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Category:Fire Protection Plan
MONTHYEARML21137A1912021-05-17017 May 2021 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Chapter 2.0-2.3, Area Design Hazards Analysis-Redacted ML21008A4182020-12-17017 December 2020 Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1 ML21008A4142020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Chapter 4, Fire Protection Program ML21008A4202020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Cover and Page Index ML21008A4212020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Chapter 1, Introduction ML21008A4262020-12-17017 December 2020 Byron/Braidwood Stations - Amendment 29 to Fire Protection Report, Appendices RS-20-153, Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-12020-12-17017 December 2020 Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1 ML19170A3112019-06-19019 June 2019 Redacted Braidwood Station, Units 1 & 2, and Byron Station, Units 1 & 2, Amendment 28 to Fire Protection Report, Appendix 5.1 (Public Version Pages 1-76 and 129-287) ML19169A0232019-06-18018 June 2019 Amendment to Fire Protection Report, Chapter 2.0 - 2.3, Area (Public Version Pages 1-26, 43-103, and 134) ML19168A2162019-06-17017 June 2019 Redacted Byron Station, Units 1&2, Amendment 28 to Fire Protection Report, Chapter 2.4, Safe Shutdown Analysis (Public Version Pages 1-20 and 1626-1643) RS-18-144, Amendment 28 to Fire Protection Report, Chapter 4, Fire Protection Program2018-12-17017 December 2018 Amendment 28 to Fire Protection Report, Chapter 4, Fire Protection Program RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report, Chapter 1, Introduction2016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report, Chapter 1, Introduction RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report Cover and Page Index2016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report Cover and Page Index ML16357A5932016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program RS-16-248, Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-12016-12-15015 December 2016 Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 RS-16-248, Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program2016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 4.0, Fire Protection Program ML16357A5912016-12-15015 December 2016 Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 ML16357A5922016-12-15015 December 2016 Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 ML17095A8522016-12-15015 December 2016 Redacted Byron Nuclear Station, Amendment 27 to Fire Protection Plan, Chapter 2.4, Safe Shutdown Analysis. Section 2.4 Public Version Pages 1-19 and 1626-1643 ML17095A8662016-12-15015 December 2016 Redacted Braidwood Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 2.4, Safe Shutdown Analysis. Section 2.4 Public Version Pages 1-18 and 1726-1742 ML16357A5842016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report, Chapter 1, Introduction ML17087A2212016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 2.0, Fire Hazards Analysis ML16357A5832016-12-15015 December 2016 Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Fire Protection Report Cover and Page Index ML17094A8652016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 5.1, Appendices RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 5.1, Appendices2016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 5.1, Appendices RS-16-248, Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 2.0, Fire Hazards Analysis2016-12-15015 December 2016 Redacted Byron/Braidwood Nuclear Stations, Amendment 27 to Fire Protection Report, Chapter 2.0, Fire Hazards Analysis RS-16-248, Byron Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-12016-12-15015 December 2016 Byron Nuclear Station, Amendment 27 to Fire Protection Report, Chapter 3.0, Guidelines of BTP Cmeb 9.5-1 ML15054A4562014-12-15015 December 2014 Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26. (Redacted Version) RS-14-338, Braidwood, Units 1 and 2, Byron, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26. (Redacted Version)2014-12-15015 December 2014 Braidwood, Units 1 and 2, Byron, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 15, Updated Fire Protection Report (Fpr), Amendment 26. (Redacted Version) RS-12-043, Units 1 & 2 - Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate2012-03-30030 March 2012 Units 1 & 2 - Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate ML0406201762004-03-0101 March 2004 Re Notification of NRC Triennial Fire Protection Baseline Inspection RS-02-207, Amendment 20 to Byron/Braidwood Stations Fire Protection Report, Tables 2.4-5 - 3-12002-12-31031 December 2002 Amendment 20 to Byron/Braidwood Stations Fire Protection Report, Tables 2.4-5 - 3-1 2021-05-17
[Table view] Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-117, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-097, License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly2022-08-31031 August 2022 License Amendment Request to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-057, Constellation Radiological Emergency Plan Addendum Revision2022-04-21021 April 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022 Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022 Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC 2024-01-11
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Exelon Generation Company, LLC www.exeloncorp.com Exelokn 430Wifield Roaderation Warrenville, IL60555 10 CFR 50.90 RS-12-043 March 30, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate
References:
- 1. Letter from Craig Lambert (Exelon Generation Company, LLC) to U. S. NRC, "Request for License Amendment Regarding Measurement Uncertainty Recapture (MUR) Power Uprate," dated June 23, 2011
- 2. Letter from B. Mozafari (U. S. NRC) to M. J. Pacilio (Exelon Generation Company, LLC), "Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2 - Request for Additional Information RE: Measurement Uncertainty Recapture Power Uprate Request (TAC NOS. ME6587, ME6588, ME6589, and ME6590)," dated February 14, 2012 [ML120270146]
- 3. E-mail from B. Mozafari (U. S. NRC) to L. Holden (et. al.) (Exelon Generation Company, LLC), "RE: B/B MUR LAR RAI #1 Response Date," dated March 8, 2012 [ML12068A382]
- 4. Letter from B. Mozafari (U. S. NRC) to M. J. Pacilio (Exelon Generation Company, LLC), "Byron Station, Unit Nos. 1 and 2 and Braidwood Station, Units 1 and 2 - Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Request (TAC NOS. ME6587, ME6588, 6589, and ME6590)," dated March 9, 2012 [ML120590460]
- 5. Letter from Kevin F. Borton (Exelon Generation Company, LLC) to U. S.
NRC, "Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate," dated February 20, 2012 NRC' from
- 6. Letter Kevin F.
"Additional Borton (Exelon Information Generation Supporting Company, Request LLC) for License to U. S.
Amendment **
- 7. Letter from N. J. DiFrancesco (U. S. NRC) to M. J. Pacilio (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 - Request for Additional Information RE: Measurement Uncertainty Power Uprate Request (TAC NOS. ME6587, ME6588, ME6589, AND ME6590)," dated October 12, 2011 [ML11262A161]
In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to Facility Operating License Nos. NPF-72, NPF-77, NPF-37 and NPF-66 for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, respectively. Specifically, the proposed changes revise the Operating License and Technical Specifications to implement an increase in rated thermal power of approximately 1.63% based on increased feedwater flow measurement accuracy. In References 2, 3 and 4, the NRC provided requests for additional information (RAIs) to support review of the proposed changes.
In Reference 5, EGC provided responses to the RAIs in Reference 2 with the exception of the response to Mechanical and Civil Engineering Branch [EMCB] request number 13; as indicated in that letter EGC would provide this response under a separate transmittal. Attachment 1 to this letter provides the information in response to EMCB request number 13.
The requested information in Reference 3 is a follow-up to a previous response provided by EGC in Reference 6 to request number 5 from the Fire Protection Branch RAIs provided in Reference 7. In response to this request, EGC is providing the information in Attachment 2.
In response to the RAIs in Reference 4, EGC is providing the information in Attachments 3 and 4.
EGC has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the NRC in Reference 1. The additional information provided in this submittal does not affect the previously stated bases in Reference 1 for concluding that the proposed license amendment does not involve a significant hazards consideration. In addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this letter, please contact Leslie E. Holden at (630) 657-3316.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 3 0 1h day of March 2012.
Respectfully, Kevin F. Borton Manager, Licensing - Power Uprate
March 30, 2012 U.S. Nuclear Regulatory Commission Page 3 Response to Request for Additional Information, NRC Letter dated February 14, 2012 [ML120270146], Request Number 13, (Non- Proprietary) Response to Request for Additional Information, NRC E-mail dated March 8, 2012 [ML12068A382], (Non- Proprietary) Response to Request for Additional Information, NRC Letter dated March 9, 2012 [ML120590460], (Non-Proprietary) CD, "Byron and Braidwood Stations, Feedwater Flow Trend Data,"
March 30, 2011 [ML120590460], (Non-Proprietary)
Braidwood and Byron Stations Measurement Uncertainty Recapture License Amendment Request (MUR LAR)
March 30, 2012 ATTACHMENT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC Letter dated February 14, 2012 [ML120270146]
Request Number 13 (NON-PROPRIETARY)
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 1, page 1 NRC Civil and Mechanical Engineering Branch NRC Request 13 Discuss further information to demonstrate that, for the expected post-uprate conditions, the spent fuel pool (SFP)structure, including SFP liner and the spent fuel racks, remain capable of performing their intended design functions and will continue to be in compliance with the Byron and Braidwood design basis code of record(s) and acceptance criteria.
Response
As stated in the MUR power uprate license amendment request (LAR) (Reference Al-1),
Attachments 5 and 7,Section VI.1 .D.ii, "Spent Fuel Pool Cooling System," the decay heat load in the spent fuel pool (SFP) increases slightly for the MUR power uprate, resulting in an increase of approximately 3.5 0 F in the expected peak SFP water temperature for each of the three scenarios.
For the first design basis case discussed in Section VI.1 .D.ii, having a 1/3 core discharge and with one heat exchanger train operating, the peak SFP temperature increases to 144.6 0 F. For the second design basis case having a full core offload and with one heat exchanger train operating, the peak SFP temperature will increase to 166.6 0 F. For the third design basis case discussed, having a normal 1/3 core refueling discharge followed 17 days later by a full core discharge with two heat exchangers operating, the calculated bulk SFP water temperature increases to 141.5 0 F.
The existing calculations for the SFP structure, including the liner and fuel pool racks, have been reviewed for the increased peak temperatures. The review concluded that these structures will remain capable of performing their intended design functions following the MUR power uprate and will continue to be in compliance with the Byron and Braidwood Stations design basis code of record(s) and associated acceptance criteria.
Reference:
Al-1 Letter from Craig Lambert (Exelon Generation Company, LLC) to U. S. NRC, "Request for License Amendment Regarding Measurement Uncertainty Recapture (MUR) Power Uprate," dated June 23, 2011
Braidwood and Byron Stations Measurement Uncertainty Recapture License Amendment Request (MUR LAR)
March 30, 2012 ATTACHMENT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC E-Mail dated March 8, 2012 [ML12068A382]
(NON-PROPRIETARY)
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 2, page 1 NRC Fire Protection Branch NRC Follow-Up Request 1 Staff notes that modifications associatedwith the SGTR and MTO have not yet been completed to addressthe impact on the fire protection program. The NRC staff requests the licensee discuss how the results of modifications associatedwith the SGTR and MTO would impact the fire protection program and the plant's compliance with the fire protection program licensing basis, 10 CFR 50.48, or applicableportionsof BTP CMEB 9.5-1, at the EPU conditions. Confirm how will the licensee will ensure that, once developed and implemented, the modifications will not change this impact.
Response
The Steam Generator Tube Rupture (SGTR) and Margin to Overfill (MTO) modifications are still being developed. The impact of these modifications on the fire protection program will be evaluated in accordance with EGC's configuration change process. Per the process, these modifications will be evaluated to assure the changes do not adversely impact the approved Fire Protection Program and will not adversely impact the ability to achieve and maintain safe shutdown in accordance with the current Bryon Unit 1 license condition 2.C (6), Byron Unit 2 license condition 2.E, and Braidwood Unit 1 and 2 license condition 2.E.
Braidwood and Byron Stations Measurement Uncertainty Recapture License Amendment Request (MUR LAR)
March 30, 2012 ATTACHMENT 3 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC Letter dated March 9, 2012 [ML120590460]
(NON-PROPRIETARY)
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 1 NON-PROPRIETARY NRC Reactor Systems Branch NRC Request 1 Test fidelity, such as test versus planned plant configuration, test variations to address configurationdifferences, and potential effects of operation on flow profile and calibration,should be addressedon a plant-specificbasis. Applicant requests must provide a comparison of the test and plantpiping configurationswith an evaluation of the effect of any differences that could affect the UFM calibration. Further,sufficient variationsin test configurationsmust be tested to establish that test-to-plant differences have been bracketedin the determination of UFM calibrationand uncertainty. The turbulent flow regimes that exist when the plant is near full power result in limited upstream flow profile perturbationfrom downstream piping. Consequently, the effects of downstream equipment need not be consideredfor normal CheckPlus operation provided changes in downstream piping, such as the entrance to an elbow, are located greaterthan two pipe diameters downstream of the chordal paths. However, if the CheckPlus is operated with one or more transducersout of service, the acceptable separationdistance is likely a function of transducerto elbow orientation. In such cases, if separationdistance is less than five pipe diameters, it should be addressed. Therefore the staff requests the licensee to provide downstream distances from the untrasonicflow meter (UFM) to the next non-straightpipe component at the Alden labs test setup to verify their applicabilityto the in plant setup.
Response
Figures A3.1-1 and A3.1-2 provide diagrams of the Alden Laboratory test piping configuration typical for Byron and Braidwood Stations, respectively. There were no downstream elbows included in the test configuration. Attachment 11 of the Measurement Uncertainty Recapture (MUR) License Amendment Request (LAR)
(Reference A3-1) provided the typical in-plant piping configuration; the closest elbow is greater than five pipe diameters (approximately 30-feet) downstream of the LEFM spool piece.
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 2 NON-PROPRIETARY Figure A3.1-1: Byron Station Typical Alden Test Laboratory Pipe Configuration Figure 2 Allen Facility Lines 1&2 CAM58A-D TBST# rTEM#1 ITEM #2 ME CAM58A NOT INSTALLBD NOT INSTALLED t CAMSSB HALFMOON PLATE* NOT INSTALLED t -900 CAM58C NOT INSTALLED HALFMOONPLATE** t SEGMENTED CAM5SD NOT INSTALLED NOT INSTALLED 4t ELBOW (1400)
P-1"a12" t SEE SECTION A-A
- SEE SECTION C-C t tSEE SECTION D-D 16",24" DRESSER COUPLING 1'- 6" " IF I49-2" 1 ",i2'- 10"2'- 0" 7i'- 0" 24, FLOW 24" 16" SEGMENTED LINE 2 20"x1~ ELBOW (14" 0)
FLOW 24"x20" ITEM #2 STRAIGHTENER Plan View TRANSDUCERS @I NTRANSDUCERS 4!ý VERTICAL SECTION A-A. SECTION D-D SECTION B-B SECTION C-C Meter S/N 28239 Meter S/N 28239 Halfoon Plate Halfinoon Plate Tests CAM58A, B, & C Test CAM5 8D Test CAM58B. Test CAM58C F1111 111 111115 I IIMIETRI Elevation View CAMERON 16" Meter Purchase Order Number: 4502294181 ALDEN May, 2010
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 3 NON-PROPRIETARY Figure A3.1-2: Braidwood Station Typical Alden Test Laboratory Pipe Configuration Allen Facility Lines 1&2 CAM59A-D TEST # ITEM #1 ITEM #2 METER CAM59A NOT INSTALLED NOT INSTALLED "
CAM59B HALFMOON PLATE* NOT INSTALLED 90' CAM59C NOT INSTALLED HALFMOONPLATE** t SEGMENTED CAM59D NOT INSTALLED NOT INSTALLED tt ELBOW (14" 0) 1'-8-1/2" t SEE SECTION A-A
- SEE SECTION C-C t t SEE SECTION D-D 16"x24"
- DRESSER COUPLING 1-16" METER SIN 37647 SEGMENTED ELBOW (14" 0) 24"x20" STRAIGHTENER Plan View TRANSDUCERS SECTION A-A SECTION D-D SECTION B-B SECTION C-C Meter S/N 37647 Meter S/N 37647 Halfinoon Plate Halfinoon Plate Tests CAM59A, B, & C Test CAM59D Test CAM59B Test CAM59C i III) )))))III 11 ýETLIZ Elevation View CAMERON 16" Meter Purchase Order Number: 4502294182 ALDEN July, 2010
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 4 NON-PROPRIETARY NRC Request 2 Each applicant for a power uprate must conduct an in-depth evaluation of the UFM following installationat its plant that includes considerationof any differences between the test and inplantresults and must prepare a report that describes the results of the evaluation. This should address such items as calibrationtraceability,potentialloss of calibration,cross-checks with other plant parametersduring operation to ensure consistency between thermalpower calculation based upon the LEFM and other plant parameters,and final commissioning testing. The process should be describedin written documentation and a final commissioning test reportshould be availablefor NRC inspection. Therefore the NRC staff requests the licensee to provide a summary of the data comparing the LEFM Checkplus operating data to the Venturi data for the past 6 months to verify consistency between thermal power calculation based on LEFM and other plant parameters.
Response
The feedwater flow trend data is provided on a CD accompanying this submittal as . The Byron Unit 1 data is for 6-months from September 6, 2011 to March 8, 2012. The Byron Unit 2 data is from the date of LEFM start-up (October 12, 2011) to March 1, 2012. The Braidwood Unit 2 data is for 6-months from August 22, 2011 to March 1, 2012. The LEFM has not been installed in Braidwood Unit 1, therefore there is no available data.
The data provided is derived by taking flow data and averaging over a two hour period.
One two hour average is collected every 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and reported in the files on the accompanying CD and graphed on Figures A3.2-1 through 6. Figures A3.2-1, 3 and 5 show the difference between the venturi and the LEFM flows for each of the feedwater line flows for Byron Units 1 and 2, and Braidwood Unit 2, respectively. Figures A3.2-2, 4 and 6 show a comparison of the total feedwater flow between the venturis and LEFM for Byron Units 1 and 2, and Braidwood Unit 2, respectively.
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 5 NON-PROPRIETARY Figure A3.2-1: Byron Unit 1 Feedwater Flow - Venturi Flow Minus LEFM Flow (per Loop)
- ASG B SG A C SG (- D SG 15 10 -. .
-1 PPA effect - Poly Acid
-25 2 -10 0
-15
-20__
FAA - Poly Acrylic Acid
-25 88 8 0 0 0 0 ooq5o 8 o o o o
- - c-J c'J cJ coJ 0 0
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 6 NON-PROPRIETARY Figure A3.2-2: Byron Unit 1 Feedwater Flow - Total Venturi and LEFM Flow Comparison
- LEFM Total - Venturi Total - Delta LEFM-Venturi 15900 *190 W16850 4170 M
-j 15800 150
.2 U.
15750 - 130 15700 .. 110 t 15650 - 90 U.
15600 70 P A secured, known effect o i FW venturis .
-j 15550 .. .50 PAA - Poly Acrylic Acid 15500 - 30>
15450- 10 -
15400 __-10 0-
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 7 NON-PROPRIETARY Figure A3.2-3: Byron Unit 2 Feedwater Flow - Venturi Flow Minus LEFM Flow (per Loop)
-- A SG -o- B SG aC SG -D SG 40 Tii 20.
-J 0 ...
I 10 cc -20
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 8 NON-PROPRIETARY Figure A3.2-4: Byron Unit 2 Feedwater Flow - Total Venturi and LEFM Flow Comparison
- LEFM Total 0- Venturi Total - Delta LEFM-Venturi 15900 - r 190 15850 170
,J 15800- 150 U_'* 15750 -130 I-I C 15700 - -7110 0W 15600 - 70 15450 -,0 -. j o0 0
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 9 NON-PROPRIETARY Figure A3.2-5: Braidwood Unit 2 Feedwater Flow - Venturi Flow Minus LEFM Flow (per Loop)
ASG -o-BSG -- CSG A DSG 50 40
,AA",
A, A0A A6 AAAA4A -- A- A A A '44AA6 A 4 AA' AAAA &A &AAA 6,1&
20 A
,,j 10 E 0 iU -_10 0 o 20 o o 0 0 0 0 0 0 0
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 10 NON-PROPRIETARY Figure A3.2-6: Braidwood Unit 2 Feedwater Flow - Total Venturi and LEFM Flow Comparison
-a- LEFM Total - Venturi Total - Delta LEFM-Venturi 15900 190 7I-
- 15850 170 E 15 7 0 0 . ... .. . .. . ... ---.. . ... . .. .... .1 10
'90 LU 15650 ---- ___________- a 90___
LU 15600 70 "
Ne 15550 . .... ... . 50 15500...
4)
Braidwood/Byron Stations MUR LAR Response to RAI March 30, 2012 Attachment 3, page 11 NON-PROPRIETARY
Reference:
A3-1. Letter from Craig Lambert (Exelon Generation Company, LLC) to U. S. NRC, "Request for License Amendment Regarding Measurement Uncertainty Recapture (MUR) Power Uprate," dated June 23, 2011
Braidwood and Byron Stations Measurement Uncertainty Recapture License Amendment Request (MUR LAR)
March 30, 2012 ATTACHMENT 4 Braidwood and Byron Stations Measurement Uncertainty Recapture Technical Evaluation RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC Letter dated March 9, 2012 [ML120590460]
CD "FW Flow Data" File Name File Size:
Byron U1 LEFM-Venturi-History Trends 59 KB Byron U2 LEFM-Venturi-History Trends 56 KB Braidwood U2 LEFM-Venturi-History Trends 61 KB Sensitivity Level: Publically Available Media: CD-R Special Information: Data file format is .xls which is used by Microsoft Excel. The data file is to be kept in native-format and the CD-R copy can be submitted to the Public Document Room.