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| | number = ML15105A443 | | | number = ML15105A443 |
| | issue date = 05/04/2015 | | | issue date = 05/04/2015 |
| | title = Nine Mile Point Nuclear Station, Unit No. 2 - Draft Safety Evaluation for License Amendment Request - Mellla+ (TAC No. MF3056) | | | title = Draft Safety Evaluation for License Amendment Request - Mellla+ |
| | author name = Vaidya B K | | | author name = Vaidya B |
| | author affiliation = NRC/NRR/DORL/LPLI-1 | | | author affiliation = NRC/NRR/DORL/LPLI-1 |
| | addressee name = Orphanos P M | | | addressee name = Orphanos P |
| | addressee affiliation = Exelon Generation Co, LLC | | | addressee affiliation = Exelon Generation Co, LLC |
| | docket = 05000410 | | | docket = 05000410 |
| | license number = NPF-069 | | | license number = NPF-069 |
| | contact person = Vaidya B K, NRR/DORL/LPL1-1, 415-3308 | | | contact person = Vaidya B, NRR/DORL/LPL1-1, 415-3308 |
| | case reference number = TAC MF3056 | | | case reference number = TAC MF3056 |
| | document type = Letter | | | document type = Letter |
| | page count = 4 | | | page count = 4 |
| | project = TAC:MF3056 | | | project = TAC:MF3056 |
| | stage = Draft Other | | | stage = Draft Approval |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:OFFICIAL USE ONLY PROPRIETARY INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Peter Orphanos Site Vice President Nine Mile Point Nuclear Station, LLC 348 Lake Road Oswego, NY 13126 May 4, 2015 | | {{#Wiki_filter: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 |
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| ==SUBJECT:== | | ==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) |
| 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) | |
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| ==Dear Mr. Orphanos:== | | ==Dear Mr. Orphanos:== |
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| 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 | | 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). |
| -Confirmation Density; (3) use the TRACG04 analysis code; and (4) increase the Safety Limit Minimum Critical Power Ratio for two recirculation loops in operation. | | 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. | | 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), |
| The purpose of this letter is to provide you with the opportunity to comment on the proprietary aspects. | | we have indicated the proprietary information in the SE by double square brackets, i.e., (( )), |
| 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 proprietary and proprietary SEs will be issued after making any necessary changes. | | based on such information in your submittals. |
| The final non-proprietary SE will be made publicly available. | | 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. | | Enclosure transmitted herewith contains Official Use Only - Proprietary Information. |
| When separated from Enclosure, this document is decontrolled. | | 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. | | 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. | | If you have any questions, please contact me at 301-415-3308. |
| Docket No. 50-410 Enclosure(s): | | 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: | | As stated cc w/encls: |
| Sincerely, -Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 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 1 O of the Code of Federal Regulations Section 2.390. Proprietary information is identified by text enclosed within double brackets
| | OFFICIAL USE ONLY PROPRIETARY INFORMATION |
| [[ ]]. ADAMS Accession No. ML 15118A004 OFFICIAL USE ONLY PROPRIETARY INFORMATION OFFICIAL USE ONLY PROPRIETARY INFORMATION P. 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.
| | 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+ |
| Docket No. 50-410 Enclosure(s):
| | 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. |
| As stated Sincerely, IRA/ Bhalchandra Vaidya, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation DISTRIBUTION:
| | Proprietary information is identified by text enclosed within double brackets (( )). |
| w/o proprietary enclosure via Listserv PUBLIC [cover letter only] LPLl-1 R/F RidsNrrDorlLPL 1-1 RidsNrrLAKGoldstein RidsNrrPMNineMilePoint ADAMS Accession Nos.: Package:
| | ADAMS Accession No. ML15118A004 OFFICIAL USE ONLY PROPRIETARY INFORMATION |
| ML 15118A688, C I ML 15105A443 P over etter: ' OFFICE DORL/LPL 1-1 \PM NAME BVaidya DATE 4/29/2015 RidsRgn1 MailCenter RidsAcrsAcnw_MailCTR DSchroder, Region 1 . t D ftSE ML15118A004 roprie ary ra DORL/LPL 1-1\LA DORL/LPL 1-1 /BC (A) KGoldstein MDudek 4/28/2015 5/01/2015 OFFICIAL RECORD COPY DORL/LPL 1-1 /PM BVaidva 5/04/2015 OFFICIAL USE ONLY PROPRIETARY INFORMATION}}
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| | 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}} |
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
MONTHYEARML24268A3382024-10-16016 October 2024
Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3
RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024
Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)
IR 05000220/20243022024-10-0303 October 2024
Initial Operator Licensing Examination Report 05000220/2024302
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
ML24190A0012024-09-26026 September 2024
Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation
NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024
Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000220/20240052024-08-29029 August 2024
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005)
IR 05000220/20240102024-08-22022 August 2024
Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024
Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000220/20240022024-08-0505 August 2024
Integrated Inspection Report 05000220/2024002 and 05000410/2024002
ML24215A3002024-08-0202 August 2024
Operator Licensing Examination Approval
ML24213A1412024-07-31031 July 2024
Requalification Program Inspection
NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024
Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024
Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations
ML24198A0852024-07-16016 July 2024
Senior Reactor and Reactor Operator Initial License Examinations
RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024
Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024
License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling
IR 05000220/20244012024-05-30030 May 2024
Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only)
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024
Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request
NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024
2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2
ML24158A2052024-05-15015 May 2024
Annual Radioactive Environmental Operating Report
IR 05000220/20240012024-05-10010 May 2024
Integrated Inspection Report 05000220/2024001 and 05000410/2024001
RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024
Updated Notice of Intent to Pursue Subsequent License Renewal Applications
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024
Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024
Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024
2023 Annual Environmental Operating Report
NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024
Core Operating Limits Report
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
ML24092A3352024-04-0101 April 2024
NRC Office of Investigations Case No. 1-2023-002
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24074A2812024-03-14014 March 2024
Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010
NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024
Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable
IR 05000220/20230062024-02-28028 February 2024
Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006)
NMP1L3570, 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
05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024
Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater
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))
05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023
Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12
IR 05000410/20243012023-12-14014 December 2023
Initial Operator Licensing Examination Report 05000410/2024301
2024-09-04
[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,
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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
