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| | issue date = 12/20/2011 | | | issue date = 12/20/2011 |
| | title = Response to NRC Bulletin 2011-01 | | | title = Response to NRC Bulletin 2011-01 |
| | author name = Jury K R | | | author name = Jury K |
| | author affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | author affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | addressee name = | | | addressee name = |
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| ==References:== | | ==References:== |
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| 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) | | 1)NRC Bulletin 2011-01,"Mitigating Strategies,"dated May 11 , 2011 (ML111250360) 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 (ML111600096) 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 (ML111920162) 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 (ML113120057) |
| 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: | | 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 | | 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 |
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 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
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-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-23-120, 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-23-119, 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-23-107, 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 RS-23-103, 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-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release 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-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-050, 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-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges 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-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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 2024-01-03
[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 (ML111250360) 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 (ML111600096) 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 (ML111920162) 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 (ML113120057)
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.