Letter Sequence Request |
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MONTHYEARRA-11-004, County, Limerick, Oyster Creek, Peach Bottom, Quad Cities, Three Mile Island, 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2011-06-0808 June 2011 County, Limerick, Oyster Creek, Peach Bottom, Quad Cities, Three Mile Island, 30-Day Response to NRC Bulletin 2011-01, Mitigating Strategies. Project stage: Request RA-11-043, Submittal of 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2011-07-0808 July 2011 Submittal of 60-Day Response to NRC Bulletin 2011-01, Mitigating Strategies. Project stage: Request ML1131200572011-11-22022 November 2011 Fleet - Bulletin 2011 01, Mitigating Strategies Request for Additional Information Regarding 60-Day Response Project stage: RAI RS-11-180, Response to NRC Bulletin 2011-012011-12-20020 December 2011 Response to NRC Bulletin 2011-01 Project stage: Request NOC-AE-12002817, Response to Request for Additional Information, Round 2, Regarding the License Amendment Request to Revise the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability2012-03-22022 March 2012 Response to Request for Additional Information, Round 2, Regarding the License Amendment Request to Revise the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability Project stage: Response to RAI ML12160A3872012-06-14014 June 2012 Closeout of Bulletin 2011-01, Mitigation Strategies, Project stage: Other ML12178A2152012-08-0202 August 2012 Closeout of Bulletin 2011-01 Migrating Strategies. Project stage: Other ML15188A0542015-05-27027 May 2015 Amendment to R-110 Reactor License for AGN-201 at Idaho State University Project stage: Request ML16040A1192016-02-22022 February 2016 Idaho State University - Request for Additional Information for License Amendment Request Regarding the Organizational Change for the Idaho State AGN-201 Training Reactor Project stage: RAI 2012-03-22
[Table View] |
Response to NRC Bulletin 2011-01ML113550139 |
Person / Time |
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Site: |
Dresden, Peach Bottom, Oyster Creek, Byron, Three Mile Island, Braidwood, Limerick, Clinton, Quad Cities, LaSalle |
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Issue date: |
12/20/2011 |
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From: |
Jury K R Exelon Generation Co, Exelon Nuclear |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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Shared Package |
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ML113550145 |
List: |
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References |
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IEB-11-001, RA-11-96, RS-11-180, TMI-11-165 |
Download: ML113550139 (5) |
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Category:Letter type:RS
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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-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 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 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) 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 RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 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 RS-24-031, Updated Safety Analysis Report (Usar), Revision 232024-04-0101 April 2024 Updated Safety Analysis Report (Usar), Revision 23 RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-24-015, Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval2024-02-29029 February 2024 Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release RS-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-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-119, 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-23-118, 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-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval 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-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 2024-07-31
[Table view] |
Text
ExeJon Generation 4300 Winfield Road Warrenville, ll60 555 www.cxeloncorp.com
---e Nuclear RS-11-180 TMI-11-165 Information
-Withhold Under 10 CFR 2.390 10 CFR 50.54(f)December 20,2011 U.S.Nuclear Regulatory Commission AnN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Braidwood Station, Units 1 and 2 Facility Operating License Nos.
and NRC Docket Nos.STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos.NPF*37 and NRC Docket Nos.STN and STN Clinton Power Station, Unit 1 Facility Operating License No.NPF-62 NRC Docket No.
Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos.
and DPR-25 NRC Docket Nos.50-237 and LaSalle County Station, Units 1 and 2 Facility Operating License Nos.NPF-11 and NPF*18 NRC Docket Nos.STN 50-373 and STN 50-374 Limerick Generating Station, Units 1 and 2 Facility Operating License Nos.NPF-39 and NPF*85 NRC Docket Nos.50-352 and Oyster CreekNuclearGenerating Station Renewed Facility Operating License No.DPR-16 NRC Docket No.
Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos.
and NRC Docket Nos.
and 50-278 Security-Related Information
-Withhold Under 10 CFR 2.390 Attachments 1 through 8 contain Sensitive Unclassified Non-Safeguards Information (SUNSI): upon separation this cover letter is decontrolled.
Security-Related Information
-Withhold Under 10 CFR 2.390 u.s.Nuclear Regulatory Commission Bulletin 2011-01 Response to Request for Additional Information December 20, 2011 Page 2 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos.DPR-29 and DPR-30 NRC Docket Nos.50-254 and 50-265 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No.DPR-50 NRC Docket No.50-289
Subject:
Response to Request for Additional Information Involving Exelon's 60-Day Response to NRC Bulletin 2011-01,"Mitigating Strategies"
References:
1)NRC Bulletin 2011-01,"Mitigating Strategies,"dated May 11 , 2011 (ML 111250360) 2)Letter from Keith R.Jury, Exelon Generation Company, LLC, to U.S.Nuclear Regulatory Commission Day Response to NRC Bulletin 2011-01 ,"Mitigating Strategies," dated June 8, 2011 (ML 111600096) 3)Letter from Keith R.Jury, Exelon Generation Company, LLC, to U.S.Nuclear Regulatory Commission60-Day Response to NRC Bulletin 2011-01 ,"Mitigating Strategies," dated July 8, 2011 (ML 111920162) 4)Letter from Joel S.Wiebe, U.S.Nuclear Regulatory Commission to Michael J.Pacilio, Exelon Generation Company, LLC-Braidwood Station, Units 1 and 2;Byron Station, Unit Nos.1 and 2;Clinton Power Station, Unit No.1;Dresden Nuclear Power Station, Units 2 and 3;LaSalle County Station, Units 1 and 2;Limerick Generating Station, Units 1 and 2;Oyster Creek Nuclear Generating Station;Peach Bottom Atomic Power Station, Units 2 and 3;Quad Cities Nuclear Power Station, Units 1 and 2;and Three Mile Island Nuclear Station, Unit1-Bulletin 2011-01,"Mitigating Strategies" Request for Additional Information Regarding 60-Day Response, dated November 22, 2011 (ML 113120057)
On May 11 , 2011 , the U.S.Nuclear Regulatory Commission (NRC)issued Bulletin 2011-01 ,"Mitigating Strategies" (Reference 1).The NRC issued this bulletin to achieve the following objectives:
1.To require that addressees provide a comprehensive verification of their compliance with the regulatory requirements of Title 10 of the Code of Federal Regulations (10 CFR)Section 50.54(hh)(2), Security-Related Information
-Withhold Under 10 CFR 2.390 Attachments 1 through 8 contain Sensitive Unclassified Non-Safeguards Information (SUNSI);upon separation this cover letter is decontrolled.
Security-Related Information
-Withhold Under 10 CFR 2.390 u.s.Nuclear Regulatory Commission Bulletin 2011-01 Response to Request for Additional Information December 20, 2011 Page 3 2.To notify addressees about the NRC staffs need for information associated with licensee mitigating strategies under 10 CFR 50.54(hh)(2) in light of the recent events at Japan's Fukushima Daiichi facility in order to determine if 1)additional assessment of program implementation is needed, 2)the current inspection program should be enhanced, or 3)further regulatory action is warranted, and 3.To requirethataddressees provide a written response to the NRC in accordance with 10 CFR 50.54(f).In Bulletin 2011-01, the NRC requested that each licensee submit a written response within 30 days of the date of the bulletin, which Exelon Generation Company, LLC (Exelon)submitted on June 8, 2011 (Reference 2).The bulletin also requested that each licensee submit a written response within 60 days of the date of the bulletin, which Exelon submitted on July 8, 2011 (Reference 3).Subsequently, by letter dated November 22,2011 (Reference 4), the NRC issued a request for additional information regarding Exelon's 60-day response to the bulletin, in which the NRC requested a response within 30 days of the date of the Reference 4 letter.Accordingly, the attachments to this letter contain the response to the requested information pursuant to the provisions of 10 CFR 50.54(f)for the applicable Exelon facilities listed below:*Braidwood Station, Units 1 and 2*Byron Station, Units 1 and 2*Clinton Power Station, Unit 1*Dresden Nuclear Power Station, Units 2 and 3*Limerick Generating Station, Units 1 and 2*Oyster Creek Nuclear Generating Station*Quad Cities Nuclear Power Station, Units 1 and 2*Three Mile Island Nuclear Station, Unit 1 The NRC, in the Reference 4 letter, indicated that there were no questions regarding the completeness of the responses for LaSalle County Station, Units 1 and 2, and Peach Bottom Atomic Power Station, Units 2 and 3.As a result, there is no request for additional information or a response needed for these stations.The attachments to this letter contain Sensitive Unclassified Non-Safeguards Information (SUNSI)and the information should be withheld from public disclosure in accordance with the requirements of 10 CFR 2.390.The pages have been marked accordingly with the notation"Security-Related Information
-Withhold Under 10 CFR 2.390." Security-Related Information
-Withhold Under 10 CFR 2.390 Attachments 1 through 8 containSensitiveUnclassified Non-Safeguards Information (SUNSI);upon separation this cover letter is decontrolled.
Security-Related Information
-Withhold Under 10 CFR 2.390 U.S.Nuclear Regulatory Commission Bulletin 2011-01 Response to Request for Additional Information December 20, 2011 Page 4 There are no regulatory commitments contained in this response.If there are any questions concerning this response, please contact David P.Helker at (610)765..5525.I declare under penalty of perjury that the foregoing is true and correct.Executed on the 20th day of December 2011.Respectfully, Vice President, Licensing and Regulatory Affairs Exelon Generation Company, LLC Attachment1-Braidwood Station Response to Request for Additional Information Attachment 2-Byron Station Response to Request forAdditionalInformation Attachment 3..Clinton Power Station Response to Request for Additional Information Attachment4-Dresden Nuclear Power Station Response to Request for Additional Information Attachment5-Umerick Generating Station Response to Request for Addjtional Information Attachment 6..Oyster Creek Nuclear Generating Station Response to Request for Additional Information Attachment7-auad Cities Nuclear Power Station Response to Request for Additional Information Attachment 8...Three Mile Island Nuclear Station, Unit 1 Response to Request for Additional Information Security-Related Information
-Withhold Under 10 CFR 2.390 Attachments 1 through 8 contain Sensitive Unclassified Non-Safeguards Information (SUNSI);upon separation this cover Jetter is decontrolled.
Security-Related Information Withhold Under 10 CFR 2.390 u.s.Nuclear Regulatory Commission Bulletin 2011-01 Response to Request for Additional Information December 20, 2011 Page 5 cc: Regional Administrator
-NRC Region I Regional Administrator
-NRC Region III NRC Senior Resident Inspector-Braidwood Station NRC Senior Resident Inspector-Byron Station NRC Senior Resident Inspector-Clinton Power Station NRC Senior Resident Inspector-Dresden Nuclear Power Station NRC Senior Resident Inspector-LaSalle County Station NRC Senior Resident Inspector-Limerick Generating Station NRC Senior Resident Inspector-Oyster Creek Nuclear Generating Station NRC Senior Resident Inspector-Peach Bottom Atomic Power Station NRC Senior Resident Inspector-Quad Cities Nuclear Power Station NRC Senior Resident Inspector-Three Mile Island Nuclear Station, Unit 1 NRC Project Manager, NRR-Braidwood Station NRC Project Manager, NRR-Byron Station NRC Project Manager, NRR-Clinton Power Station NRC Project Manager, NRR-Dresden Nuclear Power Station NRC Project Manager, NRR-LaSalle County Station NRC Project Manager, NRR-Limerick Generating Station NRC Project Manager, NRR-Oyster Creek Nuclear Generating Station NRC Project Manager, NRR-Peach Bottom Atomic Power Station NRC Project Manager, NRR-Quad Cities Nuclear Power Station NRC Project Manager, NRR-Three Mile Island Nuclear Station, Unit 1 Illinois Emergency Management Agency-Division of Nuclear Safety Director, Bureau of Radiation Protection
-Pennsylvania Department of Environmental Resources Director, Bureau of Nuclear Engineering
-New Jersey Department of Environmental Protection Chairman, Board of County Commissioners of Dauphin County, PA Chairman, Board of Supervisors of Londonderry Township, PA Mayor of Lacey Township, Forked River, NJ S.T.Gray, State of MarylandR.R.Janati, Commonwealth of Pennsylvania Security-Related Information
-Withhold Under 10 CFR 2.390 Attachments 1 through 8 contain Sensitive Unclassified Non-Safeguards Information (SUNSI);upon separation this cover letter is decontrolled.