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| | number = ML091310627 | | | number = ML091310627 |
| | issue date = 06/19/2009 | | | issue date = 06/19/2009 |
| | title = and Byron, Units 1 & 2 - Request for Additional Information Related to Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification | | | title = Request for Additional Information Related to Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification |
| | author name = David M J | | | author name = David M |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Pardee C G | | | addressee name = Pardee C |
| | addressee affiliation = Exelon Nuclear | | | addressee affiliation = Exelon Nuclear |
| | docket = 05000454, 05000455, 05000456, 05000457 | | | docket = 05000454, 05000455, 05000456, 05000457 |
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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 19, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,IL 60555 BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO DELETION OF E BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATION (TAC NOS. ME0206, ME0207, ME0208, AND ME0209) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 19, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,IL 60555 SUB~IECT: BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO DELETION OF E BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATION (TAC NOS. ME0206, ME0207, ME0208, AND ME0209) |
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| ==Dear Mr. Pardee:== | | ==Dear Mr. Pardee:== |
| By letter to the Nuclear Regulatory Commission (NRC) dated December 4, 2008, (Agencywide Documents Access and Management System Accession No. ML083390706), Exelon Generation Company, LLC (the licensee), submitted a license amendment request to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System] Specific Activity," and Surveillance Requirements 3.4.16.1 and 3.4.16.3.
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| The proposed changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity.
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| The NRC staff is reviewing your December 4, 2008, letter, and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 45 days after the date of this letter. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
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| If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1547.
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| Sincerely, ,i , f '-', ./ ! ',{! , :A Lit/)If' /' J. r Pr *ect Ma Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455 Request for Additional cc w/encls: Distribution via REQUEST FOR ADDITIONAL INFORMATION BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457 STN 50-454, AND STN 50-455 The Nuclear Regulatory Commission (NRC) staff is reviewing Exelon Generation Company, LLC's (the licensee's) license amendment request (LAR) dated December 4,2008 (Agencywide Documents Access and Management System Accession No. ML083390706).
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| The LAR requests to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System] Specific Activity," and Surveillance Requirements 3.4.16.1 and 3.4.16.3.
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| The requested changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity.
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| The LAR states that the changes are consistent with NRC-approved TS Task Force (TSTF) Change Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec." The NRC staff has determined that following additional information is required to complete its review. The proposed Inserts A and B contained in the LAR provide definitions for "dose equivalent 1-131" (DEI) and "dose equivalent Xe-133," respectively.
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| Insert A indicates that DEI may be determined using several references for dose conversion factors (DCFs). However, the purpose of the limiting condition for operation (LCO) for DEI is to satisfy Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Criterion 2, which establishes, in part, an operating restriction that is an initial condition of a design-basis accident (DBA). When surveillance of the RCS' radionuclides is performed, each acceptable set of DCFs will yield a different DEI. As approved by the NRC staff, the intent of TSTF-490 was to allow the licensee to select, from the acceptable list, one DCF reference for the calculation of DEI. Therefore, consistent with 10 CFR 50.36 and TSTF-490, the licensee should specify one DCF reference for DEI, which will be consistent with the specified LCO and DBA analysis, or justify why a list of several DCFs is consistent with the specified LCO and DBA analysis.
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| Therefore, please justify how the use of multiple DCFs maintains consistency with the specified LCO values and DBA analyses, or provide a revised definition that incorporates the DCFs appropriate for both the Braidwood and the Byron TSs.
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| June 19,2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO DELETION OF E BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATION (TAC NOS. ME0206, ME0207, ME0208, AND ME0209)
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| ==Dear Mr. Pardee:==
| | By letter to the Nuclear Regulatory Commission (NRC) dated December 4, 2008, (Agencywide Documents Access and Management System Accession No. ML083390706), Exelon Generation Company, LLC (the licensee), submitted a license amendment request to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System] |
| By letter to the Nuclear Regulatory Commission (NRC) dated December 4, 2008, (Agencywide Documents Access and Management System Accession No. ML083390706), Exelon Generation Company, LLC (the licensee), submitted a license amendment request to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System] Specific Activity," and Surveillance Requirements 3.4.16.1 and 3.4.16.3. | | Specific Activity," and Surveillance Requirements 3.4.16.1 and 3.4.16.3. The proposed changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity. |
| The proposed changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity. | | The NRC staff is reviewing your December 4, 2008, letter, and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 45 days after the date of this letter. |
| The NRC staff is reviewing your December 4,2008, letter, and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 45 days after the date of this letter. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1547. |
| If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1547. | | Sincerely, ~' |
| Sincerely, IRA! Marshall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455 Request for Additional cc w/encls: Distribution via DISTRIBUTION: | | ,i , |
| PUBLIC RidsNrrPMByron Resource RidsNrrDraAadb Resource LPL3-2 RJF RidsNrrPMBraidwood Resource RidsOgcRp Resource RidsNrrDorlLpl3-2 Resource RidsAcrsAcnw_MailCTR Resource ABoatright, NRR RidsNrrLA THarris Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No'.. ML091310627 NRR-088 OFFICE LPL3-2/PM LPL3-2/LA DRA/MDB/BC LPL3-2/BC NAME MDavid THarris RTaylor SCampbell DATE 05/14/09 05/13/09 06/16/09 06/19/09 OFFICIAL RECORD COPY}}
| | ~ |
| | :AM~ILit/)Da~n f '-', ./ ! |
| | ,/' ' , { ! |
| | If' / ' |
| | PI:t~~enSing J. r Pr *ect Ma Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455 |
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| | ==Enclosure:== |
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| | Request for Additional Information cc w/encls: Distribution via Listserv |
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| | REQUEST FOR ADDITIONAL INFORMATION BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457 STN 50-454, AND STN 50-455 The Nuclear Regulatory Commission (NRC) staff is reviewing Exelon Generation Company, LLC's (the licensee's) license amendment request (LAR) dated December 4,2008 (Agencywide Documents Access and Management System Accession No. ML083390706). The LAR requests to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System] Specific Activity," and Surveillance Requirements 3.4.16.1 and 3.4.16.3. The requested changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity. The LAR states that the changes are consistent with NRC-approved TS Task Force (TSTF) Change Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec." The NRC staff has determined that following additional information is required to complete its review. |
| | The proposed Inserts A and B contained in the LAR provide definitions for "dose equivalent 1-131" (DEI) and "dose equivalent Xe-133," respectively. Insert A indicates that DEI may be determined using several references for dose conversion factors (DCFs). However, the purpose of the limiting condition for operation (LCO) for DEI is to satisfy Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Criterion 2, which establishes, in part, an operating restriction that is an initial condition of a design-basis accident (DBA). When surveillance of the RCS' radionuclides is performed, each acceptable set of DCFs will yield a different DEI. As approved by the NRC staff, the intent of TSTF-490 was to allow the licensee to select, from the acceptable list, one DCF reference for the calculation of DEI. Therefore, consistent with 10 CFR 50.36 and TSTF-490, the licensee should specify one DCF reference for DEI, which will be consistent with the specified LCO and DBA analysis, or justify why a list of several DCFs is consistent with the specified LCO and DBA analysis. Therefore, please justify how the use of multiple DCFs maintains consistency with the specified LCO values and DBA analyses, or provide a revised definition that incorporates the DCFs appropriate for both the Braidwood and the Byron TSs. |
| | ENCLOSURE |
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| | ' .. ML091310627 NRR-088 OFFICE LPL3-2/PM LPL3-2/LA DRA/MDB/BC LPL3-2/BC NAME MDavid THarris RTaylor SCampbell DATE 05/14/09 05/13/09 06/16/09 06/19/09}} |
Letter Sequence RAI |
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TAC:ME0206, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME0207, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME0208, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME0209, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) |
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Category:Letter
MONTHYEARML24250A1182024-09-0606 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) IR 05000454/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005) ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000454/20240112024-08-0808 August 2024 Phase 2 Post- Approval License Renewal Report 05000454/2024011 IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter IR 05000454/20240022024-07-26026 July 2024 Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter ML24170A7652024-06-19019 June 2024 Confirmation of Initial License Examination RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 IR 05000454/20240012024-05-10010 May 2024 Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001 BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A1192024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors IR 05000454/20244012024-04-0303 April 2024 Cyber Security Inspection Report 05000454/2024401 and 05000455/2024401 (Public) ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 2024-09-06
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24250A1182024-09-0606 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information ML24053A3382024-02-22022 February 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062) ML24039A0412024-01-30030 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Braidwood Request for Alternative (I4R-18) ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML23018A1632023-01-18018 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22241A0522022-08-29029 August 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004 ML22237A0272022-08-25025 August 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22116A1272022-04-26026 April 2022 Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21228A2352021-08-17017 August 2021 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004 ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21036A1102021-02-0404 February 2021 NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information ML20294A5492020-10-21021 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20104C1452020-04-10010 April 2020 NRR E-mail Capture - Preliminary RAIs for Exelon'S April 6, 2020, Application to Defer Braidwood, Unit 2, Steam Generator Inspections ML20077M2212020-03-20020 March 2020 Ti 2515/194 Inspection Documentation Request ML20023A0812020-01-23023 January 2020 NRR E-mail Capture - RAIs for L-2019-LLA-0201 - Braidwood, Units 1 and 2, LAR to Revise TS 3.7.9, Ultimate Heat Sink 2024-09-06
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 19, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville,IL 60555 SUB~IECT: BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO DELETION OF E BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATION (TAC NOS. ME0206, ME0207, ME0208, AND ME0209)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated December 4, 2008, (Agencywide Documents Access and Management System Accession No. ML083390706), Exelon Generation Company, LLC (the licensee), submitted a license amendment request to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System]
Specific Activity," and Surveillance Requirements 3.4.16.1 and 3.4.16.3. The proposed changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity.
The NRC staff is reviewing your December 4, 2008, letter, and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 45 days after the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1547.
Sincerely, ~'
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PI:t~~enSing J. r Pr *ect Ma Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455
Enclosure:
Request for Additional Information cc w/encls: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457 STN 50-454, AND STN 50-455 The Nuclear Regulatory Commission (NRC) staff is reviewing Exelon Generation Company, LLC's (the licensee's) license amendment request (LAR) dated December 4,2008 (Agencywide Documents Access and Management System Accession No. ML083390706). The LAR requests to revise Technical Specifications (TSs) 1.1, "Definitions," and 3.4.16, "RCS [Reactor Coolant System] Specific Activity," and Surveillance Requirements 3.4.16.1 and 3.4.16.3. The requested changes would replace the current TS 3.4.16 limit on RCS gross specific activity with a new limit on RCS noble gas-specific activity. The LAR states that the changes are consistent with NRC-approved TS Task Force (TSTF) Change Traveler, TSTF-490, Revision 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec." The NRC staff has determined that following additional information is required to complete its review.
The proposed Inserts A and B contained in the LAR provide definitions for "dose equivalent 1-131" (DEI) and "dose equivalent Xe-133," respectively. Insert A indicates that DEI may be determined using several references for dose conversion factors (DCFs). However, the purpose of the limiting condition for operation (LCO) for DEI is to satisfy Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Criterion 2, which establishes, in part, an operating restriction that is an initial condition of a design-basis accident (DBA). When surveillance of the RCS' radionuclides is performed, each acceptable set of DCFs will yield a different DEI. As approved by the NRC staff, the intent of TSTF-490 was to allow the licensee to select, from the acceptable list, one DCF reference for the calculation of DEI. Therefore, consistent with 10 CFR 50.36 and TSTF-490, the licensee should specify one DCF reference for DEI, which will be consistent with the specified LCO and DBA analysis, or justify why a list of several DCFs is consistent with the specified LCO and DBA analysis. Therefore, please justify how the use of multiple DCFs maintains consistency with the specified LCO values and DBA analyses, or provide a revised definition that incorporates the DCFs appropriate for both the Braidwood and the Byron TSs.
ENCLOSURE
' .. ML091310627 NRR-088 OFFICE LPL3-2/PM LPL3-2/LA DRA/MDB/BC LPL3-2/BC NAME MDavid THarris RTaylor SCampbell DATE 05/14/09 05/13/09 06/16/09 06/19/09