Letter Sequence Draft Approval |
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MONTHYEARML14064A3232013-12-31031 December 2013
000N0123-FBIR-NP, Rev. 0, Fuel Bundle Information Report for Nine Mile Point 2 Reload 14 Cycle 15.
Project stage: Request
ML14002A1702014-01-0202 January 2014
Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - MF3056, License Amendment Request - Maximum Extended Load Line Limit Analysis Plus
Project stage: Other
ML14002A2202014-01-0202 January 2014
Revised Unacceptable Application with Opportunity to Supplement - Nine Mile Point Nuclear Station, Unit 2 - License Amendment Request - Maximum Extended Load Line Limit Analysis Plus
Project stage: Other
ML14023A6542014-01-21021 January 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Commitment Date to Provide Supplemental Information
Project stage: Supplement
ML14028A3982014-01-28028 January 2014
MF3056 - Acceptance of Requested Licensing Action License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Acceptance Review
ML14064A3222014-01-31031 January 2014
00N0123-SRLR, Rev. 2, Supplemental Reload Licensing Report for Nine Mile Point 2 (NMP2) Reload 14 Cycle 15 Extended Power Uprate (Epu)/Maximum Extended Load Line Limit Plus (Mellla+).
Project stage: Request
ML14051A1382014-02-14014 February 2014
Response to Request for Supplemental Information to License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus
Project stage: Supplement
ML14043A0062014-02-20020 February 2014
First Round of Requests for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mella+)
Project stage: RAI
ML14064A3212014-02-25025 February 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Core Reload and Safety Limit Supplemental Information
Project stage: Supplement
ML14064A3242014-02-28028 February 2014
000N2495-R1-NP, Rev. 0, Nine Mile Point Nuclear Station Unit 2 Comparison of Mellla+ Reference Design to Cycle 15 Design Characteristics.
Project stage: Request
ML14029A0392014-03-0505 March 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated November 1, 2013
Project stage: Withholding Request Acceptance
ML14051A0152014-03-0606 March 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 14, 2014
Project stage: Withholding Request Acceptance
ML14071A4662014-03-10010 March 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to Srxb RAI 1 and RAI 2
Project stage: Request
ML14071A2422014-03-12012 March 2014
NMP Unit 2, MF3056, 2nd Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Draft RAI
ML14083A0232014-03-31031 March 2014
Second Round of Request for Additional Information Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: RAI
ML14139A4162014-05-14014 May 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Response to RAI STSB-1 and RAI STSB-2
Project stage: Response to RAI
ML14204A3692014-08-14014 August 2014
Third Round of Request for Additional Information & Enclosure 1, Regarding License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus (Mellla+) (Tac No. MF3056)
Project stage: RAI
ML14072A0152014-09-0303 September 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated March 10, 2014
Project stage: Withholding Request Acceptance
ML14246A3962014-09-0303 September 2014
NMP Unit 2, MF3056, 4th Round of Draft RAIs - LAR License Amendment Request- Maximum Extended Load Line Limit Analysis Plus (Mellla+)
Project stage: Draft RAI
ML14065A0902014-09-0303 September 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated February 25, 2014 (Tac No. MF3056)
Project stage: Withholding Request Acceptance
NMP2L2556, Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus2014-09-15015 September 2014
Response to Request for Additional Information, License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
Project stage: Response to RAI
ML14260A1202014-11-0606 November 2014
Request for Withholding Information from Public Disclosure License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus, Dated September 15, 2014 (Tac No. MF3056)
Project stage: Withholding Request Acceptance
ML14314A2142014-11-10010 November 2014
MF3056, E-mail Capture - LAR Mellla+, Simulator Audit Plan, November 20-21, 2014 at the Plant Site
Project stage: Other
ML14321A0642014-11-17017 November 2014
Point Unit 2, MF3056, LAR Mellla+, Supplement to the Simulator Audit Plan
Project stage: Other
ML14351A4282014-12-11011 December 2014
Updated TIP Comparisons for Current Operating Conditions, GE-PPO- 1GYEF-KG1-742, Enclosure 2
Project stage: Request
ML15002A1622015-01-26026 January 2015
Request for Withholding Information from Public Disclosure Submission Dated December 11, 2014, for Supplement Information for NRC Simulator Audit LAR for Mellla+
Project stage: Withholding Request Acceptance
ML15033A0022015-01-30030 January 2015
MF3056, LAR - Mellla+, Revised RAI - Neutron Fluence Calculation Related
Project stage: RAI
ML15051A4642015-02-18018 February 2015
Response to Fifth Request for Additional Information Concerning License Amendment Request for Maximum Extended Load Line Limit Analysis Plus
Project stage: Request
ML15056A3792015-03-16016 March 2015
Request for Withholding Information from Public Disclosure Submission Dated February 18, 2015, for License Amendment Request Pursuant to 10 CFR 50.90 Maximum Extended Load Line Limit Analysis Plus
Project stage: Withholding Request Acceptance
ML15105A4432015-05-0404 May 2015
Draft Safety Evaluation for License Amendment Request - Mellla+
Project stage: Draft Approval
ML15114A1602015-05-0707 May 2015
Issuance of Simulator Audit Report License Amendment Request Regarding MELLLA Plus
Project stage: Approval
ML15096A0762015-09-0202 September 2015
Issuance of Amendment Maximum Extended Load Line Limit Analysis Plus
Project stage: Approval
ML15210A3262015-09-0404 September 2015
LTR-15-0388-1 - John W. Stetkar Letter Nine Mile Point Nuclear Station Unit 2 Maximum Extended Load Line Limit Analysis Plus (Mellla+) License Amendment Request
Project stage: Other
2014-03-12
[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
OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 4, 2015 Mr. Peter Orphanos Site Vice President Nine Mile Point Nuclear Station, LLC 348 Lake Road Oswego, NY 13126
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 2 - DRAFT SAFETY EVALUATION FOR LICENSE AMENDMENT REQUEST- RE: MAXIMUM EXTENDED LOAD LINE LIMIT PLUS (MELLLA+) (TAC NO. MF3056)
Dear Mr. Orphanos:
By letter dated November 1, 2013, as supplemented by letters dated January 21, February 14, February 25, March 10, May 14, June 13, December 11, 2014, and February 18, 2015, Nine Mile point Nuclear Station (NMPNS, the licensee) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC) requesting changes to the Nine Mile Point Nuclear Station Unit No. 2 (NMP2), Technical Specifications (TSs).
The proposed amendment includes changes to the NMP2 TS necessary to: (1) implement the Maximum Extended Load Line Limit Analysis Plus expanded operating domain; (2) change the stability solution to Detect and Suppress Solution - Confirmation Density; (3) use the TRACG04 analysis code; and (4) increase the Safety Limit Minimum Critical Power Ratio for two recirculation loops in operation.
Enclosed for your review and comment is a copy of the NRC staff's draft safety evaluation (SE) for the LAR. Pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations (10 CFR),
we have indicated the proprietary information in the SE by double square brackets, i.e., (( )),
based on such information in your submittals.
The purpose of this letter is to provide you with the opportunity to comment on the proprietary aspects. If you believe that any information in the enclosure is not correctly marked with respect to the proprietary nature, or, should have been marked as proprietary information, please identify such information line-by-line, including the source reference and define the basis pursuant to the criteria of 10 CFR 2.390. Also, please provide your comments on any factual errors or clarity concerns contained in the enclosed draft proprietary SE. The final non-proprietary and proprietary SEs will be issued after making any necessary changes. The final non-proprietary SE will be made publicly available.
Enclosure transmitted herewith contains Official Use Only - Proprietary Information.
When separated from Enclosure, this document is decontrolled.
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION P. M. Orphanos To facilitate the NRC staff's review of your comments, please provide a marked-up copy of the draft proprietary SE showing proposed changes & comments, along with a summary table of the proposed changes.
If you have any questions, please contact me at 301-415-3308.
Sincerely,
°'~
~<- "'~
Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410 Enclosure(s):
As stated cc w/encls:
OFFICIAL USE ONLY PROPRIETARY INFORMATION
OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENCLOSURE NINE MILE POINT UNIT 2 DOCKET NO. 50-410 LICENSE AMENDMENT REQUEST RE: MELLLA+
TRANSMITTAL OF AMENDMENT DRAFT SAFETY EVALUATION TO LICENSEE This document contains proprietary information pursuant to Title 1O of the Code of Federal Regulations Section 2.390.
Proprietary information is identified by text enclosed within double brackets (( )).
ADAMS Accession No. ML15118A004 OFFICIAL USE ONLY PROPRIETARY INFORMATION
Package: ML15118A688, Cover Ietter: ML15105A443 Proprie . t ary Dra ftSE ML15118A004 OFFICE DORL/LPL 1-1 \PM DORL/LPL 1-1\LA DORL/LPL 1-1 /BC (A) DORL/LPL 1-1 /PM NAME BVaidya KGoldstein MDudek BVaidva DATE 4/29/2015 4/28/2015 5/01/2015 5/04/2015
