Letter Sequence Other |
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MONTHYEARRS-09-133, Attachment 6, LaSalle, Unit 2, Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex2009-08-31031 August 2009
Attachment 6, LaSalle, Unit 2, Nuclear Power Station Spent Fuel Storage Pool Criticality Safety Analysis with Neutron Absorbing Inserts and Without Boraflex
Project stage: Request
ML0931705992009-12-0202 December 2009
Request for Withholding Information from Public Disclosure by Letter Dated 10/5/09
Project stage: Withholding Request Acceptance
ML1009802092010-04-26026 April 2010
Request for Additional Information Related to License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: RAI
ML1011904862010-05-0303 May 2010
Notice of Meeting with Exelon, LaSalle, Units 1 and 2, to Discuss Response to Request for Additional Information License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks
Project stage: RAI
ML1016502292010-06-10010 June 2010
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Other
ML1016502862010-06-23023 June 2010
June 1, 2010, Summary of Meeting with Exelon Generation Co., LLC, on Responses to Request for Information License Amendment Request for the Use of Netco-SNAP-In Rack Inserts
Project stage: RAI
ML1028003592010-10-0707 October 2010
Notice of Public Meeting with Exelon Generation Company, LLC, Regarding LaSalle Netco Insert Request
Project stage: Meeting
ML1030004242010-10-28028 October 2010
Notice of Meeting with Exelon Genertion Company to Discuss the License Amendment Request to Allow Full Recovery of Spent Fuel Storage Rack Cells That Are Unusable Due to Boraflex Neutron Absorber Degradation
Project stage: Meeting
ML1030704842010-11-19019 November 2010
Summary of Public Meeting with Exelon Generation Company, LLC Regarding LaSalle Netco Insert Request
Project stage: Meeting
ML1030903782010-11-19019 November 2010
Licensee Handouts for LaSalle Meeting with Exelon to Discuss Netco Inserts
Project stage: Meeting
ML1032104992010-11-19019 November 2010
Request for Additional Information, Related to the Use of Neutron Absorbing Inserts
Project stage: RAI
RS-10-202, Additional Information Supporting License Amendment Request Re Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2010-11-23023 November 2010
Additional Information Supporting License Amendment Request Re Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1034304232010-12-10010 December 2010
Request for Additional Information Related to the Use of Nuetron Absorbing Inserts
Project stage: RAI
RS-10-210, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2010-12-14014 December 2010
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1034904622010-12-16016 December 2010
Notice of Meeting with Exelon Generation Company, LLC Regarding LaSalle Netco Insert Request
Project stage: Meeting
RS-10-216, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2010-12-22022 December 2010
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1100503592010-12-29029 December 2010
NRC Meeting Slides for December 29, 2010, Public Conference Call with Exelon Generation Company Regarding LaSalle Netco Insert Request
Project stage: Meeting
ML1101300742011-01-11011 January 2011
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1100502552011-01-17017 January 2011
December 29, 2010, Summary of Public Conference Call with Exelon Generation Company, LLC, Regarding LaSalle Netco Insert Request
Project stage: Other
ML1101803312011-01-24024 January 2011
Proposed License Conditions Related to Use of Neutron Absorbers
Project stage: Other
RS-11-009, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2011-01-24024 January 2011
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1102500512011-01-28028 January 2011
Issuance of Amendments Concerning Spent Fuel Neutron Absorbers
Project stage: Approval
RS-11-014, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2011-01-28028 January 2011
Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks
Project stage: Request
ML1104606172011-03-0404 March 2011
Request for Additional Inforamtion Related to the Use of Neutron Absorbing Inserts
Project stage: Other
RS-11-067, Response to Request for Additional Information Regarding Unit 2 Spent Fuel Pool Storage Racks2011-04-18018 April 2011
Response to Request for Additional Information Regarding Unit 2 Spent Fuel Pool Storage Racks
Project stage: Response to RAI
RS-11-109, Completion of License Condition 2.C.(30) Associated with Unit 2 Spent Fuel Pool Storage Racks2011-07-13013 July 2011
Completion of License Condition 2.C.(30) Associated with Unit 2 Spent Fuel Pool Storage Racks
Project stage: Other
RS-11-170, Completion of License Condition 2.C.(31) Associated with Unit 2 Spent Fuel Pool Storage Racks2011-10-20020 October 2011
Completion of License Condition 2.C.(31) Associated with Unit 2 Spent Fuel Pool Storage Racks
Project stage: Other
2010-04-26
[Table View] |
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Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024
County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004
ML24024A1332024-01-24024 January 2024
Confirmation of Initial License Examination
IR 05000373/20230122024-01-18018 January 2024
County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012
ML23354A2902024-01-0505 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML23360A6082023-12-27027 December 2023
County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
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
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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
ML23317A1192023-11-10010 November 2023
Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
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
IR 05000373/20230032023-11-0909 November 2023
County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001
ML23286A2602023-11-0808 November 2023
Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report
IR 05000373/20234012023-11-0707 November 2023
County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401
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
IR 05000374/20230102023-10-11011 October 2023
NRC Inspection Report 05000374/2023010
IR 05000373/20233012023-09-15015 September 2023
Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301
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
ML23212A9012023-08-0303 August 2023
Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report
IR 05000373/20230022023-08-0101 August 2023
County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002
ML23208A3182023-07-27027 July 2023
Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI
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
ML23192A5272023-07-12012 July 2023
NRC Initial License Examination Report 05000373/2023301; 05000374/2023301
ML23186A2062023-07-0606 July 2023
Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010
ML23181A1502023-06-30030 June 2023
Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
IR 05000373/20230112023-06-26026 June 2023
County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011
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
ML23167A0352023-06-16016 June 2023
Registration of Use of Cask to Store Spent Fuel
ML23171A9562023-06-12012 June 2023
Post Exam Ltr
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 05000373/20230012023-05-10010 May 2023
County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001
ML23123A2202023-05-0303 May 2023
Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection
ML23118A3472023-05-0101 May 2023
County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143
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Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
ML23081A0382023-04-25025 April 2023
County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
ML23110A3202023-04-21021 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML23107A1822023-04-18018 April 2023
Operator Licensing Examination Approval Lasalle County Station, May 2023
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Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23073A2182023-03-22022 March 2023
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Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements
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Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
IR 05000373/20220062023-03-0101 March 2023
Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006)
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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
ML23024A1372023-02-0303 February 2023
Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2
ML23031A1972023-01-31031 January 2023
Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011
IR 05000373/20220042023-01-31031 January 2023
County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004
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
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2024-01-05
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 January 24, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 - PROPOSED LICENSE CONDITIONS RELATED TO USE OF NEUTRON ABSORBERS (TAC NOS. ME2376 AND ME2377)
Dear Mr. Pacilio:
By letter dated October 5,2009, supplemented by letters dated June 10, November 23, December 14, December 22, 2010, and January 11, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092810279, ML101650229, ML103270566, ML103490098, ML103570025, and ML110130074, respectively) Exelon Generation Company, LLC (EGC, Exelon, or the licensee), requested changes to the Technical Specifications for LaSalle County Station (LSCS),
Units 1 and 2 spent fuel pool (SFP) storage requirements. The request is required to accommodate degradation in the installed neutron absorber in the LSCS Unit 2 SFP.
For LSCS Unit 2 SFP rack modules that do not contain the NETCO-SNAP-IN inserts, the licensee continues to rely on BORAFLEX to control reactivity. A large number of BORAFLEX panels have degraded below the 0.020 gram per centimeter-square Boron-10 (gm/cm 2 B10 )
areal density modeled in the analysis of record. The information provided at this point regarding EGC's actions is not sufficient to allow the Nuclear Regulatory Commission (NRC) to reach a final licensing decision. As a result, the NRC staff has determined that several license conditions (LC) will be necessary to address the crediting o'f boron in the LSCS Unit 2 SFPs.
The NRC staff proposed the following as LC 2.(C):
(30) Beginning 120 days after the LSCS Unit 2 refueling outage 13 (L2R13) and until October 28, 2011, the storage cells in the rack models without NETCO-SNAP-IN inserts will be placed into one of three categories: Unrestricted, Restricted, and Unusable.
- a. Unrestricted will be cells whose minimum panel B10 areal density is greater than or equal to 0.0167 gm/cm 2 . Unrestricted cells may contain fuel assemblies up to the maximum reactivity identified in TS 4.3.1.1.d.
- b. Restricted will be cells whose minimum panel B10 areal density is between 0.0167 gm/cm 2 and 0.0115 gm/cm 2 . Restricted cells will only contain LSCS Units 1 and 2 Cycle 1 General Electric (GE) and GE14 fuel assemblies.
- c. Unusable will be cells whose minimum panel B10 areal density is less than or equal to 0.0115 gm/cm 2 . Unusable cells will be administratively controlled to remain empty of any fuel assembly.
M. Pacilio -2 (31) After October 28, 2011, until all NETCO-SNAP-IN inserts have been fully loaded into the LSCS Unit 2 SFP, the following categories will apply: Unrestricted, Restricted, and Unusable.
- a. Unrestricted will be cells whose minimum panel B10 areal density is greater than or equal to 0.0200 gm/cm 2 . Unrestricted cells may contain fuel assemblies up to the maximum reactivity identified in TS 4.3.1.1.d.
- b. Restricted will be cells whose minimum panel B10 areal density is between 0.0200 gm/cm 2 and 0.0167 gm/cm 2 . Restricted cells will only contain LSCS Units 1 and 2 Cycle 1 GE and GE14 fuel assemblies.
- c. Unusable will be cells whose minimum panel B10 areal density is less than or equal to 0.0167 gm/cm 2 . Unusable cells will be administratively controlled to remain empty of any fuel assembly.
(32) Exelon shall complete loading all accessible storage rack cells in the LSCS Unit 2 spent fuel pool with NETCO-SNAP-IN inserts no later than December 31,2014.
These proposed LCs were discussed with Patrick Simpson and Ken Nicely of your staff on January 13, 2011. In order to support the issuance of the safety evaluation in a timely fashion, Exelon should provide a response to the proposed license conditions indicating Exelon's understanding and acceptance of these conditions. It should be noted, however, that the acceptance does not constitute completion of the NRC staff's review regarding crediting of BORAFLEX until the NETCO-SNAP-IN inserts can be fully loaded into the SFP.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: Distribution via Listserv
M. Pacilio -2 (31) After October 28, 2011, until all NETCO-SNAP-IN inserts have been fUlly loaded into the LSCS Unit 2 SFP, the following categories will apply: Unrestricted, Restricted, and Unusable.
- a. Unrestricted will be cells whose minimum panel B'o areal density is greater than or equal to 0.0200 gm/cm 2 . Unrestricted cells may contain fuel assemblies up to the maximum reactivity identified in TS 4.3.1.1.d.
- b. Restricted will be cells whose minimum panel B'o areal density is between 0.0200 gm/cm 2 and 0.0167 gm/cm 2 . Restricted cells will only contain LSCS Units 1 and 2 Cycle 1 GE and GE14 fuel assemblies.
- c. Unusable will be cells whose minimum panel B'o areal density is less than or equal to 0.0167 gm/cm 2 . Unusable cells will be administratively controlled to remain empty of any fuel assembly.
(32) Exelon shall complete loading all accessible storage rack cells in the LSCS Unit 2 spent fuel pool with NETCO-SNAP-IN inserts no later than December 31,2014.
These proposed LCs were discussed with Patrick Simpson and Ken Nicely of your staff on January 13, 2011. In order to support the issuance of the safety evaluation in a timely fashion, Exelon should provide a response to the proposed license conditions indicating Exelon's understanding and acceptance of these conditions. It should be noted, however, that the acceptance does not constitute completion of the NRC staff's review regarding crediting of BORAFLEX until the NETCO-SNAP-IN inserts can be fully loaded into the SFP.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 Resource RidsNrrDssSrxb RidsNrrPMLaSalie Resource RidsNrrLATHarris Resource RGrover, NRR KWood, NRR RidsOgcRp Resource RidsNrrDorlDpr Resource MYoder,NRR EWong, NRR RidsNrrDirsltsb Resource RidsAcrsAcnw_MailCTR Resource APulvirenti, RES RidsRgn3MailCenter Resource RidsNrrDciCsgb ADAMS ACCESSION NO MI-110180331 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC OGC 1 NLO DORUDD MSmith AHowe NAME EBrown THarris RCarlson (NDiFrancesco for)
DATE 01/24/11 01/20/11 01/21/11 01/24/11 01/24/11 OFFICIAL RECORD COPY
