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| | issue date = 01/15/2014 | | | issue date = 01/15/2014 |
| | title = IR 05000373-13-404; 05000374-13-404; 12/02/2013 - 12/06/2013; La Salle County Station, Units 1 and 2; Routine Security Baseline Inspection. (Cover Letter Only) | | | title = IR 05000373-13-404; 05000374-13-404; 12/02/2013 - 12/06/2013; La Salle County Station, Units 1 and 2; Routine Security Baseline Inspection. (Cover Letter Only) |
| | author name = Skokowski R A | | | author name = Skokowski R |
| | author affiliation = NRC/RGN-III/DRS/PSB | | | author affiliation = NRC/RGN-III/DRS/PSB |
| | addressee name = Pacilio M J | | | addressee name = Pacilio M |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000373, 05000374 | | | docket = 05000373, 05000374 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION | | {{#Wiki_filter:UNITED STATES ary 15, 2014 |
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| ==REGION III== | | ==SUBJECT:== |
| 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532
| | LASALLE COUNTY STATION, UNITS 1 AND 2 NRC SECURITY BASELINE INSPECTION REPORT 05000373/2013404; 05000374/2013404 |
| -4352 January 15, 2014
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| Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
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| SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2 NRC SECURITY BASELINE INSPECTION REPORT 05000373/2013404; 05000374/2013404
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| ==Dear Mr. Pacilio:== | | ==Dear Mr. Pacilio:== |
| On December 6, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your LaSalle County Station, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRC's Reactor Oversight Process. | | On December 6, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your LaSalle County Station, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. |
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| The enclosed inspection report documents the inspection results, which were discussed on December 6, 2013, with Mr. H. Vinyard and other members of your staff. | | The enclosed inspection report documents the inspection results, which were discussed on December 6, 2013, with Mr. H. Vinyard and other members of your staff. |
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| The inspection examined activities conducted under your license as they relate to security and compliance with the Commission's rules and regulations and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. | | The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license. |
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| | The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. |
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| No findings were identified during this inspection. | | No findings were identified during this inspection. |
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| In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, "Public Inspections, Exemptions, Requests for Withholding," of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC's Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading | | In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). |
| -rm/adams.html (the Public Electronic Reading Room). | |
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| However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) | | However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. |
| and its disclosure to unauthorized individuals could present a security vulnerability. | |
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| Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS. Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. If you choose to provide a response and Security
| | Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information-Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) |
| -Related Information is necessary to provide an acceptable response, please mark your entire response "Security | | and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. |
| -Related Information | |
| -Withhold from public disclosure under 10 CFR 2.390" in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response. | |
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| Should you have any questions concerning this inspection, we will be pleased to discuss them with you. | | Should you have any questions concerning this inspection, we will be pleased to discuss them with you. |
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| Sincerely, | | Sincerely, |
| /RA/ Richard Skokowski | | /RA/ |
| , Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-373; 50-374 License Nos. NPF | | Richard Skokowski, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18 Nonpublic Enclosure: |
| -11; NPF-18 Nonpublic Enclosure: | | IR 05000373/2013404; 05000374/2013404 w/Attachment: Supplemental Information cc w/encl: S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI B. Desai, RII M. Haire, RIV C. Wilson, LaSalle Station Security Manager J. Klinger, State Liaison Officer, Illinois Emergency Management Agency cc w/o encl: Distribution via ListServTM |
| IR 05000373/2013404; 05000374/2013404 w/Attachment: Supplemental Information cc w/encl: | |
| S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI B. Desai, RII M. Haire, RIV C. Wilson, LaSalle Station Security Manager J. Klinger, State Liaison Officer, Illinois Emergency Management Agency cc w/o encl: Distribution via ListServ TM | |
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Category:Letter
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County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012
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Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
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County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010
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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
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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
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
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
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Operator Licensing Examination Approval Lasalle County Station, May 2023
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Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements
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IR 05000373/20220062023-03-0101 March 2023
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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
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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
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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 ary 15, 2014
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 NRC SECURITY BASELINE INSPECTION REPORT 05000373/2013404; 05000374/2013404
Dear Mr. Pacilio:
On December 6, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your LaSalle County Station, Units 1 and 2. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process.
The enclosed inspection report documents the inspection results, which were discussed on December 6, 2013, with Mr. H. Vinyard and other members of your staff.
The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.
No findings were identified during this inspection.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the PARS component of NRC's ADAMS.
Enclosure contains Sensitive Unclassified Non-Safeguards Information. When separated from enclosure, this transmittal document is decontrolled. If you choose to provide a response and Security-Related Information is necessary to provide an acceptable response, please mark your entire response Security-Related Information-Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1)
and follow the instructions for withholding in 10 CFR 2.390(b)(1). In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely,
/RA/
Richard Skokowski, Chief Plant Support Branch Division of Reactor Safety Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18 Nonpublic Enclosure:
IR 05000373/2013404; 05000374/2013404 w/Attachment: Supplemental Information cc w/encl: S. Coker, NSIR/DSO/DDSO/ST R. Albert, NSIR T. Dimitriadis, RI B. Desai, RII M. Haire, RIV C. Wilson, LaSalle Station Security Manager J. Klinger, State Liaison Officer, Illinois Emergency Management Agency cc w/o encl: Distribution via ListServTM
