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Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024
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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
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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
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ML23121A1612023-05-0101 May 2023
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
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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
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
ML23073A2182023-03-22022 March 2023
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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
ML23061A1632023-03-0303 March 2023
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)
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
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
Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
2024-01-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 September 16, 2010 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNIT 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Pacilio:
On November 29, 2010, the NRC will begin inspection of refueling and other outage activities (NRC Inspection Procedure 71111.20). This inspection will utilize NRC Operating Experience Smart Sample: (OpESS) FY2007-03, Revision 2, Crane and Heavy Lift Inspection, Supplemental Guidance for IP-71111.20, issued September 12, 2008. This inspection will focus on the impact of load handling activities on the reactor core and its cooling and plant support systems. Specifically, this inspection will review applicable design and licensing bases, engineering design and analysis, procedures, and surveillances associated with reactor vessel head removal and installation during refuel outages including: (1) reactor building crane preventative maintenance, inspections, and testing; (2) heavy load rigging equipment; (3) safe heavy load paths; and (4) single failure proof or single failure proof equivalency evaluations (or heavy load drop analyses), as applicable. The on-site inspection is scheduled to take place on November 29 through December 3, 2010, and December 13 through December 17, 2010.
Experience has shown that inspection of these activities is resource intensive both for the NRC inspector and licensee staff. In order to minimize the inspection impact to the site and to ensure a productive inspection for both parties, we have enclosed a request for information needed for the inspection. This information should be available in Region III by November 15, 2010 (preparation week). It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. S. Shields, of your organization. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Neurauter, at (630) 829-9828.
M. Pacilio This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.
The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-374 License No. NPF-18
Enclosure:
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST Inspection Report: 05000373/2010-005; 05000374/2010-005 Inspection Dates: November 29 - December 3, 2010 and December 13 - 17, 2010 Inspection Procedures: IP 71111.20, ARefueling and Other Outage Activities@
NRC Operating Experience Smart Sample: (OpESS) FY2007-03, Revision 2, Crane and Heavy Lift Inspection, Supplemental Guidance for IP-71111.20, issued September 12, 2008 (available at NRC Web site at http://www.nrc.gov/reactors/operating/ops-experience/opess/2007/index.html)
Inspector: Jim Neurauter (630) 829-9828 A. Information Requested for the In-Office Preparation Week The following information (electronic copy CD ROM if possible) is requested to be available at the Region III office on November 15, 2010. If you have any questions regarding this information, please call the inspector as soon as possible.
- 1) A copy of the following documents related to heavy load control during removal or installation of the reactor vessel head:
a) Completed Engineering Change (EC) for upgrade of reactor building crane heavy load handling structures, systems, and components to single-failure-proof-equivalency.
b) Title 10 CFR 50.59 Evaluation for the upgrade of reactor building crane heavy load handling structures, systems, and components to single-failure-proof-equivalency.
c) Matrix (if performed) that demonstrates the completed EC upgrade to single-failure-proof-equivalency is in compliance with Nuclear Energy Institute (NEI) 08-05, Industry Initiative on Control of Heavy Loads,@
Revision 0 (ADAMS Accession No. ML082180666) and the NRC Staff Safety Evaluation addressing NEI 08-05 (ADAMS Accession No. ML082410532).
d) Documents that establish the crane total lifted weight for movement of the shield plugs, reactor pressure vessel head, steam dryer, and steam separator.
e) Design calculations for the shield plugs, reactor pressure vessel head, steam dryer, and steam separator lifting devices.
1 Enclosure
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST f) Design calculations for interfacing lift points, i.e., reactor pressure vessel head lifting lugs.
g) Design calculations and site procedures associated with control of heavy loads - safe load paths for movement of the shield plugs, reactor pressure vessel head, steam dryer, and steam separator during refueling operations.
h) Reactor building crane vendor recommendations regarding preventative maintenance, and inspections and testing prior to use.
i) Site procedures associated with reactor building crane preventative maintenance, inspection, and testing prior to lifting the reactor pressure vessel head.
j) Documentation for reactor building crane preventative maintenance, inspection, and testing performed during last refueling outage prior to lifting the reactor pressure vessel head.
k) Documentation for visual inspections performed prior to use during last refueling outage on lifting devices for shield plugs, reactor pressure vessel head, steam dryer, and steam separator.
l) Site procedures associated with non-destructive examination (NDE) of the load bearing components for the shield plugs, reactor pressure vessel head, steam dryer, and steam separator lifting devices.
m) Documentation for the last non-destructive examination (NDE) performed for all load bearing components of the shield plugs, reactor pressure vessel head, steam dryer, and steam separator lifting devices.
- 2) A copy of the LaSalle UFSAR.
If you have questions regarding the information requested, please contact the lead inspector.
2 Enclosure
M. Pacilio In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-374 License No. NPF-18
Enclosure:
REFUELING AND OTHER OUTAGE ACTIVITIES INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ DISTRIBUTION:
Susan Bagley RidsNrrDorlLpl3-2 Resource RidsNrrPMLaSalle RidsNrrDirsIrib Resource Steven Reynolds Steven Orth Jared Heck Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports Resource DOCUMENT NAME: G:\DRS\WIP\Ltr 09__10 LaSalle Request for Information JEN.docx 9 Publicly Available 9 Non-Publicly Available 9 Sensitive 9 Non-Sensitive To receive a copy of this document, indicate in the concurrence box C = Copy without attach/encl; E = Copy with attach/encl N = No copy OFFICE RIII RIII NAME JNeurauter:ls DHills DATE 9/16/10 9/16/10 OFFICIAL RECORD COPY
