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| ==Enclosure:== | | ==Enclosure:== |
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Category:Letter type:NL
MONTHYEARNL-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 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update 2024-07-03
[Table view] |
Text
H. L Sumner. Jr. Southern Nuclear Vice President Operating Company, Inc.
40 lnverness Center Parkway Post Office Box 1295 Birmingham. Alabama 352111 Tel 205.992.7279 Fax 205.992.0341 SOUTHERN November 28, 2006 COMPANY Energy to Serve Your World' Docket Nos.: 50-348 NL-06-2567 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant NRC Generic Letter 2006-03 Request for Additional Information Response Ladies and Gentlemen:
By letter dated October 13,2006, Southern Nuclear Operating Company (SNC), the licensed operator for the Joseph M. Farley Nuclear Plant, received a request for additional information for Generic Letter 2006-03: Potentially Nonconforming Hemyc and MT Fire Barrier Configurations.
In accordance with 10 CFR 50.54(f), SNC hereby submits its response.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerelv.
H. L. Sumner, Jr.
A.
5 .;,p,. - -+bk, -.'.. .,.!
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4 '4,..-.
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Enclosure:
NRC Generic Letter 2006-03 Request for Additional Information Response
U. S. Nuclear Regulatory Commission NL-06-2567 Page 2 cc: Southern Nuclear Ouerating Com~anv Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, General Manager - Plant Farley RTYPE: CFA04.054; LC# 14508 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Ms. K. R. Cotton, NRR Project Manager - Farley Mr. C. A. Patterson, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Enclosure Joseph M. Farley Nuclear Plant NRC Generic Letter 2006-03 Request for Additional Information Response
Enclosure Joseph M. Farley Nuclear Plant NRC Generic Letter 2006-03 Request for Additional Information Response Farley Nuclear Plant utilizes Promat-H board as described in Southern Nuclear Operating Company (SNC) response dated June 9,2006 to Generic Letter 2006-03. This letter stated that Promat-H is tested in accordance with Underwriter Laboratories UL Standard 263, which references the American Society for Testing and Materials document ASTM El 19 and the National Fire Protection Association document NFPA 25 1. By NRC letter dated October 13, 2006, the NRC asked for additional information regarding the SNC response. The following items are the NRC requests and the SNC responses.
Request for Additional Information - Item 1 How was the Promat tested? Confirm that, per the phone call, the ASTM El 19 time-temperature, full scale fire testing was used.
SNC Response:
The Promat was tested and qualified to ASTM El 19-88 by Performance Contracting Inc.
under Omega Point Project No. 8806-90254 (Promat Report SR90-005). This testing included ASTM El 19 time-temperature, full scale fire testing for the wall assembly and a small scale fire testing of the ceiling assembly. The test details are documented in Promat Report SR90-005.
Request for Additional Information - Item 2 What acceptance criteria were used? Confirm that, per the phone call, the 325 degrees Fahrenheit temperature criterion was used.
SNC Response:
The test acceptance criteria were that of ASTM El 19-88 Section 16 "Conditions of Acceptance," which meets the acceptance criteria of GL 86-10, Supplement 1. The 325 degrees Fahrenheit temperature criterion was used, which assumes a maximum temperature rise of 250 degrees Fahrenheit above an ambient temperature of 75 degrees Fahrenheit.
Request for Additional Information - Item 3 How were installed configurations that were different fiom tested configurations evaluated?
Confmn that, per the phone call, the field installation deviations from the tested configurations were evaluated in accordance with the Generic Letter 86-10, Section 3.2.2 criteria.
SNC Response:
An analysis and acceptance for plant specific deviations from the tested configurations is included in Performance Contracting Inc. Fire Protection Technical Evaluation (FPTE) FPTE 2006-001 Revision 0. This evaluation received a documented review and approval by a qualified fire protection engineer within Southern Nuclear and found to be consistent with the GL 86-10, Section 3.2.2 criteria.
Text
H. L Sumner. Jr. Southern Nuclear Vice President Operating Company, Inc.
40 lnverness Center Parkway Post Office Box 1295 Birmingham. Alabama 352111 Tel 205.992.7279 Fax 205.992.0341 SOUTHERN November 28, 2006 COMPANY Energy to Serve Your World' Docket Nos.: 50-348 NL-06-2567 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant NRC Generic Letter 2006-03 Request for Additional Information Response Ladies and Gentlemen:
By letter dated October 13,2006, Southern Nuclear Operating Company (SNC), the licensed operator for the Joseph M. Farley Nuclear Plant, received a request for additional information for Generic Letter 2006-03: Potentially Nonconforming Hemyc and MT Fire Barrier Configurations.
In accordance with 10 CFR 50.54(f), SNC hereby submits its response.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerelv.
H. L. Sumner, Jr.
A.
5 .;,p,. - -+bk, -.'.. .,.!
a ' i ~ / :
.* i ;,-, (
4 '4,..-.
5 './,
'a c.,- . :.<,
&$TJLSldaj
, ,;:, ;c i- i>,Q JP,t<<r;.. .
Enclosure:
NRC Generic Letter 2006-03 Request for Additional Information Response
U. S. Nuclear Regulatory Commission NL-06-2567 Page 2 cc: Southern Nuclear Ouerating Com~anv Mr. J. T. Gasser, Executive Vice President Mr. J. R. Johnson, General Manager - Plant Farley RTYPE: CFA04.054; LC# 14508 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Ms. K. R. Cotton, NRR Project Manager - Farley Mr. C. A. Patterson, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Enclosure Joseph M. Farley Nuclear Plant NRC Generic Letter 2006-03 Request for Additional Information Response
Enclosure Joseph M. Farley Nuclear Plant NRC Generic Letter 2006-03 Request for Additional Information Response Farley Nuclear Plant utilizes Promat-H board as described in Southern Nuclear Operating Company (SNC) response dated June 9,2006 to Generic Letter 2006-03. This letter stated that Promat-H is tested in accordance with Underwriter Laboratories UL Standard 263, which references the American Society for Testing and Materials document ASTM El 19 and the National Fire Protection Association document NFPA 25 1. By NRC letter dated October 13, 2006, the NRC asked for additional information regarding the SNC response. The following items are the NRC requests and the SNC responses.
Request for Additional Information - Item 1 How was the Promat tested? Confirm that, per the phone call, the ASTM El 19 time-temperature, full scale fire testing was used.
SNC Response:
The Promat was tested and qualified to ASTM El 19-88 by Performance Contracting Inc.
under Omega Point Project No. 8806-90254 (Promat Report SR90-005). This testing included ASTM El 19 time-temperature, full scale fire testing for the wall assembly and a small scale fire testing of the ceiling assembly. The test details are documented in Promat Report SR90-005.
Request for Additional Information - Item 2 What acceptance criteria were used? Confirm that, per the phone call, the 325 degrees Fahrenheit temperature criterion was used.
SNC Response:
The test acceptance criteria were that of ASTM El 19-88 Section 16 "Conditions of Acceptance," which meets the acceptance criteria of GL 86-10, Supplement 1. The 325 degrees Fahrenheit temperature criterion was used, which assumes a maximum temperature rise of 250 degrees Fahrenheit above an ambient temperature of 75 degrees Fahrenheit.
Request for Additional Information - Item 3 How were installed configurations that were different fiom tested configurations evaluated?
Confmn that, per the phone call, the field installation deviations from the tested configurations were evaluated in accordance with the Generic Letter 86-10, Section 3.2.2 criteria.
SNC Response:
An analysis and acceptance for plant specific deviations from the tested configurations is included in Performance Contracting Inc. Fire Protection Technical Evaluation (FPTE) FPTE 2006-001 Revision 0. This evaluation received a documented review and approval by a qualified fire protection engineer within Southern Nuclear and found to be consistent with the GL 86-10, Section 3.2.2 criteria.