Similar Documents at Salem |
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Category:Letter type:LR
MONTHYEARLR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022 Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022 Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095) LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022 Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022 Spent Fuel Cask Registration LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022 Spent Fuel Cask Registration LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0022, Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds2022-03-21021 March 2022 Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0013, In-Service Inspection Activities - 90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0061, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2021-12-0909 December 2021 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2021-11-10010 November 2021 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations 2023-09-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARLR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report ML22061A0302022-04-0404 April 2022 Issuance of Amendment Nos. 343 and 324 Revise Technical Specifications Surveillance Requirements for Auxiliary Feedwater ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments ML21230A0182021-10-0808 October 2021 Issuance of Amendment No. 339 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report LR-N21-0065, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-09-29029 September 2021 License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0048, One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators2021-06-18018 June 2021 One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators LR-N21-0043, Supplement to License Amendment Request to Adopt TSTF-490, Delete Ebar Definition and Revision to RCS Specific Activity Tech Spec2021-06-0909 June 2021 Supplement to License Amendment Request to Adopt TSTF-490, Delete Ebar Definition and Revision to RCS Specific Activity Tech Spec 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 LR-N21-0026, Supplement to License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System2021-03-17017 March 2021 Supplement to License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments LR-N21-0006, Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions2021-02-16016 February 2021 Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions LR-N20-0003, License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec2020-09-17017 September 2020 License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec LR-N20-0027, Supplement to License Amendment Request: Revise Minimum Required Channels, Mode Applicability and Actions for the Source Range and Intermediate Range Neutron Flux Reactor Trip System Instrumentation Technical Specifications2020-05-11011 May 2020 Supplement to License Amendment Request: Revise Minimum Required Channels, Mode Applicability and Actions for the Source Range and Intermediate Range Neutron Flux Reactor Trip System Instrumentation Technical Specifications LR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2020-04-24024 April 2020 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology LR-N19-0055, License Amendment Request: Revise Minimum Required Channels, Mode Applicability and Actions for the Source Range and Intermediate Range Neutron Flux Reactor Trip System Instrumentation Technical Specifications2019-10-23023 October 2019 License Amendment Request: Revise Minimum Required Channels, Mode Applicability and Actions for the Source Range and Intermediate Range Neutron Flux Reactor Trip System Instrumentation Technical Specifications LR-N19-0064, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer2019-07-29029 July 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer LR-N19-0065, License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements2019-07-0808 July 2019 License Amendment Request for Approval of Changes to Emergency Plan Staffing Requirements LR-N19-0006, Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-04-0808 April 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program LR-N18-0129, License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements.2019-02-0404 February 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements. LR-N18-0116, Response to Request for Additional Information, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension2018-10-30030 October 2018 Response to Request for Additional Information, License Amendment Request: Inverter Allowed Outage Time (AOT) Extension LR-N18-0113, Supplement to License Amendment Request: Revise Reactor Trip System Instrumentation, Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves and Add Main Feedwater Isolation Technical Specification2018-10-27027 October 2018 Supplement to License Amendment Request: Revise Reactor Trip System Instrumentation, Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves and Add Main Feedwater Isolation Technical Specification LR-N18-0059, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2018-06-29029 June 2018 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules LR-N18-0038, License Amendment Request (LAR) to Amend the Salem Technical Specifications (TS) to Extend the Refueling Water Storage Tank (RWST) Allowed Outage Time2018-06-29029 June 2018 License Amendment Request (LAR) to Amend the Salem Technical Specifications (TS) to Extend the Refueling Water Storage Tank (RWST) Allowed Outage Time LR-N17-0144, License Amendment Request: Revise Reactor Trip System Instrumentation, Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves and Add Main Feedwater Isolation Technical Specification2018-06-29029 June 2018 License Amendment Request: Revise Reactor Trip System Instrumentation, Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves and Add Main Feedwater Isolation Technical Specification LR-N18-0067, Supplement to License Amendment Request for Vital Instrument Bus Inverter Allowed Outage Time (AOT) Extension2018-06-14014 June 2018 Supplement to License Amendment Request for Vital Instrument Bus Inverter Allowed Outage Time (AOT) Extension ML18136A8662018-05-16016 May 2018 License Amendment Request: Vital Instrument Bus Inverter Allowed Outage Time (AOT) Extension LR-N18-0022, License Amendment Request to Revise Technical Specification Actions for Rod Position Indicators2018-02-0808 February 2018 License Amendment Request to Revise Technical Specification Actions for Rod Position Indicators LR-N17-0135, License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times2017-12-18018 December 2017 License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times LR-N17-0121, License Amendment Request to Relocate the Reactor Coolant System Pressure Isolation Valve Table from the Technical Specifications to the Technical Requirements Manual2017-09-27027 September 2017 License Amendment Request to Relocate the Reactor Coolant System Pressure Isolation Valve Table from the Technical Specifications to the Technical Requirements Manual LR-N17-0058, License Amendment Request to Revise the Implementation Period for License Amendment No. 2942017-03-13013 March 2017 License Amendment Request to Revise the Implementation Period for License Amendment No. 294 LR-N16-0173, License Amendment Request: Containment Fan Cooler Unit (Cfcu) Allowed Outage Time (AOT) Extension2017-03-0606 March 2017 License Amendment Request: Containment Fan Cooler Unit (Cfcu) Allowed Outage Time (AOT) Extension LR-N16-0003, License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications2016-11-17017 November 2016 License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications LR-N16-0175, License Amendment Request - Administrative Controls2016-10-17017 October 2016 License Amendment Request - Administrative Controls LR-N16-0114, License Amendment Request 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 Using the Consolidated Line .2016-08-30030 August 2016 License Amendment Request 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 Using the Consolidated Line . LR-N16-0093, License Amendment Request to Extend the Implementation Period for Salem, Unit 1 License Amendment No. 311 and Salem, Unit 2 License Amendment No. 2922016-05-10010 May 2016 License Amendment Request to Extend the Implementation Period for Salem, Unit 1 License Amendment No. 311 and Salem, Unit 2 License Amendment No. 292 LR-N16-0057, Supplement for License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems2016-03-0404 March 2016 Supplement for License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems LR-N16-0044, Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel2016-02-11011 February 2016 Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel LR-N16-0015, Supplemental Information for License Amendment to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation2016-02-0303 February 2016 Supplemental Information for License Amendment to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation LR-N15-0084, License Amendment Request Modifying Chilled Water System Requirements2015-09-11011 September 2015 License Amendment Request Modifying Chilled Water System Requirements LR-N15-0189, Supplemental Information Needed for Review of Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve Position Indication Instrumentation from Accident Monitoring Instrumentation Technical Specifications2015-09-0202 September 2015 Supplemental Information Needed for Review of Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve Position Indication Instrumentation from Accident Monitoring Instrumentation Technical Specifications LR-N15-0187, Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications2015-08-31031 August 2015 Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications LR-N15-0021, License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems2015-04-0303 April 2015 License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems 2023-09-08
[Table view] Category:Technical Specification
MONTHYEARLR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML22270A3172022-09-27027 September 2022 Submittal of Technical Specification Bases Changes, Amendment No. 201 LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 2152022-09-27027 September 2022 Submittal of Technical Specification Bases Changes, Amendment No. 215 LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0048, One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators2021-06-18018 June 2021 One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators LR-N21-0045, Submittal of Changes to Technical Specifications Bases2021-06-16016 June 2021 Submittal of Changes to Technical Specifications Bases LR-N21-0006, Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions2021-02-16016 February 2021 Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report2020-12-0606 December 2020 License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report LR-N20-0003, License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec2020-09-17017 September 2020 License Amendment Request to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML17157B2652017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Repor LR-N17-0088, Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Re2017-05-0909 May 2017 Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and Pseg Nuclear LLC Quality Assurance Topical Repor LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 852017-01-30030 January 2017 Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85 ML17046A2292017-01-30030 January 2017 Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85 LR-N16-0003, License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications2016-11-17017 November 2016 License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications LR-N16-0114, License Amendment Request 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 Using the Consolidated Line .2016-08-30030 August 2016 License Amendment Request 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 Using the Consolidated Line . LR-N15-0187, Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications2015-08-31031 August 2015 Emergency License Amendment Request to Remove Pressurizer Power Operated Relief Valve (PORV) Position Indication Instrumentation from the Accident Monitoring Instrumentation Technical Specifications LR-N15-0021, License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems2015-04-0303 April 2015 License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation2015-03-27027 March 2015 License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation ML14210A4842014-07-28028 July 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Using the Consolidated Line Item Improvement Process ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N11-0056, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2011-02-23023 February 2011 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program LR-N10-0355, Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix2010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)2010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100503982010-10-14014 October 2010 Attachment 3 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Comparison Matrix LR-N10-0355, Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance2010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance ML1100504152010-10-14014 October 2010 Hope Creek, CY-AA-170-500, Revision 0, Meteorological Monitoring System Calibration and Maintenance LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)2010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) LR-N10-0355, Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index)2010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) ML1100503992010-10-14014 October 2010 Attachment 4 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Supporting Documents (Cd with Paper Index) ML1100503752010-10-14014 October 2010 Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version) ML1100504022010-10-14014 October 2010 Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version) ML1025802412010-09-0808 September 2010 License Amendment Request S10-01 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program ML1100505182010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction LR-N10-0355, Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction2010-08-24024 August 2010 Hope Creek, HC.OP-AB.ZZ-0150(Q), Rev. 6, 125VDC System Malfunction LR-N10-0355, Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment2010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment ML1100505002010-07-13013 July 2010 Hope Creek, HC.OP-AB.HVAC-0002(Q), Rev. 7, Control Room Environment LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling2010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling ML1100505162010-06-24024 June 2010 Hope Creek, HC.OP-AB.RPV-0009(Q), Rev. 7, Shutdown Cooling LR-N10-0355, Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment2010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment ML1100504772010-05-0303 May 2010 Hope Creek, HC.OP-AB.CONT-0002(Q), Rev. 9, Containment LR-N10-0355, Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations2010-04-21021 April 2010 Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations ML1100505052010-04-21021 April 2010 Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer2010-04-21021 April 2010 Hope Creek, HC.OP-AB.MISC-0002(Q), Rev. 10, Crids/Overhead Annunciators/Ppc Computer ML1100505062010-04-21021 April 2010 Hope Creek, HC.OP-AB.RPV-0003(Q), Rev. 21, Recirculation System/Power Oscillations LR-N10-0355, Hope Creek, Offsite Dose Calculation Manual, Revision 252010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504172010-04-16016 April 2010 Hope Creek, Offsite Dose Calculation Manual, Revision 25 ML1100504742010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup2010-03-17017 March 2010 Hope Creek, HC.IC-GP.BB-0003(Q) - Rev. 17, Nuclear Boiler - Nondivisional Channel L-11683/B21-N027 Rx Cavity Flood Up Level/Rx Shutdown Range Level Setup LR-N10-0355, Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature2010-03-0505 March 2010 Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature ML1100505022010-03-0505 March 2010 Hope Creek, HC.OP-AB.MISC-0001(Q), Rev. 15, Acts of Nature 2023-06-23
[Table view] Category:Amendment
MONTHYEARLR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N21-0048, One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators2021-06-18018 June 2021 One-Time License Amendment Request to Revise Unit 2 Technical Specification Action for Rod Position Indicators LR-N21-0006, Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions2021-02-16016 February 2021 Application to Revise Technical Specifications to Adopt TSTF-569 Revision of Response Time Testing Definitions LR-N20-0072, License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report2020-12-0606 December 2020 License Amendment Request to Amend Tech Specs to Revise and Relocate the Reactor Coolant System Pressure & Temperature Limits & Pressurizer Overpressure Protection System Limits to a Pressure & Temperature Limits Report LR-N15-0020, License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation2015-03-27027 March 2015 License Amendment Request to Revise Technical Specification 3/4.3.1, Reactor Trip System Instrumentation ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan LR-N09-0034, License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications2009-04-0909 April 2009 License Amendment Request to Relocate Communications, Manipulator Crane, and Crane Travel Requirements from Technical Specifications LR-N08-0046, Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-012008-03-11011 March 2008 Request for Changes to Technical Specifications Refueling Operations - Decay Time, License Amendment Request (LAR) S08-01 ML0715901852007-06-0606 June 2007 Units, 1 and 2, Tech Spec Pages for Amendment 265 Relocation of Technical Specification Requirements for the Movable Incore Detectors and Radioactive Gaseous Effluent Oxygen Monitoring Instrumentation LR-N07-0030, License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System2007-03-16016 March 2007 License Change Request S06-010, Steam Generator Feedwater Pump Trip, Feedwater Isolation Valve Response Time Testing and Containment Cooling System ML0701900942007-01-11011 January 2007 License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement LR-N06-0201, Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process2006-06-0707 June 2006 Request for Change to Technical Specifications to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Analyzers Using the Consolidated Line Item Improvement Process LR-N06-0055, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requiremen2006-04-0606 April 2006 Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requirements ML0601300252006-01-11011 January 2006 Technical Specifications Deletion of Reactor Coolant System Volume ML0525600402005-09-0909 September 2005 Units, 1 and 2 - Tech Spec Pages for Amendments 265 and 247 to Extend the Inspection Interval for Reactor Coolant Pump Flywheels LR-N05-0377, Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling System2005-08-11011 August 2005 Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling System LR-N05-0018, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational.2005-02-23023 February 2005 Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program, & Steam Generator Tube Inspection Report & to Revise Reactor Coolant System Operational. LR-N04-0021, Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis Report2004-04-26026 April 2004 Units I and 2 - Implementation of Alternative Source Term (AST) Request for Changes to Technical Specifications and Updated Final Safety Analysis Report ML0400804432004-01-0707 January 2004 Tech Spec Pages for License Amendment, Request for Changes to License Condition 2.C.(10) LR-N03-0092, Request for Change to TSs Explosive Gas Mixture2003-06-0606 June 2003 Request for Change to TSs Explosive Gas Mixture LR-N03-0022, Revision to Request for Change to Technical Specifications2003-02-14014 February 2003 Revision to Request for Change to Technical Specifications LR-N03-0014, Request for Change to Technical Specifications Administrative and Editorial Changes2003-01-29029 January 2003 Request for Change to Technical Specifications Administrative and Editorial Changes LR-N02-0344, Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area.2002-10-23023 October 2002 Request for Change to Technical Specifications Revise Section 6.12, High Radiation Area. ML0200702422002-01-0404 January 2002 TS Pages to Amendment 249 & 229 Change to Technical Specifications 28 Volt D.C. Distribution 2023-06-23
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bndge, New Jersey 08038-0236 0 PSEG OCT 2 3 2002 NuclearLLC LR-N02-0344 LCR S02-013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Gentlemen:
REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS REVISE SECTION 6.12, "HIGH RADIATION AREA" SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Pursuant to 10 CFR 50.90, PSEG Nuclear LLC (PSEG) hereby requests a revision to the Technical Specifications (TS) for Salem Generating Station Units 1 & 2. In accordance with 10CFR50.91 (b)(1), a copy of this submittal has been sent to the State of New Jersey.
The proposed change to the TS updates the reference to 10CFR20.203 with the corresponding reference to 10CFR20.1601 in conformance with NUREG-1 431.
PSEG Nuclear LLC has evaluated the proposed changes in accordance with IOCFR50.91(a)(1), using the criteria in 10CFR50.92(c) and has determined that this request involves no significant hazards considerations. An evaluation of the requested changes is provided in Attachment I to this letter. In addition, there is no significant increase in the amounts or types of any effluents that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure. Consequently, the proposed amendment satisfies the criteria of 10CFR51.22 (c)(9) for categorical exclusion from the requirement for an environmental assessment. The marked up Technical Specification pages affected by the proposed changes are provided in .
95-2168 REV 7/99
Document Control Desk OCT 2 3 2002 LCR H02-013 LR-N02-0344 Approva! of this proposed change is being requested by April 2003.
If you have any questions or require additional information, please contact Mr.
Michael Mosier at (856) 339-5434.
1declare under penalty of perjury that the foregoing is true and correct.
Executed on DO Sincerely D. Garc iow Vice Pre 'ident-Operations Attachments (2) 2
Document Control Desk OCT 2 3 2002 LCR H02-013 LR-N02-0344 C: Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Fretz, Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 8B2 Washington, DC 20555 USNRC Senior Resident Inspector - Salem (X24)
Mr. K.Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625 3
Document Control Desk LR-N02-0344 Attachment I LCR S02-013 SALEM GENERATING STATION UNITS I AND 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 EVALUATION OF REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)
TO REVISE SECTION 6.12, "HIGH RADIATION AREA"
- 1. DESCRIPTIO N.................................................................. 2
- 2. PROPOSED CHANGE ...................................................... 2
- 3. BACKGROUND ............................................................... 2
- 4. TECHNICAL ANALYSIS .................................................... 3
- 5. REGULATORY SAFETY ANALYSIS .................................... 3 5.1 No Significant Hazards Consideration ....................... 3 5.2 Applicable Regulatory Requirements/Criteria ........... 4
- 6. ENVIRONMENTAL IMPACT EVALUATION ................................. 5
- 7. REFERENCES .................................................................. 5 1
Document Control Desk LR-N02-0344 Attachment I LCR S02-013 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS TO REVISE SECTION 6.12, "HIGH RADIATION AREA"
- 1. DESCRIPTION The proposed change to the Technical Specifications (TS) updates the reference to 10CFR20.203 with the corresponding reference to 10CFR20.1601 in conformance with NUREG-1431 (reference 7.1). The new 10 CFR Part 20 (reference 7.2) requirements became effective on June 20, 1991. Public Service Electric & Gas (PSEG) had previously elected not to convert to the new requirements since the existing requirements were retained in the Code of Federal Regulations and the associated TS requirements were determined to be more restrictive (reference 7.3). The proposed changes will be incorporated to maintain consistency between Hope Creek Generation Station and Salem Units 1 & 2 Administrative Controls TS.
- 2. PROPOSED CHANGE The proposed Technical Specification change will revise Salem Technical Specification 6.12, "High Radiation Area" to be consistent with the Standard Technical Specifications Westinghouse Plants (NUREG-1431 Rev.2). In order to accommodate the additional material provided by this change two pages will be added to the section. These pages have been numbered 27a and 27b so as not to cause any change to the balance of the section.
- 3. BACKGROUND On August 24, 2000 the NRC issued amendment 234 for Salem Unit I and 215 for Salem Unit 2. This amendment revised the TS by relocating the procedural details of the Radiological Effluent Technical Specifications (RETS) to the Offsite Dose Calculation Manual. The TS were also revised to relocate the procedural details associated with solid radioactive wastes to the Process Control Program. In addition, the Administrative Controls section was revised to incorporate programmatic controls for radioactive effluents and environmental monitoring. These changes are consistent with the guidance provided in Generic Letter (GL) 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (RETS) in the Administrative Controls Section of the Technical Specifications and the Relocation of the Procedural Details of RETS to the Offsite Dose Control Manual or to the Process Control Program."
The proposed change is similar to that approved on September 11, 2002 for Nine Mile Point Unit 1, Amendment 176, TAC No. MB2442.
2
Document Control Desk LR-N02-0344 Attachment I LCR S02-013
- 4. TECHNICAL ANALYSIS TS 6.12 provides high radiation access control alternatives pursuant to 10 CFR20.203 (c)(2) (to be revised to 10CFR20.1601 (c)). This specification has been significantly revised as a result of the changes to 10CFR20, the guidance provided in Regulatory Guide 8.38, "Control of Access to Radiation and Very High Radiation Areas in Nuclear Power Plants," and current industry technology in controlling access to high radiation areas. The proposed changes include capping dose rate to differentiate a high radiation area from a very high radiation area, additional requirements for groups entering high radiation areas, and clarification of the need for communication with, and control of, workers in high radiation areas. These alternate controls relate to the protection of plant personnel from radiation hazards during normal plant operations. As such, the proposed changes have no impact on protection of the public from the consequences of any DBA or transient. The changes are consistent with NUREG- 1431 (reference 7.1) and provide acceptable alternate methods for controlling access to high radiation areas.
- 5. REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration PSEG Nuclear LLC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10CFR50.92, "Issuance of amendment," as discussed below:
- 1. The proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes do not affect accident initiators or precursors and do not alter the design assumptions, conditions, configuration of the facility, or manner in which the plant is operated. The proposed changes do not alter or prevent the ability of structures, systems, or components to perform their intended safety function to mitigate the consequences of an initiating event within the acceptance limits assumed in the UFSAR. The proposed changes are administrative in nature. Technical Specification (TS) 6.12 will be updated to include the new 10CFR20 (effective 06/20/91) requirements. The proposed changes do not alter the conditions or assumptions in any of the previous accident analyses, and as a result, the radiological consequences associated with these analyses remain unchanged.
Therefore, the proposed changes will not involve a significant increase in the probability or consequences of an accident previously evaluated.
3
Document Control Desk LR-N02-0344 Attachment I LCR S02-013
- 2. The proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes do not alter the design assumptions, conditions, configuration of the facility, or the manner in which the plant is operated.
The proposed changes are administrative in nature and the relocated procedural details do not change the level of programmatic controls and procedural details. Accordingly, the proposed changes do not create any new failure modes or limiting single failures associated with a plant structure, system, or component important to safety. Also, there will be no change in the types or increase in the amounts of any effluents released offsite.
Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. The proposed amendment would not involve a significant reduction in the margin of safety.
The proposed changes do not impact equipment design or operation, nor do the changes affect any TS safety limits or safety system settings that could adversely affect plant safety. The proposed changes are administrative in nature. Technical Specification (TS) 6.12 will be updated to include the new 10CFR20 requirements (effective 06/20/91) and are in conformance with NUREG-1431. Furthermore, the proposed changes do not result in a change in the types or an increase in the amounts of any effluents released offsite.
Therefore, it is concluded that the proposed changes do not involve a significant reduction in a margin of safety.
5.2.Applicable Regulatory RequirementslCriteria PSEG has determined that the proposed changes to the TS are in compliance with the following regulatory criteria.
5.2.1 NUREG-1431, Revision 2, April 2001, "Standard Technical Specifications, Westinghouse Plants" 5.2.2 Title 10 Code of Federal Regulations, Part 20, "Standards for Protection Against Radiation" 5.2.3 Regulatory Guide 8.38, "Control of Access to High and Very High Radiation Areas in Nuclear Power Plants" In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
4
Document Control Desk LR-N02-0344 Attachment I LCR S02-013
- 6. ENVIRONMENTAL IMPACT EVALUATION PSEG 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.
- 7. REFERENCES 7.1. NUREG-1431, Revision 2, April 2001, "Standard Technical Specifications, Westinghouse Electric Plants" 7.2.1 0CFR Part 20, "Standards for Protection Against Radiation" 7.3. Regulatory Guide 8.38, "Control of Access to High and Very High Radiation Areas in Nuclear Power Plants" 7.4. LCR S99-19, January 24, 2000, "Radioactive Effluent Technical Specifications 5
Document Control Desk LRN-02-0344 LCR S02-013 SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 REVISIONS TO THE TECHNICAL SPECIFICATIONS TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License DPR-70 are affected by this change request:
Technical Specification Page Section 6.12 6-27 6-27a added 6-27b added 6-28 The following Technical Specifications for Facility Operating License DPR-75 are affected by this change request:
Technical Specification Page Section 6.12 6-27 6-27a added 6-27b added 6-28 1
D ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In [lieu of th cont ol device" o "alarm s'nl eq db paragra 20.203 )(2) of CFR Part 2 , each hi radiation area in w ich the in nsity o radiatio is greater han 100 m em/hr* but ess than 000 mrem r shall e barric ed and cons icuously sted as a igh Radi ion Area and ntrane heretos 11 be cont lled by i suance of Radiatio Exposure Pe it'. y indivi ual or gro of indiv' uals perm ted to e er such eas sha be prov ed with or ccompante by one o more of t e following a A radia on monitor' g device ich cont' uously in icates the radia 'on dose rat in the ar a.
- b. A diaton mon toring devce which ontinuousl integrate teradiatio ose rate the are and alarm when a pr et ntegrated d se is rece& ed. Ent into suc areas wit this monitoring evice may e made a er the do rate 1ev in the area/
has been stablished nd perso el have b en made kn ledgeable of them.
- c. A he th physics qualifie individua (i.e., qu ified in ra 'ation prot tion pro dures) wi a raadiaqt n dose rate m itoring de ice who i responsib e for prov ding positive control ver the ac vities w .hin the a a and sha perform per' dic radiation rveillan eat the f equency sp if ied by the adiation Work Pe t.
6; .2 In add* ion to th requirem ts of 6.12 ,areas acc sible to p sonnel wi radiatio levels* s ch that a m 'or portion fthe body c uld eceive in e hour a se great than 1000 rem shall b provided wi locked do s to preve t unautho zed entry, nd the keys shall be mai tamned under t administr ive cont 1 of the Se ior Nuclear hift Superv' or on duty a /or Senior Superviso - Radiatio Protection. Doors shall emain lock except du nygtperio of access y personnel der an appr ved Rad* tion Wor ermit whi shall spe fy the dose ate levels the i ediate wor area and e maximum lowable sta time for in viduals i at area. or indivi al areas a essible to prsonnel wit radiation /evels
- is is no lly defined as the level t a distanc of 18 inche from the urce or ac essible sur ce.
- Radiat'on Protecti Personnel o personnel e orted by Ra iation Protect* n Personnel hall be exem t from the R issuance quirement during the pe ormance of heir assigne radiation pr tection dut' s, provi d they are oherwise fol wing plant r diation prot tion proced res for e ry into hig radiation a eas.
SALEM - UNIT 1 6-27 Amendment No. 139
ADMINISTRATIVE CONTROLS '
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Changes to the PCP:
- 1. Shall be documented and records of review performed shall be retained as required by Specification 6.10.3p. This documentation shall contain:
a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and b) A determination that the change will maintain the overall \
conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
/ /
- 2. Shall become effective after review and acceptance by the SORC and the approval of the Plant Manager. I k§)'
SALEM - UNIT 1 6-28 Amendment No. 2
ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls by shall be applied to high radiation areas in place of the controls required paragraph 20.1601(a) and (b) of 10 CFR Part 20:
6.12.1 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 chall 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 cr 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
- 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 within the area, or 6-27 Amendment No.
SALEM - UNIT I
(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 personr.el 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 knowladgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, k:nowledge, and pre-job briefing does not require documentation prior to initial entry.
6.12.2 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 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:
- 1. 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 SALEM - UNIT 1 6-27a Amendment No.
- 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to aremote receiver monitored by' iradiation 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
- 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 ccutrolling 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 cormunicate with and control every indivitluel 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 monitorinr 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.
- 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.
SALEM - UNIT 1 6-27b Amendment No.
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP chall be approved by the Commission prior to implementation.
6.13.2 Changes to the PCP:
- 1. Shall be documented and records of review performed shall be 3
retained as required by Specification 6.10. p. This documentation shall contain:
a) Sufficient information to oupport the change together with the appropriate analyses or evaluctions justifying the change(s) and b) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- 2. Shall become effective after review and acceptance by the SORC and the approval of the Plant Manager.
SALEM - UNIT 1 6-28 Amendment No.
ADMINISTRATIVE CONTROLS
.a.1 An aofthen onitorin devicel ohr li hconti uaull' i 'rdiae he paa h 02 c( doeat 0CRPa e aea 0 e in ihra iation the n radi ati on dose grteatertheraand1 a remshe* aupres ta mrem/ intbegara ededos id rceived Entry in such aas wih aiath this and en moniteri devi e b made y ftcte ose r dat level ite yotoi u areas sarlea hav en esthbo ccand hr py ronnel r yoebeen ade ing
- a. A hedaltho phyitquaif dedicindvi 1 (ie., uaulyifdiaes in ra iation doratcion edres)wtaraitndoert er mon Ar ainm*toring devwh ia wponibch orpruovi gyposi ives onit 1n doveste tivte c the rea and a itin pre llswh o peitrio *crdiation surilade ate- the ra euenc ecifel b the re
.12.2Insaddition t hedrqi aendop 1nl area h abcessiaet personel wthrdieat leels of hthtahjrpotefh y o eceivin hour a pro eogratrta 1000s wirem shall' be poied iath 1 peven ckd dors autorizd nty, ad th key sh 11 be itaed unr teaminstoraindve cwntol of thSonsiorleaor ShoiftSprioo dutandorSni r Sopervi rh - adiatie Prdonthet na ador all rema Re adiat~nWr '
e~wichon1 sprecify c-ede a rhteqcleelsif the th irmdiae wrkareat andWr the m am loabesa t orm dasi that. arediint For h rqi
.d2.1, areas odf accessibl ihrd eopron tio ev peThso*snormll aitefwda th svhtat levels distancpor 18 inhesd from th souceieno accessibl srae.getra 00r.emsalbpoie t unr Rdati h trotetio Personnl of personne scre byodnto Protecti/on rsonne sh 1 be exempt romothecRW isunce Dors quiremen rn thek pxerf t duigpeid of thirssged rabtos prsote tin dutiesaproviedhe inei okare a otewseoawnd pnth radin=ation poecsaytio r odre rnientry int hiha aradiator ndreas.asacsibe- eronwthrd onl SALEM - UNIT 2 6-27 Amendment No. 117
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 Changes to the PCP:
- 1. Shall be documrented zand records of review performed shall be retained as required by Specification 6.10.3p. This documentation shall contain:
a) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and b) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- 2. Shall become effective after review and acceptance by the SORC and the approval of the Plant Manager.
SALEM - UNIT 2 6-28 Amendment No.
ADMINISTRATIVE CONTROLS 6.12 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:
6.12.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiztion Sourca 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
- 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 within the area, or SALEM - UNIT 2 6-27 Amendment No.
(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.
6.12.2 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 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 activitica 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:
- 1. 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 SALEM - UNIT 2 6-27a Amendment No.
- 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
- 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.
- 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.
6-27b Amendment No.
SALEM - UNIT 2
r ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTSL PROGRAM (PCP) 6.13.1 The PCP Lhall be approved by the Commission prior to implementation.
6.13.2 Changes to the PCP:
- 1. Shall be documented and records of review performed shall be retained an requirod by Specification 6.10.3p. This documentation shall contain:
a) Sufficient information to support the change together with the appropriate analyvcs or evaluations justifying the change(s) and b) A determinLtion that the change will maintain the overall conformance of the colidifiod waste product to existing requirements of rederal, State, or other applicable regulations.
- 2. Shall become ef,!ectiv* after review and acceptance by the SORC and the approval of the Plant Hanager.
SALEM - UNIT 2 6-28 Amendment No. I