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Category:Letter type:RS
MONTHYEARRS-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
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
RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024
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
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
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
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
RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023
Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information
RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
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
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
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
RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023
Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis
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
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
RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023
Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023
Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements
RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023
Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
RS-22-085, Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-01-12012 January 2023
Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis
RS-23-006, Supplemental Information Regarding License Amendment Request – Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report2023-01-10010 January 2023
Supplemental Information Regarding License Amendment Request – Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022
Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022
Response to Request for Additional Information License Amendments Related to Fuel Storage
RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022
Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022
Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans
RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022
Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical
RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022
Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists
RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V2022-04-0404 April 2022
Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Va
RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations
RS-22-035, Supplemental Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0404 March 2022
Supplemental Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
RS-22-033, Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0303 March 2022
Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0202 March 2022
Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs
RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022
Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement
RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022
Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P
RS-22-018, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2022-02-22022 February 2022
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022
Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists
RS-22-013, Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval2022-02-0909 February 2022
Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval N
RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022
Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC
RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022
Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021
Proposed Changes to Decommissioning Trust Agreements and Master Terms
RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.52021-11-0404 November 2021
Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5
RS-21-109, Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 20212021-10-14014 October 2021
Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 2021
RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021
Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes
RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021
Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel
RS-21-085, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016)2021-08-17017 August 2021
Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016)
RS-21-064, License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter2021-06-30030 June 2021
License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter
RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021
Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
2024-09-12
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Text
Exelon Generation Company, LLC www.exeloncorp.com 4300 Winfield Road Nuclear Warrenville, IL 60555 RS-12-030 10 CFR 50.90 February 13, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Unit 1 Facility Operating License No. NPF-11 NRC Docket No. 50-373
Subject:
Supplemental Information Supporting the January 30,2012, Response to NRC RAI-03-1 (TAC No. ME7331)
References:
- 1. Letter from D. M. Gullott (Exelon Generation Company, LLC (EGC>> to U. S. NRC, "Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit," dated October 12, 2011
- 2. Letter from U. S. NRC to Mr. Michael J. Pacilio (EGC), "LaSalle County Station, Unit 1 -Request for Additional Information Regarding Proposed Technical Specification Safety Limit Minimum Critical Power Ratio Changes (TAC No. ME7331)," dated January 19, 2012
- 3. Letter from D. M. Gullott (Exelon Generation Company, LLC (EGC>> to U. S. NRC, "Supplemental Information Supporting the Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit (TAC No. ME7331)," dated January 30,2012 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to Appendix A, Technical Specifications (TS), of Facility Operating License No. NPF-11 for LaSalle County Station (LSCS), Unit 1. The proposed change revises the value of the safety limit minimum critical power ratios (SLMCPRs) in TS Section 2.1.1, "Reactor Core SLs." These changes are needed to support the upcoming cycle of operation (Le., Cycle 15) for LSCS, Unit 1. In Reference 2, the NRC requested that EGC provide additional information in support of their review of Reference 1. In Reference 3 EGC responded to the NRC's Reference 2 request. Following the submittal of Reference 3 EGC determined that additional information is required to supplement its Reference 3 response to NRC RAI-03-1. The supplemental information is contained in the Attachment to this letter.
February 13, 2012 U. S. Nuclear Regulatory Commission Page 2 The information provided in this letter does not affect the No Significant Hazards Consideration or the Environmental Consideration provided in Attachment 1 of the original license amendment request as described in the Reference 1 submittal.
In accordance with 10 CFR 50.91 (b), "State consultation," EGC is providing the State of Illinois with a copy of this letter and its attachment to the designated State Official.
This letter contains no new regulatory commitments. If you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 13th day of February, 2012.
Respectfully,
~2;J~
David M. Gullott Manager - Licensing Exelon Generation Company, LLC
Attachment:
Supplemental Information Supporting the January 30, 2012, Response to NRC RAI-03-1
Attachment Supplemental Information Supporting the January 30,2012, Response to NRC RAI-03-1
Supplemental Information Supporting the January 30,2012, Response to NRC RAI-03-1 In a letter dated January 19, 2012, the NRC requested that Exelon Generation Company, LLC (EGC) provide additional information in support of their review of EGC's October 12, 2011, license amendment request (Le., ML112860068) to modify the LaSalle County Station (LSCS),
Unit 1 Technical Specifications (TS), Section 2.1.1, "Reactor Core SLs." One of the NRC's requests was as follows:
- 3. GNF2 fuel deviates from traditional10x10 design through the introduction of a partial length rod configuration, the use of higher linear power, and the use of mixing vanes. The NRC staff considers this a new fuel design with regards to the four restrictions identified in the safety evaluation of General Electric (GE)
Licensing Topical Reports NEDC-32601 P, NEDC-32694, and Amendment 25 to NEDE-24011-P-A. Given that LSCS, Unit 1, Cycle 15, uses a core loading pattern which includes GNF2 fuel, provide the following: (1) an evaluation of the four restrictions in NEDC-32601 P, NEDC-32694 and Amendment 25 to NEDE-24011-P-A and the applicability to mixed core with ATRIUM 10 fuel; A portion of EGC's response to this question included the following discussion of how the four restrictions were addressed:
The four restrictions applied specifically to the mixed core were addressed during the transition from ATRIUM-10 to GNF2 fuel. These limitations were addressed for ATRIUM-10 as follows:
(1) The TGBLA fuel rod power calculational uncertainty for A TRIUM-1 0 was determined and verified.
(2) The rod power calculation uncertainties were used to reevaluate and confirm the R-factor uncertainty for ATRIUM-10.
(3) The applicability of the Minimum Critical Power Ratio (MCPR)
Importance Parameter (MIP) criterion was previously reevaluated through the inclusion of plants containing A TRIUM-1 0 fuel in the data contained in Figure 5 of Attachment 5.
(4) The bundle power uncertainty associated with the core monitoring system was verified by Exelon as applied to A TRIUM-1 O.
Supplemental Information Related to NRC RAI-03-1 In addition to the previous EGC response to NRC RAI-03-1, please note the following supplemental information regarding the analysis to address four restrictions on the use of NEDC-32601 P-A, "Methodology and Uncertainties for Safety Limit MCPR Evaluations," and NEDC-32694 P-A, "Power Distribution Uncertainties for Safety Limit MCPR Evaluations," for ATRI UM-1 0 fuel:
(1) The TGBLA fuel rod power calculational uncertainty for ATRIUM-1 0 was verified through extensive comparisons of TGBLA and MCNP. Comparisons included lattice k oo values and lattice pin power peaking at different exposure, temperature, and control conditions. The Page 1 of 2
Supplemental Information Supporting the January 30,2012, Response to NRC RAI-03-1 comparisons included comparisons to TGBLA accuracy for Global Nuclear Fuel (GNF) 1Ox1 0 fuel designs to demonstrate that TGBLA accuracy had not been degraded for ATRIUM-10 fuel in comparison to the accuracy of analyses for standard GNF fuel product offerings. This analysis is documented in GNF's internal design record file (eDRF) Section 0000-0015-4032 Rev. 0 and applies to ATRIUM-10 fuel in LSCS, Unit 1 Cycle 15. GNF then received confirmation from EGC that the standard GNF manufacturing uncertainties were bounding when compared to the uncertainties associated with the manufacture of ATRIUM-10fuel as documented in GNF eDRF Section 0000-0130-2044. This information, when combined with uncertainties inherent in GNF methodologies, confirmed that the standard rod power calculational uncertainty described in NEDC-32601 P-A, Section 3.1 is applicable to ATRIUM-10 fuel.
(2) The rod power calculation uncertainties were used to reevaluate and confirm the R-factor uncertainty for ATRIUM-10. The above uncertainty, combined with uncertainties inherent in GNF methodologies, demonstrated that the R-Factor uncertainty contained in NEDC-32601 P-A, Section 3 is applicable to ATRIUM-10 fuel. This analysis is documented in GNF eDRF Section 0000-0136-9407 Rev. O.
(3) The applicability of the minimum critical power ratio (MCPR) Importance Parameter (MIP) criterion was evaluated through the inclusion of plants containing ATRIUM-10 fuel in the data contained in Figure 5 of Attachment 5 of the referenced letter. The following points in the table supplied in response to RAI-05 contain ATRIUM-10 fuel: the 1st, 4th, and 5th points. This can be seen from the table as the combined GE14 and GNF2 batch fractions for these points do not add up to 100%; the remaining fuel for these points is ATRIUM-10 fuel. As can be seen by locating these pOints on the plot in Figure 5 of Attachment 5, each one is above the MIP correlation, demonstrating the continued generic conservatism of this correlation. Additionally, Section 2.6 of Attachment 5 of the referenced letter demonstrates that if limiting SLMCPR case for LSCS 1 Cycle 15 were plotted on Figure 5, it would also lie above the MIP correlation line, demonstrating the conservatism of this correlation for this specific application.
(4) Initially, GNF provided EGC with a proposed effective bundle power uncertainty for use in the LSCS, Unit 1 Cycle 15 SLMCPR analysis. In response to an EGC request, AREVA provided information related to the characteristics of ATRIUM-10 fuel to EGC to in a letter from A. W. Will (Framatome ANP, Inc) to F. W. Trikur (EGC), "Assembly Power Distribution and MCPR Uncertainties for LaSalle ATRIUM-10 Fuel," dated April 18, 2003. EGC compared the value proposed by GNF to the value that had been provided by AREVA for use with ATRIUM-10 fuel in the POWERPLEX-III core monitoring system that is used at LSCS, Unit 1. EGC concluded that the value proposed by GNF bounded the value provided by AREVA; therefore, the GNF-proposed effective bundle power uncertainty was found to be appropriate for use in the LSCS, Unit 1 Cycle 15 SLMCPR analysis.
Reference Letter from D. M. Gullott (Exelon Generation Company, LLC (EGC>> to U. S. NRC, "Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit," dated October 12, 2011 (ML112860068)
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