Letter Sequence Approval |
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MONTHYEARRS-11-117, License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources - Operating.2011-08-15015 August 2011 License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources - Operating. Project stage: Request ML11256A3332011-09-12012 September 2011 NRR E-mail Capture - Acceptance Review Results for Clinton Power Station, Unit No. 1 License Amendment Request to Modify Technical Specifications 3.8.1, AC Sources - Operating Project stage: Acceptance Review ML1135301902012-01-12012 January 2012 Request for Additional Information Related to License Amendment Request to Modify Technical Specifications Sections 3.8.1, AC Sources - Operating. Project stage: RAI RS-12-021, Additional Information Related to License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources-Operating,2012-02-13013 February 2012 Additional Information Related to License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources-Operating, Project stage: Request ML12122A9862012-05-22022 May 2012 Issuance of Amendment Proposed Technical Specification Amendment to Modify Technical Specification 3.8.1, AC Sources - Operating Surveillance Requirements Project stage: Approval ML12158A3732012-06-11011 June 2012 Correction to Issuance of License Amendment No. 199 Regarding Changes to Surveillance Requirements for Various Technical Specifications Project stage: Approval 2012-01-12
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Category:Letter
MONTHYEARIR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24004A0792024-01-18018 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000461/20230032023-11-0808 November 2023 Integrated Inspection Report 05000461/2023003 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000461/20233012023-09-12012 September 2023 NRC Initial License Examination Report 05000461/2023301 RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station 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 IR 05000461/20234202023-08-29029 August 2023 Security Baseline Inspection Report 05000461/2023420 RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20230022023-08-0404 August 2023 Integrated Inspection Report 05000461/2023002 RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release ML23209A8102023-07-28028 July 2023 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23198A0152023-07-27027 July 2023 License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23202A0992023-07-24024 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000461/2023004 ML23200A2592023-07-24024 July 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary IR 05000461/20234012023-07-19019 July 2023 Cyber Security Inspection Report 05000461/2023401 ML23194A1662023-07-19019 July 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release ML23191A8772023-07-11011 July 2023 Operator Licensing Examination Approval Clinton Power Station July 2023 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 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-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release IR 05000461/20230102023-05-26026 May 2023 Triennial Fire Protection Inspection Report 05000461/2023010 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 ML23143A3182023-05-23023 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 IR 05000461/20230012023-05-0404 May 2023 Integrated Inspection Report 05000461/2023001 ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000461/20220062023-03-0101 March 2023 Annual Assessment Letter for Clinton Power Station, Unit 1 (Report 05000461/2022006) RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 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 ML23039A1852023-02-10010 February 2023 Integrated Inspection Report 05000461/2022004 07201046/2022001 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 IR 05000461/20220112023-01-27027 January 2023 Biennial Problem Identification and Resolution Inspection Report 05000461/2022011 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing ML23005A0682023-01-0505 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000461/2023010 ML22341A6042022-12-0808 December 2022 Confirmation of Initial License Examination IR 05000461/20224022022-12-0606 December 2022 Security Baseline Inspection Report 05000461/2022402 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 2024-02-02
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation 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-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing 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-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock 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 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 ML21188A0202021-08-11011 August 2021 Issuance of Amendment No. 239 One-Time Extension of Containment Type a Integrated Leakage Rate Test Frequency RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications 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-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency2021-02-24024 February 2021 License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency 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-20-053, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2020-04-30030 April 2020 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 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 RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-06-18018 June 2019 Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control 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-18-116, Application to Revise Technical Specifications to Adopt TSTF-476, Improved BPWS Control Rod Insertion Process (NEDO-33091), Revision 12018-09-28028 September 2018 Application to Revise Technical Specifications to Adopt TSTF-476, Improved BPWS Control Rod Insertion Process (NEDO-33091), Revision 1 RS-18-105, License Amendment Request to Recapture Low-Power Testing Time2018-09-17017 September 2018 License Amendment Request to Recapture Low-Power Testing Time 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-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) ML18053A1822018-01-31031 January 2018 Enclosure 3 - Clinton Power Station, Unit 1 - Evaluation of Proposed Changes 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 ML18053A1702018-01-31031 January 2018 Attachment 3A - Clinton Power Station, Unit 1 - Marked-up Emergency Plan EP-AA-1000 Pages ML18053A1712018-01-31031 January 2018 Attachment 3B - Clinton Power Station, Unit 1 - Clean Emergency Plan EP-AA-1000 Pages 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 RS-18-005, License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation2018-01-0909 January 2018 License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation 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-17-076, License Amendment Request to Revise Spent Fuel Pool Level2017-07-18018 July 2017 License Amendment Request to Revise Spent Fuel Pool Level RS-17-017, License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations2017-05-0404 May 2017 License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations 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-16-228, Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-16-211, License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 12016-11-0404 November 2016 License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 1 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-16-143, Clinton - License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition2016-08-11011 August 2016 Clinton - License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition RS-16-143, License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition2016-08-11011 August 2016 License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition ML16229A2792016-08-11011 August 2016 Attachments 1 - 7: Clinton - License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition RS-16-153, License Amendment Request for Proposed Change to Technical Specifications Section 5.0, Administrative Controls for Permanently Defueled Condition2016-07-28028 July 2016 License Amendment Request for Proposed Change to Technical Specifications Section 5.0, Administrative Controls for Permanently Defueled Condition 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. 2023-08-21
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22292A0352022-11-10010 November 2022 Issuance of Amendment No. 246 Secondary Containment and the Fuel Building Railroad Airlock (EPID L-2022- LLA-0055) ML22263A4732022-11-10010 November 2022 Issuance of Amendment No. 247 Adoption of TSTF-230, Revision 1 ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML22047A1272022-02-22022 February 2022 Relief from the Requirements of the American Society of Mechanical Engineers Code ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21306A0002021-12-21021 December 2021 License Amendment to Revise Degraded Voltage Relay Allowable Values ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21132A2882021-06-28028 June 2021 Issuance of Amendment No. 238, Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21166A1682021-06-25025 June 2021 ML21090A1932021-05-19019 May 2021 Issuance of Amendment No. 237 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML21005A0612021-01-14014 January 2021 Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018) ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20268C2322020-11-0404 November 2020 Proposed Alternative I4R-06 to the Requirements of the ASME Code ML20266G3432020-10-14014 October 2020 Issuance of Amendment No. 235 Regarding Operation of the Emergency Auxiliary Reserve Transformer Load Tap Changer ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20218A6602020-09-0202 September 2020 Proposed Alternative I4R-01 to the Requirements of the ASME Code ML20232A1882020-09-0101 September 2020 Proposed Alternative I4R-02 to the Requirements of the ASME Code ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20219A2022020-09-0101 September 2020 Proposed Alternative I4R-05 to the Requirements of the American Society of Mechanical Engineers Code ML20212L3902020-08-31031 August 2020 Proposed Alternative I4r-03 to the Requirements of the Asme Code (Epid L-2019-Llr-0114) ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20163A7172020-06-26026 June 2020 Proposed Alternative to the Requirements of the ASME Code ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML20010E8702020-01-27027 January 2020 Proposed Alternative to the Requirements of the ASME Code ML19238A3082019-09-30030 September 2019 Issuance of Amendment - Regarding Adoption of TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19109A0012019-06-12012 June 2019 Issuance of Amendment Regarding Recapture of Low-Power Testing Time ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18303A3132019-01-0303 January 2019 Issuance of Amendment 221 Regarding Revised Alternative Source Term Dose Calculation 2023-04-28
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 22, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB~IECT: CLINTON POWER STATION, UNIT NO.1 - ISSUANCE OF AMENDMENT RE: PROPOSED TECHNICAL SPECIFICATION AMENDMENT TO MODIFY TECHNICAL SPECIFICATION 3.8.1, hAC SOURCES - OPERATING" SURVEILLANCE REQUIREMENTS (TAC NO. ME6876)
Dear Mr. Pacilio:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 199 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit NO.1. The amendment is in response to your application dated August 15, 2011, as supplemented by letter dated February 13, 2012.
The amendment requested a revision to the Limiting Condition for Operation 3.8.1, HAC Sources
- Operating," through a reduction to the maximum steady state voltage criteria for safety-related 4.16 kV buses from 4580 V to 4300 V in certain Technical Specifications (TSs), Section 3.8.1, Surveillance Requirements.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
~
\ 'lIthq/) A~Lv jJoel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosures:
- 1. Amendment No. 199 to NPF-62
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 199 License No. NPF-62
- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Exelon Generation Company, LLC (the licensee), dated August 15, 2011, as supplemented by letter dated February 13, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
-2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 199, are hereby incorporated into this license. Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J~~L :80. Chief Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Facility Operating License Date of Issuance:
ATTACHMENT TO LICENSE AMENDMENT NO. 199 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following pages of the Facility Operating License and Appendix "A" Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License NPF-62 License NPF-62 Page 3 Page 3 TSs TSs 3.8-4 3.8-4 3.8-6 3.8-6 3.8-8 3.8-8 3.8-9 3.8-9 3.8-11 3.8-11 3.8-14 3.8-14 3.8-15 3.8-15
AC Sources 3.8.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME G. Three or more required G.1 Enter LCO 3.0.3. Immediately AC sources inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and In accordance indicated power availability for each with the offsite circuit. Surveillance Frequency Control Program SR 3.8.1. 2 -------------------NOTES------------------
- 1. Performance of SR 3.8.1.7 satisfies this SR.
- 2. All DG starts may be preceded by an engine period and followed by prior to loading.
- 3. A modified DG start involving and gradual acceleration to synchronous may be used for this SR as recommended by the manufacturer.
When modified start procedures are not used, the time, voltage, and tolerances of SR 3.8.1.7 must be met.
Verify each DG starts from standby In accordance conditions and achieves steady state with the voltage ~ 4084 V and s 4300 V and frequency Surveillance
~ 58.8 Hz and ~ 61.2 Hz.
Frequency Control Program (continued)
CLINTON 3.8-4 Amendment No. 199
AC Sources--Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.7 -------------------NOTE-----------------
All DG starts may be by an engine period.
Veri each DG starts from standby In accordance condition and achieves: with the Surveillance
- a. In ~ 12 seconds, ~ 4084 V and Frequency Control Program frequency ~ 58.8 Hz; and
- b. state voltage ~ 4084 V and
~ 4300 V and frequency ~ 58.8 Hz and
~ 61.2 Hz.
SR 3.8.1. 8 ------------------NOTE-------------------
This Surveillance shall not be performed in MODE 1 or 2 (not applicable to Division 3 AC sources). However, credit may be taken for unplanned events that satisfy this SR.
automatic and manual transfer of In accordance unit power supply from the normal offsite with the circuit to the alternate offsite circuit. Surveillance Frequency Control Program (continued)
CLINTON 3.8-6 Amendment No. 199
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.11 -------------------NOTES------------------
- 1. All DG starts may be by an engine period.
- 2. This Surveillance shall not be performed in MODE 1, 2, or 3 (not icable to the Division 3 DG) .
However, credit may be taken for unplanned events that satisfy this SR.
on an actual or simulated loss of In accordance offsite power signal: with the Surveillance Frequency Control Program
- a. De-energization of emergency buses;
- b. Load shedding from emergency buses for Divisions 1 and 2; and
- c. DG auto-starts from standby condition and:
- 1. zes permanently connected loads in :0; 12 seconds,
- 2. energizes auto-connected shutdown loads,
- 3. maintains steady state voltage
~ 4084 V and :0; 4300 V,
- 4. maintains state frequency 58.8 Hz and:O; 61.2 Hz, and
- 5. supplies permanently connected and auto-connected shutdown loads for
~ 5 minutes.
(continued)
CLINTON 3.8-8 Amendment No. 199
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.:'2 -------------------NOTES------------------
- 1. All DG starts may be preceded by an engine period.
- 2. This Surveillance shall not be performed in MODE 1 or 2 (not applicable to the Division 3 DG).
However, credit may be taken for unplanned events that satisfy this SR.
Verify on an actual or simulated Emergency In accordance Core Cooling System (ECCS) initiation with the signal each DG auto-starts from standby Surveillance condition and: Frequency Control Program
- a. In S 12 seconds after auto-start and during tests, achieves voltage ~ 4084 V and ~58.8 Hz;
- b. Achieves state voltage ~ 4084 V and S 4300 V and frequency ~ 58.8 Hz and S 61.2 Hz; and
- c. Operates for 2 5 minutes.
SR 3.8.1.13 ------------------NOTE-------------------
Credit may be taken for unplanned events that satisfy this SR.
Verify each DG's automatic trips are In accordance bypassed on an actual or simulated ECCS with the initiation except: Surveillance Frequency
- a. Engine Control Program
- b. Generator differential current; and
- c. Overcrank for DG 1A and DG lB.
(continued)
CLINTON 3.8-9 Amendment No. 199
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FR::!:QUENCY SR 3.8.1.15 ----------------------NOT::!:---------------
- 1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has ~ 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loaded ~ 3482 kW for DG lA, ~ 3488 kW for DG lE, and ~ 1980 kW for DG 1C.
Momentary transients outside of the load range do not invalidate this test.
- 2. All DG starts may be preceded by an prelube Verify each DG starts and achieves: In accordance with the
- a. In S 12 seconds, voltage ~ 4084 V and Surveillance Frequency frequency ~ 58.8 Hz and Control Program
- b. state ~ 4084 V and S 4300 V and frequency ~ 58.8 Hz and S 61.2 Hz.
(continued)
CLINTON 3.8-11 Amendment No. 199
AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.19 -------------------NOTES------------------
- 1. All DG starts may be by an engine prelube period.
- 2. This Surveillance shall not be performed in MODE 1, 2, or 3 (not applicable to the Division 3 DG).
However, credit may be taken for unplanned events that this SR.
Verify, on an actual or simulated loss of In accordance offsite power signal in conjunction with an with the actual or simulated ECCS initiation Surveillance Frequency
- a. De-energization of emergency buses; Control Program
- b. Load shedding from emergency buses for Divisions 1 and 2; and
- c. DG auto-starts from condition and:
- 1. energizes connected loads in s 12 seconds,
- 2. energizes auto-connected emergency loads,
- 3. achieves steady state voltage
~ 4084 V and s 4300 V,
- 4. achieves steady state frequency
~ 58.8 Hz and S 61.2 Hz, and
- 5. supplies permanently connected and auto-connected emergency loads for
~ 5 minutes.
(continued)
CLINTON 3.8-14 Amendment No. 199
AC 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.20 -------------------NOTE-------------------
All DG starts may be by an engine prelube period.
Verify, when started simultaneously from In accordance standby condition, each DG achieves: with the Surveillance
- a. In S 12 seconds, 2 4084 V and Frequency Control Program frequency 2 58.8 Hz; and
- b. Steady state 4084 V and S 4300 V and 2 58.8 Hz and S 61.2 Hz.
CLINTON 3.8-15 Amendment No. 199
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 199 TO FACILITY OPERATING LICENSE NO. NPF-62 EXELON GENERATION COMPANY, LLC CLINTON POWER STATION, UNIT NO.1 DOCKET NO. 50-461 By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated August 15, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112280256 ), as supplemented by letter dated February 13, 2012 (ADAMS Accession No. ML12045A069), Exelon Generation Company, LLC (the licensee) requested changes to the technical specifications (TSs) for Clinton Power Station, Unit No.1 (CPS). The proposed changes would revise the maximum steady-state voltage criteria of TS Limiting Condition for Operation (LCO) 3.8.1, "AC Sources - Operating," for safety-related 4.16 kV buses from 4580 V to 4300 V.
The February 13, 2012, supplemental letter contained clarifying information and did not change the NRC staff's initial proposed finding of no significant hazards consideration.
2.0 REGULATORY EVALUATION
The staff used the following NRC requirements and guidance documents to review the license amendment request (LAR):
Part 50 of Title 10 of the Code of Federal Regulations (10 CFR) requires that TSs shall be included by applicants for a license authorizing operation of a production or utilization facility.
10 CFR 50.36(c) requires that TSs include items in five specific categories related to station operation. These categories are (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operations (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. The proposed changes to TS, discussed in this safety evaluation, are within the SRs category.
Regulatory Guide (RG) 1.9, Revision 3, "Selection, Design, Qualification, and Testing of Emergency Diesel Generator (EDG) Units used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants," provides certain recommendations for EDG design and testing, which in general are used as guidance to develop the SRs for the EDGs.
Enclosure
-2
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensee's regulatory and technical analyses in support of its proposed license amendment which are described in Section 3.0 of the licensee's submittal.
The detailed evaluation below will support the conclusion that: (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.
3.1 Background According to the CPS updated final safety analysis report (UFSAR), Section 8.1.2, the station is provided with offsite power from 138 kilovolt (kV) and 345 kV transmission systems. An Emergency Reserve Auxiliary Transformer (ERAT) transforms the electrical power from 138 kV to the 4160 V emergency auxiliary bus Voltage. The 345 kV transmission system feeds Reserve Auxiliary Transformers (RATs) A, B, and C, which in turn transform the electrical power to the 6900 V and 4160 V auxiliary bus voltages.
According to UFSAR, Section 8.3, the onsite alternating current (ac) power system consists of unit auxiliary (non-Class 1E) and unit Class 1E power systems. The unit auxiliary 6900 V and 4160 V buses are primarily fed from the two unit auxiliary transformers (UATs) 1A and 1B. The secondary source of these buses are three RATs A, B, and C. The onsite Class 1E AC power system includes three 4160V Class 1E divisions/buses, each provided with an EDG. One of the offsite power sources for Class 1E divisions/buses is the RAT B, and the other is the ERAT.
Each EDG set is automatically started based on the following events: (1) associated bus voltage when fed from either of the offsite power sources falls below the preset value [loss of voltage];
(2) reactor low water level; (3) high drywell pressure; or (4) associated bus second level undervoltage falls below the preset value (degraded voltage condition). After each EDG set accelerates to approximately rated frequency and voltage, its breaker automatically closes if normal offsite ac power is not available, and the EDG is sequentially loaded. In UFSAR, Section 8.3.1.2.2, under a paragraph regarding conformance to RG 1.9, it is stated that during the loading sequence, each EDG has the capability of frequency restoration to within 2 percent (%)
of nominal and voltage restoration to within 10% of nominal within 2 seconds after loading is applied, which is within 60% of the load sequence time interval.
3.2 Evaluation of Proposed Change to Maximum Steady-State Voltage Criteria In the LAR, the licensee stated that a review of TS Section 3.8.1 was performed and concluded that the maximum steady state voltage limit specified in TS SR's 3.8.1.2, 3.8.1.7, 3.8.1.11, 3.8.1.12, 3.8.1.15, 3.8.1.19, and 3.8.1.20 is non-conservative with respect to existing design basis analyses for certain 120 V ac safety-related components. Therefore, the licensee performed an Operability Evaluation (OE) in accordance with NRC Administrative Letter 98-10, "Dispositioning of Technical Specifications that are insufficient to assure plant safety." The OE concluded that the TS SRs associated with maximum steady-state voltage for EDGs involve an improper or inadequate TS value, and considered this issue a degraded or non-conforming
- 3 condition. Therefore, consistent with the NRC Administrative Letter 98-10, the licensee implemented administrative controls as a short term corrective action.
To correct the issue, the licensee proposed to revise the TS to reduce the maximum steady state voltage limit for EDGs from 4580 V to 4300 V, as described in the SR's 3.8.1.2, 3.8.1.7, 3.8.1.1:1, 3.8.1.12, 3.8.1.15, 3.8.1.19, and 3.8.1.20.
In response to a staff question, regarding the basis for an EDG voltage of 4300 V instead of 4580 V currently specified in TS, the licensee in a letter dated February 13, 2012, stated that based on its engineering calculation, it was derived that EDGs should have a maximum steady state voltage of 4300 V to prevent an overvoltage condition on the 120 V equipment. Therefore, the TS maximum allowable value of 4580 V was found to be non-conservative.
In response to another staff question regarding the basis of the maximum acceptable voltage limits on the 4.16 kV safety-related buses as 4454 V for 30 minutes, and 4300 V for continuous operation as stated in the LAR, the licensee in a letter dated February 13, 2012, provided the following clarification:
A Static VAR [volt amperes reactive] Compensator (SVC) is located on the 4.16 kV side of the RAT [B] and ERAT. The SVCs provide voltage support by varying the reactive load on the bus.
The maximum voltage for both offsite sources is 105 percent of rated voltage. When an offsite source voltage is high, the associated transformer SVC actively maintains the 4.16 kV bus at a lower value than would be expected without the SVC. If an SVC trips off-line while the 345 kV source is at the maximum 105 percent voltage, the voltage on the secondary side of RAT would reach 4454 V due to the transformer tap ratio. However, in the case of the 138 kV off-site source, a 105% maximum voltage would produce less than 4454 V on the secondary side of ERAT. Therefore, the RAT secondary voltage is the bounding case. The basis for 4454 V for 30 minutes is the maximum bus voltage that can be expected if the RAT SVC trips concurrent with 345 kV offsite voltage at 105 percent. It is expected that the licensee will reduce the voltage or transfer to the ERAT within 30 minutes. The steady state voltage limit of 4300 V will prevent component damage at the 120 V level at no load or lightly loaded conditions.
Based on the information provided, the staff finds the licensee response acceptable.
The staff requested the licensee to provide the maximum instrument voltage uncertainty considered to derive the TS EDG voltage limits. In a letter dated February 13, 2012, the licensee responded that the uncertainty considered is the same for Divisions 1, 2, and 3. For calibration purposes, test instrument uncertainties as well as voltage regulator uncertainties are considered to derive the allowable range for EDG output voltage. The test instrument uncertainty of plus (+) 21 V is applied to the lower limit of 4084 V and minus (-) 8 V is applied to the upper limit of 4300 V. The uncertainty due to the voltage regulator is plus/minus (+/-) 21 V.
Therefore, the allowable calibration band for the voltage regulator is 4126 V (Le., 4084 V + 21 V
+ 21 V) to 4271 V (Le., 4300 V - 8 V - 21 V). This calibration band for the voltage regulator ensures that the EDGs are operated within the TS limits of 4084 V and 4300 V. Based on this information, the staff finds the licensee has adequately considered the instrument voltage uncertainty to derive the TS EDG steady-state voltage limits.
-4 Additionally, the staff requested the licensee to provide a discussion of the voltage profile for the 4160 V safety-related buses when powered by the EDGs during the sequencing of large safety related loads, based on analysis or test. The licensee in a letter dated February 13, 2012, responded that the voltage profiles recorded for all three divisions from the integrated tests conducted in December 2011, demonstrated that the Division 1 EDG output voltage stabilized at approximately 4220 V, the Division 2 EDG output voltage stabilized at approximately 4230 V, and the Division 3 EDG output voltage stabilized at approximately 4140 V. This is acceptable to the staff as the voltages for all three EDGs stabilized below 4300 V following the sequencing of major safety-related loads.
Based on the review of the August 15, 2011, LAR and the responses provided by the licensee in a letter dated February 13, 2012, the NRC staff finds that the proposed EDG maximum steady state voltage limit is more restrictive, and meets the intent of RG 1.9, Revision 3. The EDGs will continue to provide adequate voltage to the safety-related loads and mitigate accidents as described in the UFSAR. Therefore, the staff finds the changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Illinois State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to installation or use of a facility's components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (76 FR 64391; October 18, 2011). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Swagata Som, NRR Date of issuance:
May 22,2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT NO.1 - ISSUANCE OF AMENDMENT RE: PROPOSED TECHNICAL SPECIFICATION AMENDMENT TO MODIFY TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES - OPERATING" SURVEILLANCE REQUIREMENTS (TAC NO. ME6876)
Dear Mr. Pacilio:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 199 to Facility Operating License No. NPF-62 for the Clinton Power Station, Unit No.1. The amendment is in response to your application dated August 15, 2011, as supplemented by letter dated February 13, 2012.
The amendment requested a revision to the Limiting Condition for Operation 3.8.1, "AC Sources
- Operating," through a reduction to the maximum steady state voltage criteria for safety-related 4.16 kV buses from 4580 V to 4300 V in certain Technical Specifications (TSs), Section 3.8.1, Surveillance Requirements.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely, I RA I Joel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosures:
- 1. Amendment No. 199 to NPF-62
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2 RIF RidsOgcRp Resource RidsNrrLASRohrer Resource RidsNrrDirsltsb Resource RidsNrrDorlLpl3-2 Resource RidsNrrPMClinton Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrRgn3MailCenter Resource Amendment ML12122A986 OFFICE
- LPL3-2IPM i LPL3-2IPM I LPL3-2ILA DEIEEEB IOGC I LPL3-2IBC LPL3-2IPM NAME PHernandez JWiebe
- JZimmerman JWiebe DATE 5107112 5107112 15107112 5120112 15116112 I 5122112 I 5122112 OFFICIAL RECORD COpy