Letter Sequence Other |
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TAC:ME0817, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR (Approved, Closed) |
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MONTHYEARML0932701012009-11-23023 November 2009
Request for Additional Information Relocation of Pressure and Temperature Limit Curves to PTLR
Project stage: RAI
ML0935700972009-12-17017 December 2009
Submittal of Response to Request for Additional Information on License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
Project stage: Response to RAI
ML0933700022010-01-21021 January 2010
Issuance of Amendment Relocation of Pressure and Temperature Curves to the Pressure Temperature Limits Report
Project stage: Approval
ML1006301202010-03-10010 March 2010
Correction to Amendment No. 204 - License Amendment Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
Project stage: Other
2009-12-17
[Table View] |
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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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINpTON, D.C. 20555-0001 MFlrch io, 2010 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 - CORRECTION LETTER TO LICENSE AMENDMENT REGARDING RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATURE LIMITS REPORT (TAC NO. ME0817)
Dear Mr. Belcher:
On January 21,2010, the Nuclear Regulatory Commission (NRC) issued Amendment No. 204 to Renewed Facility Operating License No. DPR-63 for the Nine Mile Point Nuclear Station (NMPNS), Unit No.1 (NMP1). This amendment modified Technical Specification (TS) Section 3.2.1, "Reactor Vessel Heatup and Cooldown Rates," and Section 3.2.2, "Minimum Reactor Vessel Temperature for Pressurization," by replacing the existing reactor vessel heatup and cooldown rate limits and the pressure and temperature limit curves with references to the Pressure and Temperature Limits Report (PTLR). In addition, the amendment added a new section addressing administrative requirements for the PTLR to TS Section 6.0, "Administrative Controls."
Subsequent to the issuance of the January 21, 2010, letter, the NRC staff identified that page 3 of the operating license was not included with the issued license amendment. Enclosed please find page 3.
The NRC regrets any inconvenience that this error may have caused. If there are any questions regarding this matter, please contact me at 301-415-1030.
Sincerely, Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 Enc'osure:
As stated cc w/encl: Distribution via Listserv
-3 (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components.
(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 204, is hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications.
(3) Deleted RenO'tved License No. DPR ed Amendment No. 191, 192, 193, 194, 196, 1ge, 197, 198, 199,200,201,202,203,204 Issued by letter dated March l~ 2010
March 10,2010 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 - CORRECTION LETTER TO LICENSE AMENDMENT REGARDING RELOCATION OF PRESSURE AND TEMPERATURE LIMIT CURVES TO THE PRESSURE AND TEMPERATURE LIMITS REPORT (TAC NO. ME0817)
Dear Mr. Belcher:
On January 21, 2010, the Nuclear Regulatory Commission (NRC) issued Amendment No. 204 to Renewed Facility Operating License No. DPR-63 for the Nine Mile Point Nuclear Station (NMPNS), Unit No.1 (f\lMP1). This amendment modified Technical Specification (TS) Section 3.2.1, "Reactor Vessel Heatup and Cooldown Rates," and Section 3.2.2, "Minimum Reactor Vessel Temperature for Pressurization," by replacing the existing reactor vessel heatup and cooldown rate limits and the pressure and temperature limit curves with references to the Pressure and Temperature Limits Report (PTLR). In addition, the amendment added a new section addressing administrative requirements for the PTLR to TS Section 6.0, "Administrative Controls."
Subsequent to the issuance of the January 21, 2010, letter, the NRC staff identified that page 3 of the operating license was not included with the issued license amendment. Enclosed please find page 3.
The NRC regrets any inconvenience that this error may have caused. If there are any questions regarding this matter, please contact me at 301-415-1030.
Sincerely, IRA!
Richard V. Guzman, Senior Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosure:
As stated cc w/encl: Distribution via Listserv Distribution:
PUBLIC RidsOgcRp RidsOGCMailCenter Rids NrrDssSrxb LPL 1-1 R1F RidsNrrDorlLPL 1-1 RidsNrrLASLittle RidsRgn1 MailCenter RidsAcrsAcnw_MailCenter RidsNrrDirsltsb RidsNrrDorlDpr RidsNrrPMNineMilePoint BParks, NRR CFairbanks, NRR CSchulten, NRR RidsN rrDeCvib ADAMS Accession No'.. ML100630120 OFFICE LPL 1-1/PM LPL 1-1/LA LPL1-1/BC NAME RGuzman SUttle NSalgado DATE 3/08/10 3/08/10 3/10/10 OFFICIAL RECORD COpy
