List of Regulatory Commitments
- 3. Affidavit from Continuum Dynamics, Inc. Justifying Withholding Proprietary Information
- 4. Continuum Dynamics, Inc .Technical Memo No. 11-24NP, Nine Mile Point Velocity Squared Data Analysis, Revision 2 (Proprietary) cc: NRC Regional Administrator, Region I NRC Resident Inspector NRC Project Manager A. L. Peterson, NYSERDA (w/o Attachment 4)
ATTACHMENT 1 RESPONSES TO OPEN ITEMS FROM THE REVIEW BY THE ACRS SUBCOMMITTEE ON POWER UPRATES AND RELATED NRC STAFF QUESTIONS Nine Mile Point Nuclear Station, LLC November 1, 2011
ATTACHMENT 1 RESPONSES TO OPEN ITEMS FROM THE REVIEW BY THE ACRS SUBCOMMITTEE ON POWER UPRATES AND RELATED NRC STAFF QUESTIONS The following are responses to open items from the review of the Nine Mile Point Unit 2 (NMP2) extended power uprate (EPU) license amendment request by the Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Power Uprates, as clarified by the additional information communicated to Nine Mile Point Nuclear Station, LLC (NMPNS) in a conference call with the NRC staff on October 20, 2011. Each open item is stated (in italics), followed by the NMPNS response.
Open Item 1 Does the result of 1/8th scale test merely confirm that the existing standpipe/valves do not begin excitation until past EPU conditions? Isn't it also being used in calculating the bump-up factor (BUF) which was used to scale up the loadfrom CurrentLicensed Thermal Power (CLTP) to EPU conditions?
(CDI 08-13P described detailedtests in a 1/8th scale model. It also suggested that NMPNS use a BUF of 1.39 when scalingplant steam line datafrom CLTP to EPUpower.)
NMPNS Response In Section 1.0 of Attachment 13 to the NMP2 EPU license amendment request (NMPNS letter dated May 27, 2009), NMPNS indicated that the NMP2 steam dryer has been evaluated for EPU steam flow conditions consistent with the guidance provided in BWRVIP-182, "Guidance for Demonstration of Steam Dryer Integrity for Power Uprate," issued January 2008, including the response to the NRC request for information in April 2009. The BWRVIP-182 guidelines require screening for acoustic resonances.
The guidelines indicate that when no acoustic resonances exist, the expected EPU scaling is main steam line (MSL) velocity squared. 3 included a description of the confirmatory 1/8h scale test, which was designed to confirm the screening calculations. CDI test report 08-13P includes a summary of the testing results, and an overall conclusion that the results support a bump-up factor (BUF) consistent with velocity squared.
Figures 8.1 through 8.8 of CDI test report 08-13P were not designed or intended to represent the demonstration of the velocity squared scaling.
Figure 9.1 of CDI test report 08-13P was revised by the NMPNS response to NMP2-EMCB-SD-RAI SO1 submitted by NMPNS letter dated November 5, 2010. The revised Figure 9.1 evaluates the test data in the velocity range applicable for NMP2 EPU. The data show scaling consistent with velocity squared.
A review of the data provided in CDI report 08-13P is documented in CDI Technical Memo TM-i 1-24P, which is included in Attachment 4 herein. The report shows that the 1/8th scale test results in the velocity range for the NMP2 EPU indicate that a velocity squared scaling is appropriate. CDI Technical Memo TM-11-24P includes additional data from the NMP2 plant full scale data and from a similar plant's full scale EPU data. These full scale data provide additional confirming evidence that velocity squared scaling is appropriate in the absence of an acoustic resonance.
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ATTACHMENT 1 RESPONSES TO OPEN ITEMS FROM THE REVIEW BY THE ACRS SUBCOMMITTEE ON POWER UPRATES AND RELATED NRC STAFF QUESTIONS Open Item 2 Confirm BUF and V squared (W2) relationshipwith plant data.
According to Dr. Wallis, the dataprovided in Figure 8.1 of CDI 08-13P reveals that the power law that best fits all the data has an exponent significantly greater than 2. It appears that the BUF can be determined in different ways, leading to a significant variation in the predicted loads on the dryer. The staff or the industry should determine what were the actualBUFs obtainedfrom steam line strain gages in the several plants (e.g., Quad Cities, Vermont Yankee, Susquehanna, and Hope Creek) that have already implemented EPUs similarto NMP2.
NMPNS Response CDI-TM- 11-24P (Attachment 4 herein) provides a summary of the NMP2 full scale data and a similar plant's full scale EPU data. In addition, NMP2 has reviewed proprietary information for two other BWR EPUs and confirmed that the scaling for these plants, like the full scale data in Attachment 4, was also bounded by a velocity squared assumption.
Open Item 3 The licensee stated that as part of steam dryer modifications, there areplates with 1/8" thickness that will be welded to the inner hood and middle hood, to shift the frequency, such that the hood supports can meet their established 100% stress margin at EPU conditions. The licensee stated that the plates will be welded along three edges, but the bottom edge will not be welded. The licensee did not have a readily available answerfor Member Abdel-Khalik's question regardingthe length of the unwelded part of this coverplate.
NMPNS Response The statement regarding welding of the 1/8" plates provided at the ACRS subconmmittee meeting was incorrect. The current design of the 1/8" hood re-enforcement plate includes a 360 degree weld. There are no unwelded edges.
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ATTACHMENT 1 RESPONSES TO OPEN ITEMS FROM THE REVIEW BY THE ACRS SUBCOMMITTEE ON POWER UPRATES AND RELATED NRC STAFF QUESTIONS Open Item 4 NMPNS used embedded models to obtain more accurate results for alternate stress intensities at high-stress locations. In the embedded model, a small portion of the global model (shell element) including a high stress location is replaced by a solid element mesh, which explicitly models the local welds, if present. The licensee did not have a readily available answerfor Member Abdel-Khalik's questions: Are the nodes near the interface between the two regions highly skewed, or are there typically reasonable aspect ratiosfor the nodes? Are aspect ratios within the allowable limits of the ANSYS code?
NMPNS Response The nodes near the interface between the global model shell elements and the embedded model solid elements are consistent with ANSYS guidelines. According to the ANSYS basis documents, one particular shape metric predicts whether the quality of the element would affect the numerical solution time and accuracy. The figure of merit is the calculation of the Jacobian ratio at the integration points of the element. At a certain level of the Jacobian ratio, the ANSYS development team determined that the element solution would degrade and produce an unacceptable result. In particular, a Jacobian ratio of 40 was set to be the error level. The ratio of 10 was assigned a warning level. While many other shape metrics are used for the generation of the mesh in the ANSYS Workbench, the Jacobian ratio is the primary metric used to determine the acceptability of the mesh. The Jacobian ratio results for the NMP2 embedded models are as follows.
- NMP2 Embedded Model 1 (SRF = 0.80) - Jacobian ratio 9.3
" NMP2 Embedded Model 2 (SRF = 0.64) - Jacobian ratio 6.6 3 of 5
ATTACHMENT 1 RESPONSES TO OPEN ITEMS FROM THE REVIEW BY THE ACRS SUBCOMMITTEE ON POWER UPRATES AND RELATED NRC STAFF QUESTIONS Open Item 5 The licensee's stress analysis procedure is using the concept of "stress reduction factor." In the procedure, the embedded model is analyzed over a reducedfrequency range which includes afrequency associatedwith the dominant stress peak at the selected high stress location. The stress reductionfactor is determined by comparing the stresses in the embedded model to the results of the corresponding analysis of the global mode. Then the stress reductionfactor is applied to the stresses obtained in the full frequency range using the originalglobal model. The licensee's slide indicated that there are two critical locations: lower lifting rod support bracket weld with SRF = 0. 64 and outer hood/hood support/cover platejunction with SRF = 0.8. Member Abdel-Khalik asked: Where is SRF 0.64 referred to? What is the stress at CLTP?
NMPNS Response The CLTP limiting alternating stress ratios (SR-a) in the global model at the two embedded model locations without the stress reduction factor (SRF) (and without the proposed physical modifications) were 2,26 for the outer hood/hood support/cover plate junction and 2.28 for the lower bracket/lifting rod/vane bank side plate junction.
The embedded model was not used to calculate the SRF without the modification. However, a simplified sub-model technique was employed to determine the benefit of a refined mesh for these two locations without the modifications. The results of the simplified sub-model showed an SRF of approximately 1.0 for both locations.
These results did not become part of the basis for the final design since the analysis supported a conclusion that a modification was required to achieve the desired margin. It follows that the SRF for these two locations is achieved by the modification and is not the result of a refined finite element analysis (FEA) mesh.
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ATTACHMENT 1 RESPONSES TO OPEN ITEMS FROM THE REVIEW BY THE ACRS SUBCOMMITTEE ON POWER UPRATES AND RELATED NRC STAFF QUESTIONS Oven Item 6 With respect to an ACRS member question on environmental qualification, the NRC staff requested confirmation of the statements below.
Inside Containment The increase in integrateddose will cause some components in containment to reach EQ dose limitsprior to the end ofplant life. These components will be replaced as requiredprior to end of qualified life in accordance with the EQ program. The remaining components will still have qualified lives beyond the end ofplant life.
Outside Containment The increase in integrateddose will cause some components outside containment to reach EQ dose limits prior to the end ofplant life. These components will be replacedas requiredprior to end of qualified life in accordancewith the EQ program. In addition, 17 components will requireshielding to be installed to reducepost accident dose to meet EQ programrequirements.
NMPNS Response NMPNS hereby confirms that the above statements are accurate.
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ATTACHMENT 2 LIST OF REGULATORY COMMITMENTS Nine Mile Point Nuclear Station, LLC November 1, 2011
ATTACHMENT 2 LIST OF REGULATORY COMMITMENTS The following table identifies the regulatory commitments in this document. Any other statements in this submittal represent intended or planned actions. They are provided for information purposes and are not considered to be regulatory commitments.
REGULATORY COMMITMENT DUE DATE In accordance with ASME Section III NB-3200, stress based fatigue This commitment will monitoring at Nine Mile Point Unit 2 (NMP2) will include all six stress apply for the NMP2 components. period of extended operation, commencing on November 1, 2026.
At each 2.5% power ascension test interval during the ascent to EPU During the ascent to EPU conditions from 100% Current Licensed Thermal Power (CLTP), the conditions from 100%
Acoustic Circuit Model (ACM) 4.1 load definition and a corresponding CLTP.
stress analysis for the top 100 stress locations (known as real time stress analysis) will be determined, and the minimum alternating stress intensity ratio (SR-a) at each of these intervals will be confirmed as follows.
Power Level Minimum SR-a Minimum SR-a
(% CLTP) 100 2.51 2.76 102.5 2.42 2.63 105 2.33 2.50 107.5 2.24 2.37 110 2.16 2.24 112.5 2.08 2.12 115 2.00 2.00 Notes
- 1. These criteria establish a variation from velocity squared scaling that could represent a significant trend. If a criterion is exceeded, a review of the results by the Plant Operations Review Committee (PORC) and NRC is required. A power reduction is not required provided that SR-a remains greater than 2.0.
- 2. These criteria establish the expected velocity squared scaling as power is increased. If a criterion is exceeded, an engineering review is required. If the review determines that the variation does not represent a significant deviation in velocity squared scaling, power may be increased to the next test interval.
A summary of the stress analysis results will be provided for NRC review at each 5% power test interval.
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I ATTACHMENT 3 AFFIDAVIT FROM CONTINUUM DYNAMICS, INC JUSTIFYING WITHHOLDING PROPRIETARY INFORMATION Nine Mile Point Nuclear Station, LLC November 1, 2011
Continuum Dynamics, Inc.
(609) 538-0444 (609) 538-0464 fax 34 Lexington Avenue Ewing, NJ 08618-2302 AFFIDAVIT Re: C.D.I. Technical Memo No.11-24P "Nine Mile Point Velocity Squared Data Analysis" Revision 2 I, Alan J. Bilanin, being duly sworn, depose and state as follows:
I1. 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.I. under privilege and in confidence.
- 2. The Information sought to be withheld, as transmitted to Constellation Energy Group as attachment to C.D.I. Letter No. 11130 dated 26 October 2011, C.D.I. Technical Memo No.11-24P "Nine Mile Point Velocity Squared Data Analysis" Revision 2.
- 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
I 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 c-*b day of LVbC5c--- 2011.
Alan J. Bilanin Continuum Dynamics, Inc.
Subscribed and sworn before me this day: c*::6 z& //
eter,-Bur otary Public EILEEN P. BURMEISTER NOTARY PUBLIC OF NEW JERSEY
,MY COMM. EXPIRES-MAY 6,2012