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MONTHYEARNL-11-0984, Response to NRC Bulletin 2011-01, Mitigating Strategies2011-06-10010 June 2011 Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Request NL-11-1148, Day Response to NRC Bulletin 2011-01, Mitigating Strategies2011-07-0707 July 2011 Day Response to NRC Bulletin 2011-01, Mitigating Strategies Project stage: Request ML11312A1862011-11-21021 November 2011 Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies Project stage: RAI NL-11-2389, Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, Mitigating Strategies2011-12-15015 December 2011 Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, Mitigating Strategies Project stage: Response to RAI ML12125A2412012-05-25025 May 2012 Closeout of Bulletin 2011-01, Mitigating Strategies (TAC Nos. ME6430 and ME6431) Project stage: Other 2011-06-10
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Category:Letter type:NL
MONTHYEARNL-24-0320, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,.2024-09-27027 September 2024 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3,. NL-24-0349, Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided2024-09-20020 September 2024 Units 1 and 2 - 10 CFR 26.719(c)(1) 30-Day Report Blind Performance Test Results Inconsistent with Sample Provided NL-24-0341, Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-09-10010 September 2024 Response to Request for Additional Information Related to the Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0340, Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R322024-09-0404 September 2024 Unit 1 - Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 1 R32 NL-24-0259, License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes2024-09-0404 September 2024 License Amendment Request to Revise Technical Specification 3.4.14, Reactor Coolant System Pressure Isolation Valve Leakage, Surveillance Requirement 3.4.14.3 Acceptance Criteria and Miscellaneous Obsolete Changes NL-24-0321, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information2024-08-16016 August 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions - Supplemental Information NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0235, Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-06-19019 June 2024 Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0221, Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift2024-06-17017 June 2024 Pressurizer Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpoint Drift NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0123, for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel2024-04-15015 April 2024 for Manual Reactor Trip Due to Loss of Power to the 2A 125 Volt DC Distribution Panel NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0092, Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R292024-03-15015 March 2024 Inservice Inspection Program Owners Activity Report (OAR-1) for Outage 2R29 NL-24-0003, Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R312024-02-16016 February 2024 Inservice Inspection Program Owners Activity Report (OAR) Supplement for Outages 1 R30 and 1 R31 NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0828, Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift2023-11-30030 November 2023 Main Steam Safety Valve Lift Pressure Outside of Technical Specifications Limits Due to Setpolnt Drift NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal 2024-09-04
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Thomas A. Lynch Southern Nuclear Vi ce Presidenl . Farley Operating Company, Inc.
farley Nuclear Pla nt Post Office Drawer 470 Ashford, Alabama 36312 Tel 334.B1 4.4511 Fax 334.814.4728 December 15, 2011 SOUTHERN ........
COMPANY Docket Nos.: 50-348 NL-11-2389 50-364 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Units 1 and 2 Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies" (TAC NOS. ME6430 and ME6431)
Ladies and Gentlemen:
By letters dated June 10, 2011 (ADAMS Accession 1\10. ML11165A009) and July 7,2011 (ADAMS Accession No. ML11196A093) Southern Nuclear Operating Company Inc. (SNC) submitted a 30 day response and a 60 day response respectively to Nuclear Regulatory Commission (NRC)Bulletin 2011-01, Mitigating Strategies. Subsequently, by letter dated November 15, 2011 the NRC submitted a request for additional information (RAI) to the July 7, 2011 letter submitted by SNC. The response to the NRC RAI is provided in the Enclosure.
Mr. T. A. Lynch states he is a Vice President of Southern Nuclear Operating Company, and is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
u.s. Nuclear Regulatory Commission NL-11-2389 Page 2 This letter contains no NRC commitments. If you have any questions, please contact Doug McKinney at (205) 992-5982.
Respectfully submitted,
'icrL T. A. Lynch Vice President - Farley srr to and subscribed before me this t1'WL filO1.rJ.f1v J!L day of Dece~J)et ,2011.
Notary Public My commission expires:
TAULBH/lac
Enclosures:
Joseph M. Farley Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies" cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Chief Nuclear Officer Ms. P. M. Marino, Vice President - Engineering RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. V. Sreenivas, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Joseph M. Farley Nuclear Plant, Units 1 and 2 Enclosure Joseph M. Farley Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies"
Joseph M. Farley Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies" NRC RAI Describe in detail how you ensure that a vehicle is available to move the B.S.b portable pump and other B.S.b equipment to the appropriate place when needed.
The bulletin requested that each licensee describe in detail the controls for assuring equipment needed to execute the mitigating strategies will be available when needed. A vehicle is typically needed to implement the strategies since the portable pump and other equipment is stored away from target areas. The NRC staff could not determine if you performed activities to ensure that a tow vehicle would be available when needed.
SNC Response Farley maintains a tow vehicle that is available to move the B.S.b portable pump trailer and other B.S.b equipment to the appropriate location when needed. This vehicle is under the control of Operations and used for routine operations activities onsite and is typically located outside of the target areas and is equipped with radio equipment for direct communications with the Main Control Room. The vehicle is designated as the Outside Systems Operator truck. The hitch needed for towing is located and maintained in the B.S.b storage building.
Additionally. multiple other vehicles located outside the target area are available and controlled that can receive the hitch for towing of the B.S.b trailer and equipment. To ensure the vehicles are capable of responding. preventive maintenance is performed periodically and as recommended by the vehicle manufacturer. Vehicle maintenance is conducted on site but outside the target areas by onsite maintenance personnel.
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Text
Thomas A. Lynch Southern Nuclear Vi ce Presidenl . Farley Operating Company, Inc.
farley Nuclear Pla nt Post Office Drawer 470 Ashford, Alabama 36312 Tel 334.B1 4.4511 Fax 334.814.4728 December 15, 2011 SOUTHERN ........
COMPANY Docket Nos.: 50-348 NL-11-2389 50-364 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Units 1 and 2 Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies" (TAC NOS. ME6430 and ME6431)
Ladies and Gentlemen:
By letters dated June 10, 2011 (ADAMS Accession 1\10. ML11165A009) and July 7,2011 (ADAMS Accession No. ML11196A093) Southern Nuclear Operating Company Inc. (SNC) submitted a 30 day response and a 60 day response respectively to Nuclear Regulatory Commission (NRC)Bulletin 2011-01, Mitigating Strategies. Subsequently, by letter dated November 15, 2011 the NRC submitted a request for additional information (RAI) to the July 7, 2011 letter submitted by SNC. The response to the NRC RAI is provided in the Enclosure.
Mr. T. A. Lynch states he is a Vice President of Southern Nuclear Operating Company, and is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
u.s. Nuclear Regulatory Commission NL-11-2389 Page 2 This letter contains no NRC commitments. If you have any questions, please contact Doug McKinney at (205) 992-5982.
Respectfully submitted,
'icrL T. A. Lynch Vice President - Farley srr to and subscribed before me this t1'WL filO1.rJ.f1v J!L day of Dece~J)et ,2011.
Notary Public My commission expires:
TAULBH/lac
Enclosures:
Joseph M. Farley Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies" cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Chief Nuclear Officer Ms. P. M. Marino, Vice President - Engineering RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. V. Sreenivas, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Joseph M. Farley Nuclear Plant, Units 1 and 2 Enclosure Joseph M. Farley Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies"
Joseph M. Farley Response to Request for Additional Information Regarding 60 Day Response to Bulletin 2011-01, "Mitigating Strategies" NRC RAI Describe in detail how you ensure that a vehicle is available to move the B.S.b portable pump and other B.S.b equipment to the appropriate place when needed.
The bulletin requested that each licensee describe in detail the controls for assuring equipment needed to execute the mitigating strategies will be available when needed. A vehicle is typically needed to implement the strategies since the portable pump and other equipment is stored away from target areas. The NRC staff could not determine if you performed activities to ensure that a tow vehicle would be available when needed.
SNC Response Farley maintains a tow vehicle that is available to move the B.S.b portable pump trailer and other B.S.b equipment to the appropriate location when needed. This vehicle is under the control of Operations and used for routine operations activities onsite and is typically located outside of the target areas and is equipped with radio equipment for direct communications with the Main Control Room. The vehicle is designated as the Outside Systems Operator truck. The hitch needed for towing is located and maintained in the B.S.b storage building.
Additionally. multiple other vehicles located outside the target area are available and controlled that can receive the hitch for towing of the B.S.b trailer and equipment. To ensure the vehicles are capable of responding. preventive maintenance is performed periodically and as recommended by the vehicle manufacturer. Vehicle maintenance is conducted on site but outside the target areas by onsite maintenance personnel.
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