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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 - 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 .
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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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.
P.O. Box 63 CENG.
a joint venture of Lycoming, New York 13093 315.349.5200 315.349.1321 Fax 0Constellation Energy, eD NINE MILE POINT NUCLEAR STATION March 11, 2013 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 Submittal of Evaluation to Establish Inspection Intervals for Jet Pump Holddown Beams Fabricated from Modified Alloy 718 Material
REFERENCES:
(a) Letter from F. R. Payne (NMPNS) to NRC (Document Control Desk), dated December 30, 2011, License Amendment Request Pursuant to 10 CFR 50.90:
Use of Modified Alloy 718 Material in Jet Pump Holddown Beams (b) Letter from K. Langdon (NMPNS) to NRC (Document Control Desk), dated March 20, 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 (c) Letter from R. V. Guzman (NRC) to K. Langdon (NMPNS), dated April 13, 2012, Nine Mile Point Nuclear Station, Unit No. 2 - Issuance of Amendment Regarding a Change to the Updated Safety Analysis Report Allowing the Use of Modified Alloy 718 Material in Jet Pump Holddown Beams (TAC No. ME7800)
By letter dated December 30, 2011 (Reference a), as supplemented by letter dated March 20, 2012 (Reference b), Nine Mile Point Nuclear Station, LLC (NMPNS) submitted a request to use Modified Alloy 718 material for fabrication of the Nine Mile Point Unit 2 (NMP2) reactor recirculation system jet pump holddown beams. The NRC approved the request in a letter dated April 13, 2012 issuing NMP2 License Amendment No. 141 (Reference c). The new jet pump holddown beams were installed during the spring 2012 NMP2 refueling outage.
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 March 11, 2013 Page 2 In Reference (a), NMPNS included the following regulatory commitment regarding the establishment of inspection intervals for the Modified Alloy 718 jet pump holddown beams:
In accordance with BWRVIP guidelines, NMPNS will submit to the NRC an evaluation to support establishment of inspection intervals for the new holddown beams in accordance with criteria contained in the latest revision of BWRVIP-41, "BWR Vessel and Internals Project, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines." This NMPNS evaluation will be submitted approximately one year prior to the next scheduled NMP2 refueling outage following installation of the Modified Alloy 718 jet pump holddown beams.
In accordance with the above commitment, the evaluation to support establishment of an inspection interval for the new jet pump holddown beams is documented in the Westinghouse Engineering Report that is provided in Attachment 2 (non-proprietary) and Attachment 4 (proprietary). Based on the results of the evaluation, NMPNS will perform the initial baseline inspection of the Modified Alloy 718 jet pump holddown beams within 24 years after installation and then perform re-inspections every 16 years thereafter. This inspection frequency has been established by following the technical approach used in BWRVIP-138, Revision 1, "Updated Jet Pump Beam Inspection and Flaw Evaluation Guidelines," and considering the stress corrosion cracking (SCC) susceptibility of Modified Alloy 718 material when compared to that of Alloy X-750. The comparison of Modified Alloy 718 with Alloy X-750 addresses a variety of factors, including fabrication process, material composition, mechanical properties, stress relaxation, and fatigue initiation. The comparison shows that in all cases, Modified Alloy 718 is as good as or better than Alloy X-750 under BWR operating conditions. In two other important areas, SCC initiation and SCC crack growth, modified Alloy 718 is significantly better than X-750.
The information contained in Attachment 4 is considered by Westinghouse Electric Company LLC (Westinghouse) to contain proprietary information exempt from disclosure pursuant to 10 CFR 2.390.
Therefore, on behalf of Westinghouse, NMPNS hereby makes application to withhold Attachment 4 from public disclosure in accordance with 10 CFR 2.390(b)(1). The affidavit from Westinghouse detailing the reasons for the request to withhold the proprietary information is provided in Attachment 3. A non-proprietary version of the same document is provided in Attachment 2. The regulatory commitments contained in this letter are listed in Attachment 1.
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, Paul M. Swift Manager Engineering Services PMS/DEV
Document Control Desk March 11, 2013 Page 3 Attachments:
- 1. List of Regulatory Commitments
- 2. Westinghouse Engineering Report XGEN-2012-25-NP, Revision 1, Technical Basis for the Inspection Frequency of the Modified Alloy 718 Jet Pump Beam (Non-Proprietary)
- 3. Affidavit from Westinghouse Electric Company LLC Justifying Withholding Proprietary Information
- 4. Westinghouse Engineering Report XGEN-2012-25-P, Revision 1, Technical Basis for the Inspection Frequency of the Modified Alloy 718 Jet Pump Beam (Proprietary) cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC
ATTACHMENT 1 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 Nine Mile Point Nuclear Station, LLC (NMPNS) will perform Initial Baseline Inspection by May the initial baseline inspection of the Nine Mile Point Unit 2 1, 2036.
(NMP2) Modified Alloy 718 jet pump holddown beams within 24 years after installation and then perform re-inspections every Re-inspection every 16 years after 16 years thereafter. May 1, 2036 (provided the unit is still operating).
Nine Mile Point Nuclear Station, LLC March 11, 2013
