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MONTHYEARML0926406812009-09-18018 September 2009 License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications - Tech. Spec. Sections 3.2.7.1 and 4.2.7.1 Project stage: Request ML0927408002009-10-0606 October 2009 Individual Notice of Consideration of Issuance of Amendment Removal of Pressure Isolation Valve Requirements Consistent with Improved Technical Specification Project stage: Other ML0927407982009-10-0606 October 2009 FRN: General Notice. Nine Mile Point Nuclear Station, Unit No. 1 - Removal of Pressure Isolation Valve Requirements Consistent with Improved TS Project stage: Other NRC-2009-0451, FRN: General Notice. Nine Mile Point Nuclear Station, Unit No. 1 - Removal of Pressure Isolation Valve Requirements Consistent with Improved TS2009-10-0606 October 2009 FRN: General Notice. Nine Mile Point Nuclear Station, Unit No. 1 - Removal of Pressure Isolation Valve Requirements Consistent with Improved TS Project stage: Other ML0929407172009-10-15015 October 2009 License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications - Revised Requested Approval Date Project stage: Request ML1006301242010-03-18018 March 2010 Request for Additional Information, Primary Coolant System Pressure Isolation Valves (PIV) Standard Technical Specifications (STS) Project stage: RAI ML1011101792010-04-14014 April 2010 Response to Request for Additional Information on License Amendment Request Pursuant to 10 CFR 50.90: Revisions to Primary Coolant System Pressure Isolation Valve Requirements Consistent with Standard Technical Specifications Project stage: Response to RAI ML1018803332010-07-26026 July 2010 Issuance of Amendment No. 206 Modification of TS Section 3.2.7.1 and 4.2.7.1 Project stage: Approval 2009-09-18
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Category:Federal Register Notice
MONTHYEARML21294A3762021-11-16016 November 2021 Federal Register Notice for Order Approving Indirect Transfer of Licenses ML21145A0142021-05-26026 May 2021 Fleet and the Associated Independent Spent Fuel Storage Installations - Extension of Comment Period for Notice of Consideration of Approval of Transfer of Licenses and Conforming Amendments and Opportunity to Request a Hearing EPID L-2021-L ML21145A0152021-05-26026 May 2021 FRN Exelon License Transfer - Extend Comment Period ML21102A0752021-04-28028 April 2021 Fleet - Notice of Consideration of Approval of Transfer of Licenses and Conforming Amendments and Opportunity for a Hearing (FRN) ML21061A0672021-04-13013 April 2021 FRN, Exemption from the Requirements of 10 CFR 2.109(b) Related to Submission of Subsequent License Renewal Application ML21060A5962021-03-0909 March 2021 FRN - Notice of Issuance of Multiple COVID-19 Exemptions Regarding 10 CFR Part 26 for February 2021 ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20243A0002020-09-23023 September 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for August 2020 ML20156A4002020-06-30030 June 2020 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, Opportunity for Hearing ML20035C4082020-02-18018 February 2020 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 02/25/2020 ML19337A0312019-12-11011 December 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 12/17/2019 ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 ML18351A0022019-01-0202 January 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/2019 NRC-2018-0287, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/20192019-01-0202 January 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 01/02/2019 ML18304A3042018-11-23023 November 2018 Federal Register Notice: Environmental Assessment and Finding of No Significant Impact Regarding Exelon Generation Company, LLC License Amendment Request to Change Emergency Plan Staffing NRC-2018-0262, Federal Register Notice: Environmental Assessment and Finding of No Significant Impact Regarding Exelon Generation Company, LLC License Amendment Request to Change Emergency Plan Staffing2018-11-23023 November 2018 Federal Register Notice: Environmental Assessment and Finding of No Significant Impact Regarding Exelon Generation Company, LLC License Amendment Request to Change Emergency Plan Staffing ML18002A3812018-01-24024 January 2018 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: February 6, NRC-2018-0011, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: Februar2018-01-24024 January 2018 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: February 6, ML17143A1182017-05-24024 May 2017 FRN Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration, and Opportunity for Hearing (CAC Nos. MF9720-21) ML16271A0922016-09-28028 September 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: October 11, 2016 NRC-2016-0202, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 20162016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML16257A5172016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML16004A1182016-01-0707 January 2016 FRN, Issuance of Confirmatory Orders, Authorize Use of Preemption Authority Granted Under Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended ML15356A5992015-12-29029 December 2015 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 5, 2016 ML15320A2842015-12-0808 December 2015 Final Environmental Assessment and Finding of No Significant Impact Related to Preemption Authority Requests ML15328A5502015-11-27027 November 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: December 8, 2015 NRC-2015-0269, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: December 8, 20152015-11-27027 November 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: December 8, 2015 ML15279A3362015-10-23023 October 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: November 3, NRC-2015-0240, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: Novemb2015-10-23023 October 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: November 3, ML15218A6252015-08-14014 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 14, 2015 ML15148A3762015-06-0101 June 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015 ML15120A2272015-05-0101 May 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 12, 2015 NRC-2015-0009, G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units2015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14335A6302015-01-15015 January 2015 G20110262 - Final Response to Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14335A6482015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14303A3812014-10-31031 October 2014 Biweekly Sholly FRN - Application and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: November 12, 2014 NRC-2014-0228, Federal Register Notice License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene; Order for Exelon Generation Company, LLC, Nine Mile Point Nuclear Station, Units 1 and 22014-10-21021 October 2014 Federal Register Notice License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene; Order for Exelon Generation Company, LLC, Nine Mile Point Nuclear Station, Units 1 and 2 ML14282A6282014-10-21021 October 2014 Federal Register Notice License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene; Order for Exelon Generation Company, LLC, Nine Mile Point Nuclear Station, Units 1 and 2 ML14189A6652014-07-24024 July 2014 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information - August 5, 2014 ML14126A4382014-05-20020 May 2014 Facility Operating and Combined Licenses: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Acces ML14063A1842014-03-25025 March 2014 Order Approving Direct Transfer of Renewed Operating Licenses and Conforming License Amendments ML13294A0702013-12-18018 December 2013 Consideration of Approval of Transfer of Renewed Facility Operating Licenses, Materials Licenses, and Conforming Amendments Containing SUNSI ML13294A0392013-11-0707 November 2013 Notice of Consideration of Approval of Transfer of Renewed Facility Operating Licenses and Conforming Amendments,.. ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 ML13121A4592013-06-0505 June 2013 Order Designating an Interim Class of NRC Licensed Facilities That Are Eligible to Apply to the Commission for Authorization to Use the Authority Granted Under the Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended NRC-2013-0127, Order Designating an Interim Class of NRC Licensed Facilities That Are Eligible to Apply to the Commission for Authorization to Use the Authority Granted Under the Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended2013-06-0505 June 2013 Order Designating an Interim Class of NRC Licensed Facilities That Are Eligible to Apply to the Commission for Authorization to Use the Authority Granted Under the Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments 2021-05-26
[Table view] 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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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 6, 2009 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.1 (NMP1) -INDIVIDUAL NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR HEARING (TAC NO. ME2253)
Dear Mr. Belcher:
The U.S. Nuclear Regulatory Commission has forwarded the enclosed "Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing," to the Office of the Federal Register for publication.
This notice relates to your application dated September 18, 2009, in which you requested to modify Technical Specification (TS) Sections 3.2.7.1 and 4.2.7.1, "Primary Coolant System Pressure Isolation Valves," to incorporate requirements that are consistent with Section 3.4.5 of the Improved Standard TSs, NUREG-1433, Revision 3.
If you have any questions, please contact me at 301-415-1030.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
Notice of Consideration cc w/encl: Distribution via Listserv
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION NINE MILE POINT NUCLEAR STATION, UNIT NO.1 DOCKET NO. 50-220 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-63 issued to Nine Mile Point Nuclear Station, LLC (the licensee) for operation of Nine Mile Point, Unit NO.1 (NMP1) located in Oswego, NY.
The proposed amendment would modify Technical Specification (TS) Sections 3.2.7.1 and 4.2.7.1, "Primary Coolant System Pressure Isolation Valves," to incorporate requirements that are consistent with Section 3.4.5 of the Improved Standard TSs, NUREG-1433, Revision 3.
The proposed TS changes include the addition of applicable reactor operating conditions, addition of actions to be taken when pressure isolation valve (PIV) leakage is not within limit, relocation of the PIV leakage limit criterion from TS Table 3.2.7.1 to Specification 4.2.7.1.a, replacement of the existing PIV leakage test frequencies with a reference to the Inservice Testing Program, and deletion of TS Table 3.2.7.1, "Primary Coolant System Pressure Isolation Valves." The list of PIVs would be relocated from TS Table 3.2.7.1 to the NMP1 Updated Final Safety Analysis Report, consistent with the guidance in Generic Letter (GL) 91-08, "Removal of Component Lists from Technical Specifications."
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations.
-2 The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91 (a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment involves changes to the TS requirements that apply to reactor coolant system (RCS) PIVs. No physical plant changes are involved.
PIVs isolate the boundary between the high pressure RCS and connected low pressure piping systems. The TS requirements are intended to detect PIV degradation that has the potential to cause a loss of coolant accident (LOCA) outside of containment due to the failure of low pressure portions of systems connected to the RCS.
The proposed changes to the TS requirements are consistent with NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWR/4," and will continue to ensure that excessive leakage through these valves is properly identified and resolved. Testing in accordance with the 1ST [Inservice Testing]
Program will continue to detect PIV leakage in excess of the established limits, which are not being changed. When these limits are exceeded, required actions will initiate appropriate activities to minimize the impact of the leakage. These actions will not adversely impact nuclear safety because the flow paths will be sufficiently isolated, the period of time without redundant isolation capability will be appropriately limited, and the probability of a second valve failing during this time period is low. Thus, the proposed amendment does not result in operation that would make an accident more likely to occur, and does not alter assumptions relative to mitigation of a previously evaluated accident.
Relocation of the list of PIVs from the TS to a licensee-controlled document (the UFSAR) in accordance with the guidance in GL 91-08 is an administrative change that does not alter the TS requirements that are applicable to the PIVs.
- 3 Based on the above discussion, it is concluded that the proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed amendment involves changes to the TS requirements that apply to RCS PIVs. These changes to the TS requirements are consistent with NUREG 1433. The proposed changes do not involve a physical alteration of the plant (no new or different type of equipment will be installed) or changes in the methods governing normal plant operation. The changes also do not alter the design function of the PIVs and do not adversely affect the ability of the PIVs to perform their design function.
Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed amendment involves changes to the TS requirements that apply to RCS PIVs. No physical plant changes are involved. PIVs isolate the boundary between the high pressure RCS and connected low pressure piping systems.
The revised TS PIV requirements will continue to ensure that excessive leakage through these valves is properly identified and resolved, such that a LOCA outside of containment due to the failure of low pressure portions of systems connected to the RCS will be no more likely to occur. Thus, the proposed amendment will not result in a design basis or safety limit being exceeded or altered.
Based on the above discussion, it is concluded that the proposed amendment does not involve a significant reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination.
-4 Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60-day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rulemaking and Directives Branch (RDB), TWB-05-B01 M, Division of Administrative Services, Office of Administration, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be faxed to the RDB at 301-492-3446. Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
Within 60 days after the date of publication of this notice, any person(s) whose interest may be affected by this action may file a request for a hearing and a petition to intervene with respect to issuance of the amendment to the subject facility operating license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's "Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the Commission's PDR, located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor),
-5 Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management System's (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements:
- 1) the name, address and telephone number of the requestor or petitioner; 2) the nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding; 3) the nature and extent of the requestor's/petitioner's property, financial, or other interest in the proceeding; and 4) the possible effect of any decision or order which may be entered in the proceeding on the requestor's/petitioner's interest. The petition must also identify the specific contentions which the petitioner/requestor seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner/requestor shall provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner/requestor must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show
-6 that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner/requestor who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing.
If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a request for hearing, a petition for leave to intervene, any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule, which the NRC promulgated in August 2007 (72 FR 49139, August 28, 2007).
The E-Filing process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Participants may not submit paper copies of their filings unless they seek an exemption in accordance with the procedures described below.
-7 To comply with the procedural requirements of E-Filing, at least ten (10) days prior to the filing deadline, the petitioner/requestor should must contact the Office of the Secretary bye-mail at hearing.docket@nrc.gov, or by calling (301) 415-1677, to request (1) a digitallD certificate, which allows the participant (or its counselor representative) to digitally sign documents and access the E-Submittal server for any proceeding in which it is participating; and/or (2) creation of an electronic docket for the proceeding (even in instances in which the petitioner/requestor (or its counselor representative) already holds an NRC-issued digital ID certificate). Each petitioner/ requestor will need to download the Workplace Forms Viewer" to access the Electronic Information Exchange (EIE), a component of the E-Filing system. The Workplace Forms Viewer" is free and is available at http://www.nrc.gov/site-help/e-submittals/install viewer.html. Information about applying for a digital ID certificate is available on NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html.
Once a petitioner/requestor has obtained a digitallD certificate, had a docket created, and downloaded the EIE viewer, it can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with NRC guidance available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html.
A filing is considered complete at the time the filer submits its documents through EIE. To be timely, an electronic filing must be submitted to the EIE system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an e-mail notice confirming receipt of the document. The EIE system also distributes an e-mail notice that provides access to the document to the NRC Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their counselor representative) must apply for and receive a digital ID certificate before a hearing
-8 request/petition to intervene is filed so that they can obtain access to the document via the E Filing system.
A person filing electronically using the agency's adjudicatory e-filing system may seek assistance through the "Contact Us" link located on the NRC Web site at http://www.nrc.gov/site help/e-submittals.html or by calling the NRC electronic filing Help Desk, which is available between 8:00 a.m. and 8:00 p.m., Eastern Time, Monday through Friday, excluding government holidays. The toll-free help line number is 1-866-672-7640. A person filing electronically may also seek assistance by sending an e-mail to the NRC electronic filing Help Desk at MSHD.Resource@nrc.gov.
Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format.
Such filings must be submitted by: (1) first class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants.
Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service.
Non-timely requests and/or petitions and contentions will not be entertained absent a determination by the Commission, the presiding officer, or the Atomic Safety and Licensing Board that the request and/or petition should be granted and/or the contentions should be admitted, based on a balancing of the factors specified in 10 CFR § 2.309(c)(1)(i)-(viii).
-9 Documents submitted in adjudicatory proceedings will appear in NRC's electronic hearing docket which is available to the public at http://ehd.nrc.gov/ehd proceeding/home. asp, unless excluded pursuant to an order of the Commission, an Atomic Safety and Licensing Board, or a Presiding Officer. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or home phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submissions.
For further details with respect to this license amendment application, see the application for amendment dated September 18, 2009 (Agencywide Documents Access and Manqgement System (ADAMS) Accession No. IVIL092640681), which is available for public inspection at the Commission's PDR, located at One White Flint North, File Public Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the ADAMS Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or bye-mail to pdr.resource@nrc.gov.
- 10 Attorney for licensee: Mark J. Wetterhahn, Esquire, Winston & Strawn, 1700 K Street, NW., Washington, DC 20006.
Dated at Rockville, Maryland, this 6th day of October 2009.
FOR THE NUCLEAR REGULATORY COMMISSION 42te~r-----
Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
October 6, 2009 Mr. Samuel L. Belcher Vice President Nine Mile Point Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT NO.1 (NMP1) -INDIVIDUAL NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR HEARING (TAC NO. ME2253)
Dear Mr. Belcher:
The U.S. Nuclear Regulatory Commission has forwarded the enclosed "Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing," to the Office of the Federal Register for publication.
This notice relates to your application dated September 18, 2009, in which you requested to modify Technical Specification (TS) Sections 3.2.7.1 and 4.2.7.1, "Primary Coolant System Pressure Isolation Valves," to incorporate requirements that are consistent with Section 3.4.5 of the Improved Standard TSs, NUREG-1433, Revision 3.
If you have any questions, please contact me at 301-415-1030.
Sincerely, IRA!
Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
Notice of Consideration cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL1-1r/f RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-1 Resource RidsNrrLASLittle Resource RidsOgcRp Resource RidsRgn1 MailCenter Resource RidsNrrPMNineMilePoint Resource Accession Number: ML092740800 FRN (ADM-012)
OFFICE LPL1-1/PM LPL1-1/LA LPL1-1/BC NAME RGuzman SLittie NSalQado DATE 10/05/.09 10/05/09 10/06/09 OFFICIAL RECORD COPY