|
|
Line 3: |
Line 3: |
| | issue date = 06/10/2011 | | | issue date = 06/10/2011 |
| | title = Response to NRC Bulletin 2011-01, Mitigating Strategies | | | title = Response to NRC Bulletin 2011-01, Mitigating Strategies |
| | author name = Stinson L M | | | author name = Stinson L |
| | author affiliation = Southern Nuclear Operating Co, Inc | | | author affiliation = Southern Nuclear Operating Co, Inc |
| | addressee name = | | | addressee name = |
Letter Sequence Request |
---|
|
|
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
[Table View] |
|
---|
Category:Letter type:NL
MONTHYEARNL-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-24-0340, 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-24-0321, 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, Plants Units 1&2, 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 Plants Units 1&2, 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-24-0201, 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-24-0238, 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-24-0134, 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-23-0877, 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 NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 2024-09-04
[Table view] |
Text
Southern Nuclear Operating Company, Inc.Post Office Drawer 470 Ashford, Alabama 36312 June 10, 2011 SOUTHERN Docket Nos.: 50-348; 50-364 COMPANY Energy to Serve Your World" U. S. Nuclear Regulatory Commission ATTN: Document Control Desk NL-1 1-0984 Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Response to NRC Bulletin 2011-01 Mitigating Strategies Ladies and Gentlemen:
By letter dated May 11, 2011 the Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2011-01 to holders of operating licenses requiring a comprehensive verification of compliance within 30 days and a need for information associated with the mitigating strategies within 60 days under Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(hh)(2).
This letter is in response to the information requested within 30 days of the date of the letter dated May 11, 2011 and is provided in the Enclosure.
A separate response will be provided for information requested within 60 days of letter dated May 11, 2011. Southern Nuclear Operating Company (SNC) is the licensed operator for the Joseph M.Farley Nuclear Plant (Farley).Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, 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.This letter contains no NRC commitments.
If you have any questions, please contact Jack Stringfellow at (205) 992-7037.Respectfully submitted, L. M. Stinson Vice President
-Farley Sworn to and subscribed before me this 0 day of TU fl , ,2011.Notary Public My commission expires: I 3 1o -/LMS/LBH/lac U. S. Nuclear Regulatory Commission NL- 11-0984 Page 2
Enclosure:
SNC Response to NRC Bulletin 2011-01: Mitigating Strategies cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Ms. P. M. Marino, Vice President
-Engineering Mr. M. J. Ajluni, Nuclear Licensing Director RTYPE: CFA04.054 U. S. Nuclear Requlatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager -Farley Mr. E. L. Crowe, Senior Resident Inspector
-Farley Mr. P. G. Boyle, NRR Project Manager Joseph M. Farley Nuclear Plant, Units 1 and 2 Enclosure SNC Response to NRC Bulletin 2011-01: Mitigating Strategies NRC Question 1 Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?SNC Response Yes. Representatives from several groups were utilized to complete verifications of the functionality of equipment necessary to execute the mitigating strategies as required by 10 CFR 50.54(hh)(2).
Verification of functionality was achieved by performing a series of inspections and tests of equipment and reviews and walk-through of procedures.
All equipment was found to be in a state of readiness to implement the mitigating strategies as required in 10 CFR 50.54(hh)(2).
NRC Question 2 Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?SNC Response Yes. A thorough review of staffing levels and qualification and training of operations and support personnel, and walk through of implementing procedures needed to implement the mitigating strategies required by 10 CFR 50.54(hh)(2) was conducted.
All required personnel were available and found to be qualified with no gaps noted. The review concluded that the current configuration of the facility, staffing levels and skill levels are sufficient to execute the necessary functions as required by 10 CFR 50.54(hh)(2).
Text
Southern Nuclear Operating Company, Inc.Post Office Drawer 470 Ashford, Alabama 36312 June 10, 2011 SOUTHERN Docket Nos.: 50-348; 50-364 COMPANY Energy to Serve Your World" U. S. Nuclear Regulatory Commission ATTN: Document Control Desk NL-1 1-0984 Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Response to NRC Bulletin 2011-01 Mitigating Strategies Ladies and Gentlemen:
By letter dated May 11, 2011 the Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2011-01 to holders of operating licenses requiring a comprehensive verification of compliance within 30 days and a need for information associated with the mitigating strategies within 60 days under Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(hh)(2).
This letter is in response to the information requested within 30 days of the date of the letter dated May 11, 2011 and is provided in the Enclosure.
A separate response will be provided for information requested within 60 days of letter dated May 11, 2011. Southern Nuclear Operating Company (SNC) is the licensed operator for the Joseph M.Farley Nuclear Plant (Farley).Mr. L. M. Stinson states he is a Vice President of Southern Nuclear Operating Company, 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.This letter contains no NRC commitments.
If you have any questions, please contact Jack Stringfellow at (205) 992-7037.Respectfully submitted, L. M. Stinson Vice President
-Farley Sworn to and subscribed before me this 0 day of TU fl , ,2011.Notary Public My commission expires: I 3 1o -/LMS/LBH/lac U. S. Nuclear Regulatory Commission NL- 11-0984 Page 2
Enclosure:
SNC Response to NRC Bulletin 2011-01: Mitigating Strategies cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Ms. P. M. Marino, Vice President
-Engineering Mr. M. J. Ajluni, Nuclear Licensing Director RTYPE: CFA04.054 U. S. Nuclear Requlatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager -Farley Mr. E. L. Crowe, Senior Resident Inspector
-Farley Mr. P. G. Boyle, NRR Project Manager Joseph M. Farley Nuclear Plant, Units 1 and 2 Enclosure SNC Response to NRC Bulletin 2011-01: Mitigating Strategies NRC Question 1 Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?SNC Response Yes. Representatives from several groups were utilized to complete verifications of the functionality of equipment necessary to execute the mitigating strategies as required by 10 CFR 50.54(hh)(2).
Verification of functionality was achieved by performing a series of inspections and tests of equipment and reviews and walk-through of procedures.
All equipment was found to be in a state of readiness to implement the mitigating strategies as required in 10 CFR 50.54(hh)(2).
NRC Question 2 Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?SNC Response Yes. A thorough review of staffing levels and qualification and training of operations and support personnel, and walk through of implementing procedures needed to implement the mitigating strategies required by 10 CFR 50.54(hh)(2) was conducted.
All required personnel were available and found to be qualified with no gaps noted. The review concluded that the current configuration of the facility, staffing levels and skill levels are sufficient to execute the necessary functions as required by 10 CFR 50.54(hh)(2).