|
---|
Category:Letter type:RS
MONTHYEARRS-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 Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V 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-22-015, 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-21-063, 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 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-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-055, Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended.2021-05-10010 May 2021 Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended. RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations RS-21-050, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-16016 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-045, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-0707 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-040, Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-03-31031 March 2021 Response to Second Round Request for Additional Information (Rais) for License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-21-043, Supplemental Information Regarding Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 22021-03-26026 March 2021 Supplemental Information Regarding Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2 RS-21-042, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 22021-03-26026 March 2021 Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs, Revision 2 RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments RS-21-035, Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs2021-03-0909 March 2021 Relief Request I4R-12 Relief from Code Examinations for 2B33-F060A and 2B33-F060B Repairs 2023-08-04
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-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 ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements 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-23-006, 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 ML22332A4492022-11-10010 November 2022 License Amendment Request - Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report 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-22-004, 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 ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments 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 JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position 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-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-087, Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink2020-07-17017 July 2020 Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process RS-20-011, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2020-01-31031 January 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-20-009, Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-01-31031 January 2020 Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-18-032, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2018-04-25025 April 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers RS-18-028, License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator2018-04-19019 April 2018 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) RS-18-023, License Amendment Request to Revise the Technical Specifications (TS) Surveillance Requirement (SR) 3.4.4.1 to Revise the Lower Setpoint Tolerances for Safety/Relief Valves (S/Rvs)2018-02-27027 February 2018 License Amendment Request to Revise the Technical Specifications (TS) Surveillance Requirement (SR) 3.4.4.1 to Revise the Lower Setpoint Tolerances for Safety/Relief Valves (S/Rvs) RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1752018-01-31031 January 2018 Attachment 5A - LaSalle Marked-up Emergency Plan EP-AA-1000 Pages ML18053A1762018-01-31031 January 2018 Attachment 5B - LaSalle Clean Emergency Plan EP-AA-1000 Pages ML18053A1842018-01-31031 January 2018 Enclosure 5 - LaSalle - Evaluation of Proposed Changes RS-18-009, License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-01-24024 January 2018 License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System RS-17-127, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-12-13013 December 2017 Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process RS-16-225, Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review2016-11-0808 November 2016 Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review RS-16-191, License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-26026 October 2016 License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-198, Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods2016-09-30030 September 2016 Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16036A3482016-02-0505 February 2016 Maintenance of Draft Supplemental Environmental Impact Statement at the Seneca Public Library in Regards to the Review of the LaSalle County Station License Renewal Application (TAC Nos. MF5567 and MF5568) RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings RS-15-305, Corrections to the License Renewal Application Dated December 9, 20142015-12-0202 December 2015 Corrections to the License Renewal Application Dated December 9, 2014 RS-15-279, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2015-11-19019 November 2015 Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application2015-08-0606 August 2015 Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application RS-15-221, Revisions to License Renewal Application, Applicant'S Environmental Report - Operating License Renewal Stage2015-07-31031 July 2015 Revisions to License Renewal Application, Applicant'S Environmental Report - Operating License Renewal Stage 2023-05-25
[Table view] Category:Technical Specification
MONTHYEARRS-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 ML22332A4512022-11-10010 November 2022 Attachment 3 - Markup of Technical Specification Bases Pages (for Information Only) 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 ML22111A2572022-04-13013 April 2022 Technical Specification Bases RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-087, Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink2020-07-17017 July 2020 Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-20-029, Technical Specification Bases2020-04-13013 April 2020 Technical Specification Bases RS-20-009, Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-01-31031 January 2020 Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-18-028, License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator2018-04-19019 April 2018 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator RS-18-044, Revised Technical Specification Bases2018-04-11011 April 2018 Revised Technical Specification Bases RS-18-009, License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-01-24024 January 2018 License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System RS-16-191, License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-26026 October 2016 License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-080, Updated Final Safety Analysis Report (Ufsar), Revision 22, Technical Specification Bases2016-04-11011 April 2016 Updated Final Safety Analysis Report (Ufsar), Revision 22, Technical Specification Bases RS-15-002, License Amendment Request to Revise Technical Specifications Sections 3.5.1, ECCS - Operating2015-01-12012 January 2015 License Amendment Request to Revise Technical Specifications Sections 3.5.1, ECCS - Operating RS-14-322, License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of.2014-12-22022 December 2014 License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of. RS-14-192, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process RS-12-184, Request to Revise Technical Specification 2.1.1.2 for Minimum Critical Power Ratio Safety Limit - Cycle 152012-10-11011 October 2012 Request to Revise Technical Specification 2.1.1.2 for Minimum Critical Power Ratio Safety Limit - Cycle 15 RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0404 April 2011 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-02-22022 February 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. ML1003213072010-01-27027 January 2010 Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages RS-10-001, LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages2010-01-27027 January 2010 LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages RS-08-132, LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 52008-10-23023 October 2008 LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5 RS-08-132, Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 52008-10-23023 October 2008 Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I2008-06-0909 June 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im RS-08-045, Technical Specification Bases2008-04-14014 April 2008 Technical Specification Bases RS-07-165, License Amendment Request Regarding Spent Fuel Storage Pool Criticality2007-12-13013 December 2007 License Amendment Request Regarding Spent Fuel Storage Pool Criticality RS-07-069, Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink2007-06-29029 June 2007 Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process RS-07-034, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection2007-04-0606 April 2007 Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection RS-06-181, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report2006-12-15015 December 2006 Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report RS-06-154, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program.2006-11-17017 November 2006 Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program. RS-06-089, Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical Power2006-08-16016 August 2006 Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical Power ML0504902692005-02-0404 February 2005 Request for Change to Technical Specifications Traversing In-core Probe (TIP) System ML0434900702004-12-10010 December 2004 Tech Spec Pages for License Amendments 170 & 156, Pressure-Temperature Limits RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-04-30030 April 2004 Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RS-03-079, Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing2003-05-19019 May 2003 Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing RS-03-031, Request for Amendment to Technical Specifications Surveillance Requirement 3.6.1.3.82003-04-18018 April 2003 Request for Amendment to Technical Specifications Surveillance Requirement 3.6.1.3.8 RS-03-040, Request for Amendment to Technical Specifications Section 5.7, High Radiation Area.2003-03-31031 March 2003 Request for Amendment to Technical Specifications Section 5.7, High Radiation Area. RS-03-029, Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation.2003-03-31031 March 2003 Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation. ML0234505702002-11-27027 November 2002 Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.2002-10-24024 October 2002 Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program. RS-02-110, Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation.2002-07-0808 July 2002 Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation. RS-02-076, Request for Amendment to Technical Specifications, Excess Flow Check Valve Testing Surveillance Requirement 3.6.1.3.8 & Relief Request RV-122002-05-31031 May 2002 Request for Amendment to Technical Specifications, Excess Flow Check Valve Testing Surveillance Requirement 3.6.1.3.8 & Relief Request RV-12 2023-05-25
[Table view] Category:Amendment
MONTHYEARRS-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-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-20-087, Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink2020-07-17017 July 2020 Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-20-009, Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-01-31031 January 2020 Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-16-191, License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-26026 October 2016 License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies RS-12-184, Request to Revise Technical Specification 2.1.1.2 for Minimum Critical Power Ratio Safety Limit - Cycle 152012-10-11011 October 2012 Request to Revise Technical Specification 2.1.1.2 for Minimum Critical Power Ratio Safety Limit - Cycle 15 RS-08-132, Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 52008-10-23023 October 2008 Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5 RS-08-132, LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 52008-10-23023 October 2008 LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I2008-06-0909 June 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im RS-07-165, License Amendment Request Regarding Spent Fuel Storage Pool Criticality2007-12-13013 December 2007 License Amendment Request Regarding Spent Fuel Storage Pool Criticality RS-07-034, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection2007-04-0606 April 2007 Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection RS-06-181, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report2006-12-15015 December 2006 Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report RS-06-154, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program.2006-11-17017 November 2006 Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program. RS-06-089, Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical Power2006-08-16016 August 2006 Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical Power ML0434900702004-12-10010 December 2004 Tech Spec Pages for License Amendments 170 & 156, Pressure-Temperature Limits RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-04-30030 April 2004 Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RS-03-079, Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing2003-05-19019 May 2003 Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing RS-03-040, Request for Amendment to Technical Specifications Section 5.7, High Radiation Area.2003-03-31031 March 2003 Request for Amendment to Technical Specifications Section 5.7, High Radiation Area. RS-03-029, Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation.2003-03-31031 March 2003 Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation. ML0234505702002-11-27027 November 2002 Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.2002-10-24024 October 2002 Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program. RS-02-110, Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation.2002-07-0808 July 2002 Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation. RS-02-076, Request for Amendment to Technical Specifications, Excess Flow Check Valve Testing Surveillance Requirement 3.6.1.3.8 & Relief Request RV-122002-05-31031 May 2002 Request for Amendment to Technical Specifications, Excess Flow Check Valve Testing Surveillance Requirement 3.6.1.3.8 & Relief Request RV-12 2023-05-25
[Table view] |
Text
Exekmn I Exelon Generation wwwexeloncorpcom Nuclear 4300 Winfield Road Warrenville, IL 60555 10 CFR 50.90 RS-03-040 March 31, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555
Subject:
LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Request for Amendment to Technical Specifications Section 5.7, "High Radiation Area" In accordance with 10 CFR 50.90, Exelon Generation Company (EGC), LLC, hereby requests the following amendment to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-11 and NPF-18. Specifically, the proposed change will modifyTS 5.7, "High Radiation Area," by incorporating the wording and requirements from NUREG- 1434, 'Standard Technical Specifications General Electric Plants, BWR/6," Revision 2, dated June 2001.
The information supporting the proposed TS change is subdivided as follows.
Attachment 1 is the notarized affidavit.
Attachment 2 provides our evaluation supporting the proposed changes.
Attachment 3 contains the copies of the marked up TS pages.
Attachment 4 provides the retyped TS pages.
The proposed TS change has been reviewed by the LaSalle County Station Plant Operations Review Committee (PORC) and approved by the Nuclear Safety Review Board (NSRB) in accordance with the Quality Assurance Program.
EGC is notifying the State of Illinois of this application for amendment by transmitting a copy of this letter and its attachments to the designated State Official.
We request approval of the proposed change by March 1, 2004 with an implementation period of 60 days.
A
March 31, 2003 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this submittal, please contact Mr. T. W. Simpkin at (630) 657-2821.
Sincerely, q4xAA Keith R. Jury Director-Licensing Mid-West Regional Operating Group Attachments: . Affidavit . Evaluation of Proposed Change . Markup of Proposed Technical Specification Page Change . Retyped Pages for Technical Specification Change cc: Regional Administrator - NRC Region IlIl NRC Project Manager- NRC NRR NRC Senior Resident Inspector - LaSalle County Station Office of Nuclear Facility Safety - Illinois Department of Nuclear Safety
ATTACHMENT I Affidavit STATE OF ILLINOIS )
COUNTY OF DUPAGE )
IN THE MATTER OF: )
EXELON GENERATION COMPANY (EGC), LLC ) Docket Numbers LASALLE COUNTY STATION - UNIT I and UNIT 2 ) 50-373 and 50-374
SUBJECT:
Request for Amendment to Technical Specifications Section 5.7, "High Radiation Area" AFFIDAVIT I affirm that the content of this transmittal is true and correct to the best of my knowledge, information, and belief.
q/?9.
T. W. S pkin Manager-Licensing Mid-West Regional Operating Group Subscribed and sworn to before me, a Notary Public in and for the State above named, this 3 I day of LI) 1A . , 2003 Notary Public OFFICIAL SEAL ANESE L.GRIGSBY NOTARY PUBLIC, STATE OF ILLWNOIS
" " rOMMISSION EXPIRES 3 13-2005
ATTACHMENT 2 Evaluation of Proposed Changes Page 1 of 10
1.0 INTRODUCTION
2.0 DESCRIPTION
OF PROPOSED AMENDMENT
3.0 BACKGROUND
4.0 REGULATORY REQUIREMENTS & GUIDANCE
5.0 TECHNICAL ANALYSIS
6.0 REGULATORY ANALYSIS
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION (NSHC)
8.0 ENVIRONMENTAL CONSIDERATION
9.0 PRECEDENT
ATTACHMENT 2 Evaluation of Proposed Changes Page 2 of 10
1.0 INTRODUCTION
In accordance with 10 CFR 50.90, Exelon Generation Company (EGC), LLC, hereby requests the following amendment to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-1 1 and NPF-1 8. Specifically, the proposed change will modify TS 5.7, "High Radiation Area," by incorporating the corresponding wording and requirements from NUREG- 1434, "Standard Technical Specifications General Electric Plants, BWRI6," Revision 2, dated June 2001.
2.0 DESCRIPTION
OF PROPOSED AMENDMENT The proposed changes will replace the current LaSalle County Station (LSCS) TS 5.7 with the corresponding wording and requirements from NUREG- 1434, Revision 2. The marked up and retyped TS pages are contained in Attachments 3 and 4.
3.0 BACKGROUND
TS 5.7 describe the LSCS program to control access to areas within the plant that have radiation levels that exceed 100 millirem per hour (mrem/hr). The current TS 5.7.1 and TS 5.7.3 describe the requirements for access into high radiation areas that have radiation levels that exceed 100 mrem/hr but are less than or equal to 1000 mrem/hr.
The current TS 5.7.2, 5.7.3 and 5.7.4 describes the requirements for access into high-high radiation areas that have radiation levels that exceed 1000 mrem/hr. For those areas where locking is not practical, current TS 5.7.2 and TS 5.7.4 both require the area to be barricaded, conspicuously posted, and have an activated flashing light.
4.0 REGULATORY REQUIREMENTS & GUIDANCE 10 CFR 50.36(c)(5), "Administrative controls.", requires that provisions relating to organization and management, procedures, recording keeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner must be included in a licensee's TS.
5.0 TECHNICAL ANALYSIS
5.1 Design Bases The proposed change incorporates corresponding wording and requirements from NUREG- 1434, into the LSCS TS. The LSCS evaluation of the proposed change concluded the following.
Both the proposed and current TS 5.7.1 describe the requirements for access into areas that have radiation levels that exceed 100 mrem/hr but are
ATTACHMENT 2 Evaluation of Proposed Changes Page 3 of 10 less than or equal to 1000 mrem/hr. The proposed and current TS 5.7.1 are considered to have equivalent level access controls as both contain the need to provide a barricade, conspicuously post the area and issue an RWP to control entrance to the area.
Proposed TS 5.7.2 and current TS 5.7.4 describe the requirements for access into areas that have radiation levels that exceed 1000 mrem/hr.
Proposed TS 5.7.2 and current TS 5.7.4 are considered to have equivalent level access controls as both require these areas to be locked. For those areas where locking is not practical, proposed TS 5.7.2 and current TS 5.7.4 both require the area to be barricaded, conspicuously posted, and have an activated flashing light.
The proposed change includes the deletion of the use of computer controlled doors in current TS 5.7.2. This description is being removed as computer controlled doors are no longer utilized at LSCS. Rather, manual locking mechanisms are used on doors providing an equivalent level of control.
Current TS 5.7.4 also discusses "high-high" radiation areas. The term "high-high" radiation area is a legacy term that is being deleted from the proposed TS. This is an administrative change only to remove an outdated term.
Therefore, LSCS has determined that the proposed change provides an equivalent level of protection as that currently provided.
5.2 Risk Information This submittal is not based on risk informed decision making.
6.0 REGULATORY ANALYSIS
TS 5.7 describes the LSCS program to control access to areas within the plant that have radiation levels that exceed 100 mrem/hr. These administrative controls provide provisions relating to the control of radiation exposure to individuals and thus in accordance with 10 CFR 50.36(c)(5) must be included in the TS.
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION EGC has evaluated the proposed change to the TS for LaSalle County Station, Unit 1 and Unit 2, and has determined that the proposed change does not involve a significant hazards consideration and is providing the following information to support a finding of no significant hazards consideration.
ATTACHMENT 2 Evaluation of Proposed Changes Page 4 of 10 Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change will modify LaSalle County Station (LSCS) Technical Specification (TS) 5.7, "High Radiation Area," by incorporating into the TS the corresponding wording and requirements from NUREG- 1434, "Standard Technical Specifications General Electric Plants, BWRI6," Revision 2, dated June 2001. TS 5.7 establishes the administrative controls on entry into high radiation areas. High radiation area administrative controls are not a precursor to accidents previously evaluated. Thus, the proposed change does not have any affect on the probability of an accident previously evaluated.
The proposed change in administrative controls on entry into a radiation area does not affect the ability of LSCS to successfully respond to previously evaluated accidents and does not affect radiological assumptions used in the evaluations. Thus, the radiological consequences of any accident previously evaluated are not increased.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change does not affect the control parameters governing unit operation or the response of plant equipment to transient conditions. The proposed change does not introduce any new equipment, modes of system operation or failure mechanisms.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Does the change involve a significant reduction in a margin of safety?
Response: No The proposed change incorporates corresponding wording and requirements from NUREG- 1434, into the LSCS TS. The LSCS evaluation of the proposed change concluded the following.
Both the proposed and current TS 5.7.1 describe the requirements for
ATTACHMENT 2 Evaluation of Proposed Changes Page 5 of 10 access into areas that have radiation levels that exceed 100 mrem/hr but are less than or equal to 1000 mrem/hr. The proposed and current TS 5.7.1 are considered to have equivalent level access controls as both contain the need to provide a barricade, conspicuously post the area and issue an RWP to control entrance to the area.
Proposed TS 5.7.2 and current TS 5.7.4 describe the requirements for access into areas that have radiation levels that exceed 1000 mrem/hr.
Proposed TS 5.7.2 and current TS 5.7.4 are considered to have equivalent level access controls as both require these areas to be locked. For those areas where locking is not practical, proposed TS 5.7.2 and current TS 5.7.4 both require the area to be barricaded, conspicuously posted, and have an activated flashing light.
- The proposed change includes the deletion of the use of computer controlled doors in current TS 5.7.2. This description is being removed as computer controlled doors are no longer utilized at LSCS. Rather, manual locking mechanisms are used on doors providing an equivalent level of control.
- Current TS 5.7.4 also discusses "high-high" radiation areas. The term "high-high" radiation area is a legacy term that is being deleted from the proposed TS. This is an administrative change only to remove an outdated term.
Therefore, LSCS has determined that the proposed change provides an equivalent level of protection as that currently provided.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based upon the above, EGC concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
8.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
ATTACHMENT 2 Evaluation of Proposed Changes Page 6 of 10 9.0 PRECEDENT The proposed amendment incorporates into the LSCS a change that is specific to LSCS to incorporate the wording and intent of NUREG-1434, Rev. 2, into TS 5.7, and therefore, this proposed amendment does not rely upon the issuance of amendments to other licensees.
ATTACHMENT 3 MARKUP OF PROPOSED TECHNICAL SPECIFICATION PAGE CHANGE Revised TS Pages
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7 Pursuant to 10 CFR 20, paragraph 20.1601(c). in lieu of the requirements of 10 CFR 20.1601, each high radiation area, s defined in 10 CFR 20, in which the intensity of radiatio s
> 100 mrem/hr but < 1000 mrem/hr, shall be barricaded ad onspicuously posted as a high radiation area and entr nce thereto sall be controlled by requiring issuance of a Radia ion Work Pe it (RWP). Individuals qualified in radiation otection proc dures or personnel continuously escorted by ch individuals may b exempt from the RWP issuance requirement uring the perform nce of their assigned duties in high r iation areas with exposure ates > 100 mrem/hr and < 1000 mrem/r, provided they are otherwise ollowing plant radiation protecti n procedures for entry into ch high radiation areas.
Any individual r group of individuals rmitted to enter such areas shall be p vided with or accomp nied by one or more of the following:
- a. A radiation mon oring devic that continuously indicates the radiation dos rate in e area.
- b. A radiation monito ri d ice that continuously integrates the radiation dose rat n the area and alarms when a preset integrated dose is re c ed. Entry into such areas with this monitoring devi ma be made after the dose rate levels in the area ave bee established and personnel are aware of them.
- c. An individual alified in radi ion protection procedures with a radiat n dose rate monito ng device, who is responsible or providing positive ontrol over the activities ithin the area and shall erform periodic radiatione urveillance at the frequenc specified by the radiatio protection manager in the RWP.
5.7.2 In additi n to the requirements of Specification 7.1 for areas accessi e to personnel with radiation levels such hat a major portio of the body could receive in one hour a dose reater than 1000 Krem, the computer shall be programmed to permit ntry thr ugh locked doors for any individual requiring acces to any su high-high radiation areas for the time that access i rtquired.
(continued)
LaSalle 1 and 2 5.7-1 Amendment No. 147/133
High Radiation Area 5.7 5.7 High Radiation Area 5.7.3 Keys to manually open computer controlled high radiation area do s and high-high radiation area doors shall be maintained der the ministrative control of the shift manager on duty or e radiat protection manager.
5.7.4 High-high rad tion areas, as defined in Specifica on 5.7.2, not equipped with t computerized card readers sha be maintained in accordance with 1 FR 20.1601(a)(3). locked cept during periods when access to the a a is required with pO tive control over each individual entry, r in the case of high radiation area established for a period f 30 days or ess, direct surveillance to prevent unauthorized ent may b ubstituted. Doors shall remain locked except during p io of access by personnel under an approved RWP which shall spe fy the dose rate levels in the immediate work area and the im allowable stay time for individuals in that area. Mor div ual areas accessible to personnel with radiation evels such t t a major portion of the body could receive in ne hour a dose in cess of 1000 mrem that are located within rge areas, such as the ontainment, where no enclosure exists r purposes of locking, and o enclosure can be reasonably con ructed around the individual ar s, then that area shall be rop off, conspicuously posted and a fla ing light shall be a vated as a warning device. In lieu of e stay time specifi ion of the RWP, direct or remote, such as us of closed circuj TV cameras, continuous surveillance may be made per nnel qualified in radiation protection procedures to p vide sitive exposure control over the activities within the area.
LaSalle 1 and 2 5.7-2 Amendment No. 147/133
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 20, the following controls As provided in paragraph 20.1601(c) of 10 CFR Part the controls required by shall be applied to high radiation areas in place of paragraph 20.1601(a) and (b) of 10 CFR Part 20:
1.0 rem/hour 5.7.1 High Radiation Areas with Dose Rates Not Exceedinc Source or from any Surface at 30 Centimeters from the Radiation Penetrated by the Radiation
- a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such or exit barricades may be opened as necessary to permit entry of personnel or equipment.
- b. Access to, and activities in, each such area shall be or controlled by means of Radiation Work Permit (RWP) dose equivalent that includes specification of radiation rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
and
- c. Individuals qualified in radiation protection procedures be personnel continuously escorted by such individuals may while exempted from the requirement for an RWP or equivalent provided that they are performing their assigned duties for otherwise following plant radiation protection procedures entry to, exit from, and work in such areas.
possess:
- d. Each individual or group entering such an area shall displays
- 1. A radiation monitoring device that continuously radiation dose rates in the area; or
- 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
- 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued) anal ItICo1 -L{
ILCJaG 5.7-1 Amendment No.
L--
Area High Radiation High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)
- 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure with the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
- e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates In the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation. but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation
- a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked (continued)
LaSalle 1 and 2 5.7- 2 Amendment No.
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation. but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued) or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
- 1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.
- 2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
- b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d. Each individual or group entering such an area shall possess one of the following:
- 1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
- 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (continued)
LaSalle 1 and 2 5.7 -3 Amendment No.
It High Radiation Area 5.7 5.7 High Radiation Area High Radiation Areas with Dose Rates Greater from than 1.0 rem/hour at 5.7.2 or anY Surface 30 Centimeters from the Radiation Source 500 rads/hour at 1 Penetrated by the Radiation. but less than any Surface Penetrated by Meter from the Radiation Source or from the Radiation (continued) ionization chamber
- 3. A self-reading dosimeter (e.g., pocket or electronic dosimeter) and, in the RWP or (i) Be under the surveillance, as specified individual equivalent, while in the area, of an equipped qualified in radiation protection procedures, continuously with a radiation monitoring device that rates in the area; who is displays radiation dose within responsible for controlling personnel exposure the area, or in the RWP or (ii) Be under the surveillance, as specified of closed equivalent, while in the area, by means in circuit television, of personnel qualified for radiation protection procedures, responsible the area, in controlling personnel radiation exposure and control and with the means to communicate with every individual in the area.
(3), above, are
- 4. In those cases where options (2) and with the "As impractical or determined to be inconsistent a radiation Low As is Reasonably Achievable" principle, radiation monitoring device that continuously displays dose rates in the area.
radiation protection
- e. Except for individuals qualified in escorted by such procedures, or personnel continuously be made only after individuals, entry into such areas shall and entry dose rates in the area have been determined These continuously personnel are knowledgeable of them.
a pre-job briefing prior to escorted personnel will receive determination, entry into such areas. This dose rate require documentation knowledge, and pre-job briefing does not prior to initial entry.
(continued) 5.7-4 Amendment No.
LaSalle 1 and 2
High Radiation Area 5.7 5.7 High Radiation Area rem/hour at 5.7.2 HiQh Radiation Areas with Dose Rates Greater than 1.0 any Surface 30 Centimeters from the Radiation Source or from but less than 500 rads/hour at 1 Penetrated by the Radiation.
Surface Penetrated bY Meter from the Radiation Source or from any the Radiation (continued) area where no
- f. Such individual areas that are within a larger no enclosure exists for the purpose of locking and where individual enclosure can reasonably be constructed around the by a locked door or gate, nor area need not be controlled continuously guarded, but shall be barricaded, conspicuously be posted, and a clearly visible flashing light shall activated at the area as a warning device.
5.7-5 Amendment No.
LaSalle 1 and 2
ATTACHMENT 4 RETYPED PAGES FOR TECHNICAL SPECIFICATION CHANGE
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:
5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation
- a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.
- b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d. Each individual or group entering such an area shall possess:
- 1. A radiation monitoring device that continuously displays radiation dose rates in the area; or
- 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
- 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)
LaSalle 1 and 2 5. 7- 1 Amendment No.
Area High Radiation High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)
- 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure with the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
- e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation. but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation
- a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked (continued)
LaSalle 1 and 2 5.7-2 Amendment No.
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation. but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued) or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
- 1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.
- 2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.
- b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.
- d. Each individual or group entering such an area shall possess one of the following:
- 1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
- 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or (continued)
LaSalle 1 and 2 5.7 -3 Amendment No.
Area High Radiation High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)
- 3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii)Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.
- 4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.
- e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
(continued)
LaSalle 1 and 2 5.7-4 Amendment No.
High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation. but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)
- f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.
LaSalle 1 and 2 5.7-5 Amendment No.