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MONTHYEARML20217J3751999-10-15015 October 1999 Informs That Applicable Portions of NEDC-32778P, Safety Analysis Rept for River Bend 5% Power Uprate, Marked as Proprietary Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) Project stage: Other ML0232502012002-11-15015 November 2002 License Amendment Request Pursuant to 10 CFR 50.90: Revision of Reactor Pressure Vessel Pressure-Temperature Limits and Request for Exemption from Requirements of 10 CFR 50.60 Project stage: Request ML0236501962002-12-31031 December 2002 Additional Questions Re 11/15/02 Amendment Request Project stage: Other ML0302900562003-01-15015 January 2003 Transmittal of Neutron Transport Calculations Benchmarking Report Project stage: Request ML0311401882003-04-23023 April 2003 P-T Limits Amendment Project stage: Other ML0311402082003-04-24024 April 2003 NMP1 P-T Limits Curve Amendment - Issues for Discussion Project stage: Other ML0312603012003-05-0606 May 2003 Request for Additional Information - Amendment Application Pressure-Temperature Limit Curves Project stage: RAI ML0314001372003-05-16016 May 2003 Current Active Action List Project stage: Other ML0317702342003-06-18018 June 2003 Change to Commitment Date for Response to Request for Additional Information - Amendment Application Pressure-Temperature Limit Curves (TAC No.MB6687 & MB6703) Project stage: Response to RAI ML0320504542003-07-24024 July 2003 Issuance of License Amendment No. 136, Reactor Vessel Material Surveillance Program Project stage: Approval ML0322505952003-07-31031 July 2003 Response to Request for Additional Information Pressure-Temperature Limit Curves Project stage: Response to RAI ML0326810102003-09-15015 September 2003 Transmittal of Revised Neutron Transport Calculations Benchmarking Report Project stage: Request ML0327606962003-10-27027 October 2003 License Amendment, Issuance of Amendment Re. Pressure Temperature Limit Curves Project stage: Approval RBG-46368, Additional Information Regarding River Bend Station Fluence Calculations2004-12-0808 December 2004 Additional Information Regarding River Bend Station Fluence Calculations Project stage: Other 2003-04-24
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Category:Letter
MONTHYEARNMP1L3570, 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 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)) 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 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 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 IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval 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) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - 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RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - 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)2023-06-0909 June 2023 Day Commitment Response - 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) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
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P.O. Box 63 Lycoming, New York 13093 Constellation Energy Group Nine Mile Point Nuclear Station September 15, 2003 NMP1L 1773 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Nine Mile Point Units 1 and 2 Docket Nos. 50-220 and 50-410 Facility Operating License Nos. DPR-63 and NPF-69 Transmittal of Revised Neutron Transport Calculations Benchmarking Report TAC Nos. MB6687 and MC0331 Gentlemen:
The purpose of this letter is to transmit the revised Reactor Pressure Vessel (RPV) neutron transport calculations benchmarking report for NRC review as required to support qualification of the calculational methodology utilized in the neutron fluence determinations applicable to Nine Mile Point Units 1 and 2 (NMP 1 and NMP2). In a conference call held on July 30, 2003 with the NRC, the Nine Mile Point Nuclear Station, LLC, (NMPNS) staff committed to update the data previously reported in the January 15, 2003 benchmarking report submittal [Letter No. NMP1L 1708; ADAMS Accession No. ML030290056].
The attached revised benchmarking report, "Benchmarking of Nine Mile Point Unit 1 and Unit 2 Neutron Transport Calculations," has been updated to be consistent with the NMPNS responses [Letter No. NMP1L 1749, dated July 31, 2003] to an NRC Request for Additional Information (RAI), dated May 6, 2003 [ADAMS Accession No. ML031260301]. The RAI contained a list of issues to be addressed by NMPNS pertaining to the information and analytical results provided in the January 15, 2003 benchmarking report submittal. In addressing the issues raised in the RAI, NMPNS found it necessary to perform additional analyses, which included supplemental neutron transport calculations for NMP1 Operating Cycles 9, 10, and 11, and the re-analyses of Cycles 7 and 12. The revised benchmarking report updates the data, discussions, and conclusions to incorporate the results of these additional analyses. A more detailed summary of changes is included in the report.
DCof
Page 2 NMP1L 1773 By letters dated November 15, 2002 [NMPlL 1697; ADAMS Accession No. ML023250201] and August 15, 2003 [NMP2L 2096], NMPNS transmitted applications for amendments to the NMIP1 and NMP2 Technical Specifications (TSs) that would revise the Reactor Coolant System (RCS) Pressure-Temperature (P-T) limit curves. The proposed P-T limit curves were developed using the MPM Technologies, Inc.
methodology to determine the RPV neutron fluence values. Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," dated March 2001, requires the benchmarking of the methodology used for fluence determinations. The MPM methodology satisfies the requirements of Regulatory Guide 1.190. The Regulatory Position 1.4 uncertainty analyses and comparisons with benchmark measurements and calculational benchmark problems (as provided in NUTREG/CR-6115) have been completed and the Position 1.4 methodology qualification and uncertainty estimates have been satisfied. The benchmark analyses (Report No.
MPM-40278 1)were submitted to the NRC for review [Letter NWPiL 1708] as required to support plant-specific (applicable to NMP1 and NMP2) qualification of the MPM methodology. Supplemental information was provided [Letter NMPL 1749] in response to the May 6, 2003 RAI regarding the benchmark analyses. As reported in the RAI response, successful calculation of the pool critical assembly (PCA) benchmark has been achieved and comparisons of the calculated and measured reaction rates for the NMP1 dosimetry sets indicate agreement well within the +/-20% requirement for fluence calculational uncertainty. Moreover, the calculations do not exhibit any significant bias.
Therefore, the supplemental information provided in the RAI response confirmed that the MPM methodology used for the calculation of the NMP1 and NMP2 fluence values fully satisfies the Regulatory Guide 1.190 requirement for fluence methodology qualification by measurement and calculational benchmarks.
Contained herein as Attachment 1 (Report No. MPM402781, Revision 1) is a revision to the benchmarking report that was originally submitted on January 15, 2003. The attached report has been updated to be consistent with the supplemental information provided in the July 31, 2003 RAI response. In addition, the revised benchmarking report also updates the results of the NMP1 Cycle 12 core shroud boat sample analyses to reflect the new neutron transport results as reported in the RAI response. The updated results of the Cycle 12 boat sample analyses are not included in the RAI response information. Note that the MPM methodology, as analyzed for methods qualification in the attached revised benchmarking report, applies to both NMP1 and NMP2 for use in RPV and reactor component (e.g., core shroud, surveillance capsule) fluence determinations.
Pursuant to the Regulatory Guide 1.190 requirement for fluence methodology qualification, Revision 1 to the RPV neutron transport calculations benchmarking report is hereby submitted for NRC review to support evaluation and approval of the currently
Page 3 NMP1L 1773 pending TS amendment applications for revision of the NUT1 and NMP2 RCS P-T limit curves. The NMP2 P-T curve amendment is needed by February 15, 2004 to support the Spring 2004 refueling outage (RFO9), which is scheduled to commence in March 2004.
Sincerely, William C. Holston Manager Engineering Services WCHICDM/bjh : Report No. MPM-40278 1,Revision 1 cc: Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Mr. P. S. Tam, Senior Project Manager, NRR (2 copies)
ATTACHMENT 1 REPORT NO. MPM-402781, Revision 1 BENCHMARKING OF NINE MILE POINT UNIT 1 AND UNIT 2 NEUTRON TRANSPORT CALCULATIONS