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Category:Letter
MONTHYEARML24222A6772024-08-0909 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 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 ML24213A1412024-07-31031 July 2024 Requalification Program Inspection 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) 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 NMP1L3582, Annual Radioactive Environmental Operating Report2024-05-15015 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 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 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 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 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 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 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 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 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 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 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 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 2024-08-09
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARML16319A0982016-11-0808 November 2016 Special Report: Inoperable Drywell Pressure Monitor/Suppression Chamber Water Level Instrumentation ML15174A1282015-06-19019 June 2015 Special Report: Containment High Range Radiation Monitor Instrumentation Channel #12 Inoperable NMP1L2980, 10 CFR 50.46 30-Day Report2014-12-12012 December 2014 10 CFR 50.46 30-Day Report ML12268A0492012-09-12012 September 2012 Discovery of Tritium in Groundwater In-Leakage - 30-Day Report in Accordance with the Industry Ground Water Protection Initiative ML11165A2212011-06-0606 June 2011 Day Report Pursuant to 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors ML1109701512011-04-0101 April 2011 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML0919505792009-07-0808 July 2009 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 11 Inoperable ML0913904002009-05-11011 May 2009 Submittal of Containment High Range Radiation Monitor Instrumentation Channel 11 Inoperable ML0802305112008-01-11011 January 2008 Special Report: Inoperable Suppression Chamber Water Level Instrument ML0701704682007-01-11011 January 2007 Report of Changes or Errors Discovered in the Current Acceptable Emergency Core Cooling System Evaluation Models ML0618703962006-06-19019 June 2006 Special Report; Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Unplanned Maintenance ML0526401672005-09-12012 September 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0525004162005-08-29029 August 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0522402502005-08-0303 August 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0506901722005-03-0101 March 2005 Special Report, Channel No. 11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0502501452005-01-17017 January 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0420403002004-07-12012 July 2004 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Nine Mile Point Unit 1 ML0407607562004-03-0505 March 2004 Special Report, Channel #11 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0406409232004-02-20020 February 2004 Special Report, Channel #12 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0236101942002-12-13013 December 2002 Special Report, Channel #12 Accident Monitoring Instrumentation Inoperable Due to Loss of Power ML0233304002002-10-31031 October 2002 Special Report, Channel #11 Containment High Range Radiation Monitor Declared Inoperable to Repair Failed Chart Recorder ML0207905522002-03-0404 March 2002 Special Report Re Channel 12 Chamber Water Level Indicator Inoperable ML0208404412002-02-25025 February 2002 Special Report, Channel #11 Containment High Range Radiation Monitor Inoperable ML0206502942002-02-20020 February 2002 Special Report Re Channel #12 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0205801952002-02-0808 February 2002 Special Report, Channel #12 Suppression Chamber Water Level Indicator Inoperable ML0205002372002-01-21021 January 2002 Special Report Re Channel 11 Containment Hydrogen Monitoring System Inoperable for Scheduled Elective Maintenance ML18094A0311977-09-0707 September 1977 Telecopy Message from Niagara Mohawk Power Corp Re Event on 9/7/1977 Re August 1977 Liquid Waste Monthly Chemical Composite Analysis ML17037C1301972-08-0101 August 1972 Letter Reporting an Orderly Shutdown on July 27, 1972 Due to Increasing Recirculation System Valve Packing Leakage within the Drywell ML17037C1011972-04-19019 April 1972 Letter Reporting Findings on Incident That Occurred on 12/31/1971 in Which Unit 1 Tripped Off Line as Result of Surveillance Testing ML17037C1021972-04-18018 April 1972 Letter Reporting an Incident Tripped Off-Line as a Result of a Malfunction in a Continuous Power Supply on 02/28/72 ML17037C1371971-09-25025 September 1971 Letter Regarding a Maintenance Item Occurring During the Outage of Unit 1 in April-May 1971 ML17037C1421970-03-10010 March 1970 Letter Reporting an Incident, During Radiography and Ultrasonic Testing, That Disclosed a Series of Cracks Extending Around the Upper 180 Degrees of the Inside Diameter, Exist in the Stainless Steel Safe-End of the Core Spray.. ML17037C1431970-03-0606 March 1970 Letter Notifying the Commission of a Situation in Which Waste Discharge in Excess of Technical Specifications Has Taken Place on February 26, 1970 ML17037C1441969-12-0606 December 1969 Letter Reporting That the Nine Mile Point Reactor Was Scrammed from 25 Percent Power on November 20, 1969 and Advising That the Reactor Will Be Brought Critical and the Turbo-Generator Set Placed on the Line on December 8, 1969 ML17037C1451969-11-18018 November 1969 Letter Reporting an Incident on November 8, 1969 Where the Reactor Scrammed on Momentary Upscale Trips from Intermediate Range Monitoring Channels 2016-11-08
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P.O. Box 63 C EN G S.
a joint venture of Lycoming, New York 13093 Constellation eDF NINE MILE POINT NUCLEAR STATION June 6, 2011 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 30-Day Report Pursuant to 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors In accordance with 10 CFR 50.46(a)(3)(ii), Nine Mile Point Nuclear Station, LLC (NMPNS) hereby provides notification of a significant change to and errors in the Nine Mile Point Unit 1 (NMP1)
Emergency Core Cooling System (ECCS) evaluation model.
10 CFR 50.46(a)(3)(ii) requires that a significant change to or error in an ECCS evaluation model be reported to the NRC. A significant change or error is one that results in a calculated peak cladding temperature (PCT) different by more than 50'F from the temperature calculated using the last acceptable model or is a cumulation of changes and errors such that the sum of the absolute magnitudes of the respective temperature changes is greater than 50'F.
On May 3, 2011, NMPNS was informed by its fuel vendor (GE Hitachi (GEH)) of a change in its ECCS evaluation model PCT calculation that could affect NMP1. This change was required to address three individual errors and a model change identified by GEH for the previous calculation of record. On May 6, 2011, based on the information provided by GEH, NMPNS determined that correction of one of the identified errors resulted in a greater than 50'F increase in calculated PCT. Also, the sum of the absolute magnitudes of the respective temperature changes due to the three individual errors and the model change was greater than 50'F. Therefore, the error(s) and model change meet the 30-day reporting requirements delineated in 10 CFR 50.46(a)(3)(ii).
The Attachment provides a description of the errors and model change, the actions taken, and a tabular summary of the impact on the calculated PCT.
1~ Document Control Desk June 6, 2011 Page 2 There are no regulatory commitments in this submittal.
Should you have questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.
Very truly yours, Alex D. Sterio Manager Engineering Services -
Acting ADS/JMT
Attachment:
10 CFR 50.46 ECCS Evaluation Model - Errors and Model Change cc: Regional Administrator, NRC Project Manager, NRC Resident Inspector, NRC
ATTACHMENT 10 CFR 50.46 ECCS EVALUATION MODEL - ERRORS AND MODEL CHANGE Nine Mile Point Nuclear Station, LLC June 6, 2011
ATTACHMENT 10 CFR 50.46 ECCS EVALUATION MODEL - ERRORS AND MODEL CHANGE On May 3, 2011, Nine Mile Point Nuclear Station, LLC (NMPNS) was informed by its fuel vendor (GE Hitachi (GEH)) of a change in its Emergency Core Cooling System (ECCS) evaluation model peak clad temperature (PCT) calculation that could affect Nine Mile Point Unit I (NMP1). This change was required to address three individual errors and a model change identified by GEH for the previous calculation of record. On May 6, 2011, based on the information provided by GEH, NMPNS determined that correction of one of the identified errors resulted in a greater than 50'F increase in calculated PCT.
Also, the sum of the absolute magnitudes of the respective temperature changes due to the three individual errors and the model change was greater than 50'F. Therefore, the errors and model change meet the 30-day reporting requirements delineated in 10 CFR 50.46(a)(3)(ii). A description of the four individual notifications regarding the ECCS evaluation model, as detailed by the vendor, is as follows:
GEH Notification Letter 2011-01, Impact of CORCL Bundle Power Correction - Part-length Rods (Reference 1):
An option in the CORCL code distributes power in a manner considering part-length rods in the bundle. This modeling technique has been found to be non-conservative in that it slightly under predicts the total power generated in the hot bundle. As such, the PCT results in calculations using this option would be non-conservative.
This error impacted the NMP1 GElI fuel with a PCT effect of +60'F.
GEH Notification Letter 2011-03, Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and 1 Ox] 0 Fuel Bundles (Reference 2):
In the input formulation for the SAFER model, input coefficients are used to direct the deposition of gamma and neutron radiation energy produced by fuel fissions and decay heat, determining whether it would heat the fuel rod, cladding, channel, or control rod structural materials. The contribution of heat from gamma ray absorption by the channel was found to have been minimized. The method had been simplified such that initially all the energy was assumed to be deposited in the fuel rods prior to the Loss-of-Coolant-Accident (LOCA) and then adjusted such that the correct heat deposition was applied after the scram. This modeling was determined to be potentially non-conservative, as not accounting for this small fraction of total power generation outside the fuel rod would tend to suppress the hot bundle power required to meet the initial operating Planar Linear Heat Generation Rate (PLHGR). Also, there is a small effect on the initial conditions for the balance of the core as these are set in relation to the hot bundle condition.
This error impacted the NMP1 GEl 1 fuel with a PCT effect of-25'F.
GEH Notification Letter 2011-04, Impact of Droplet Flow Distribution Arra Alignment to Rod Groupings Error (Reference 3):
Programmed enhancements to the CORCL code allowed for an increased number of rod groupings to be defined so as to more accurately represent bundle configuration in the ECCS-LOCA analysis. It was noted that an array in the model, which describes distribution of droplets and film cooling from core spray across the several groupings of rods and the channel, was not populated with corresponding additional elements. This had the effect of denying the channel and peripheral groupings of this core spray distribution, preferentially distributing liquid film and droplets with cooling effect to represented rod groupings. This condition is potentially non-conservative for calculating temperatures in those groupings where the PCT may occur.
This error impacted the NMP1 GEl 1 fuel with a PCT effect of-30'F.
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ATTACHMENT 10 CFR 50.46 ECCS EVALUATION MODEL - ERRORS AND MODEL CHANGE GEHNotification Letter 2011-05, Impact of Update in CORCL Code Version (Reference 4):
The CORCL code has been updated to Version CORCL07E3. The update provided added functionality of the code with respect to power distribution, increased the number of rod groups that can be modeled, included PRIME-based properties on fuel, corrected film cooling that was credited and provided other updates by way of code maintenance.
This model change impacted the NMP1 GEl 1 fuel with a PCT effect of+35'F.
The combined impact of the errors and the model change described above is a +40'F increase in the calculated NMP1 fuel PCT from 2150'F to 2190'F (i.e., below the 10 CFR 50.46 acceptance criterion of 2200-F).
In anticipation of the GEH Notifications, the NMP1 evaluation model was corrected prior to the startup from the Spring 2011 refueling outage to resolve the identified errors and address the model change. The NMP1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits were adjusted through a plant monitoring system (i.e., 3D Monicore) update to maintain the desired PCT margin of 50'F. The updated MAPLHGR limits have also been included in the NMP1 Core Operating Limits Report (COLR) for the current operating cycle (Cycle 20) which commenced following the 2011 outage.
As such, NMP1 is in full compliance with 10 CFR50.46 PCT requirements. Note that although Global Nuclear Fuel (GNF2) fuel was installed during the refueling outage, NMP1 did not operate with GNF2 fuel prior to the MAPLGHR adjustments and model corrections being made.
The individual effect of each error and model change is also described in the attached Table, LOCA Margin Summary Sheet - 30 Day Report, Nine Mile Point Nuclear Station, Nine Mile Point Unit 1.
References
- 1) GE Hitachi Nuclear Energy 10 CFR 50.46 Notification Letter 2011-01 for Nine Mile Point Unit 1, "Impact of CORCL Bundle Power Correction - Part-length Rods," April 29, 2011
- 2) GE Hitachi Nuclear Energy 10 CFR 50.46 Notification Letter 2011-03 for Nine Mile Point Unit 1, "Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9x9 and l0x10 Fuel Bundles," April 29, 2011
- 3) GE Hitachi Nuclear Energy 10 CFR 50.46 Notification Letter 2011-04 for Nine Mile Point Unit 1, "Impact of Droplet Flow Distribution Array Alignment to Rod Groupings Error," April 29, 2011
- 4) GE Hitachi Nuclear Energy 10 CFR 50.46 Notification Letter 2011-05 for Nine Mile Point Unit 1, "Impact of Update in CORCL Code Version," April 29, 2011 2 of 3
ATTACHMENT 10 CFR 50.46 ECCS EVALUATION MODEL - ERRORS AND MODEL CHANGE Table LOCA Margin Summary Sheet - 30 Day Report Nine Mile Point Nuclear Station Nine Mile Point Unit 1 Evaluation Model: General Electric SAFER / GESTR - LOCA Methodology Net Absolute PCT Effect PCT Effect A. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = 00F 00F Previous Years B. Prior 10 CFR 50.46 Changes or Error Corrections - APCT = OOF O0F This Year C. Current 10 CFR 50.46 Changes:
- 1. Notification 2011-01 (GEl 1) APCT = 60OF 60OF
- 2. Notification 2011-03 (GEl 1) APCT = -25OF 250F
- 3. Notification 2011-04 (GE 11) APCT = -30OF 30°F
- 4. Notification 2011-05 (GEl 1) APCT = 35 0F 35OF 150 F Absolute Sum of 10 CFR 50.46 Changes APCT =
The sum of the PCT from the most recent analysis using an acceptable evaluation model and the estimates of PCT impact for changes and errors identified since this analysis is less than 22000 F.
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