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| {{#Wiki_filter:Mr. C. R. Pierce Regulatory Affairs Director UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 6, 2014 Southern Nuclear Operating Company, Inc. P. 0. Box 1295 I Bin-038 Birmingham, AL 35201-1295 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 6, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. |
| | P. 0. Box 1295 I Bin- 038 Birmingham, AL 35201-1295 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| JOSEPH M. FARLEY, UNITS 1 AND 2-ACCEPTANCE REVIEW CONCERNING ALTERNATIVE TO INSERVICE INSPECTION FOR REACTOR VESSEL FLANGE LEAK-OFF LINES (TAC NOS. MF4206 AND MF4207) | | JOSEPH M. FARLEY, UNITS 1 AND 2- ACCEPTANCE REVIEW CONCERNING ALTERNATIVE TO INSERVICE INSPECTION FOR REACTOR VESSEL FLANGE LEAK-OFF LINES (TAC NOS. MF4206 AND MF4207) |
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| ==Dear Mr. Pierce:== | | ==Dear Mr. Pierce:== |
| By letter dated May 28, 2014 (Agencywide Documents Access and Management System -Accession No. ML14148A492), the Southern Nuclear Operating Company, Inc., submitted a request for approval to use an alternative to the American Society of Mechanical Engineers (ASME) Section XI code requirement of subarticle IWC-5220 for leakage testing of the Class 2 reactor vessel flange leakoff lines. The request, if approved, would be applicable to the fourth 1 0-year inservice inspection interval. | | |
| * Pursuant to Section 50.55a(a)(3)(ii), the licensee requested to use the proposed alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The purpose of this correspondence is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to *identify whether the request has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. The NRC staff has reviewed your request and concluded that it does provide technical information in sufficient detail to enable the NRC staff to continue its detailed technical review and make an independent assessment regarding the acceptability of the proposed request in terms of regulatory requirements and the protection of public health and safety and the environment. | | By letter dated May 28, 2014 (Agencywide Documents Access and Management System |
| Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified in "requests for additional information" despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | | - Accession No. ML14148A492), the Southern Nuclear Operating Company, Inc., submitted a request for approval to use an alternative to the American Society of Mechanical Engineers (ASME) Section XI code requirement of subarticle IWC-5220 for leakage testing of the Class 2 reactor vessel flange leakoff lines. The request, if approved, would be applicable to the fourth 10-year inservice inspection interval. |
| C. R. Pierce If you have any questions, please contact me on {301) 415-1009. | | * Pursuant to Section 50.55a(a)(3)(ii), the licensee requested to use the proposed alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| Docket Nos.: 50-348 and 50-364 cc: Distribution via Listserv Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation C. R. Pierce If you have any questions, piease contact me on (301) 415-1009.
| | The purpose of this correspondence is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to |
| Docket Nos.: 50-348 and 50-364 cc: Distribution via Listserv DISTRIBUTION: | | *identify whether the request has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. |
| PUBLIC LPL2-1 R/F RidsAcrsAcnw_MaiiCTR Resource RidsNrrDorllpl2-1 Resource RidsNrrLASFigueroa Resource RidsNrrPMFarleyResource RidsRgn2MaiiCenter Resource KHoffman, NRR ADAMS Accession No.: ML14154A087 Sincerely, /RA/ Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation OFFICE NRR/LPLII-1/PM NRR/LPLII-1/LA NRR/LPLII-1/BC NRR/LPLII-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 06/03/14 06/05/14 06/05/14 06/06/14 OFFICIAL RECORD COPY}}
| | The NRC staff has reviewed your request and concluded that it does provide technical information in sufficient detail to enable the NRC staff to continue its detailed technical review and make an independent assessment regarding the acceptability of the proposed request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified in "requests for additional information" despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. |
| | |
| | C. R. Pierce If you have any questions, please contact me on {301) 415-1009. |
| | Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-348 and 50-364 cc: Distribution via Listserv |
| | |
| | ML14154A087 OFFICE NRR/LPLII-1/PM NRR/LPLII-1/LA NRR/LPLII-1/BC NRR/LPLII-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 06/03/14 06/05/14 06/05/14 06/06/14}} |
Letter Sequence Acceptance Review |
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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024
Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
ML24026A0532024-01-30030 January 2024
Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information
IR 05000348/20230402024-01-24024 January 2024
95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter
ML23341A2042024-01-12012 January 2024
Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021)
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
ML23345A1312024-01-0303 January 2024
Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021)
ML23346A2222023-12-22022 December 2023
Transmittal of Dam Inspection Report - Public
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
ML23228A1432023-11-22022 November 2023
Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals
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
ML23318A0672023-10-31031 October 2023
1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes,
IR 05000348/20230032023-10-24024 October 2023
Integrated Inspection Report 05000348/2023003 and 05000364/2023003
IR 05000348/20230912023-10-19019 October 2023
Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091
IR 05000348/20234022023-10-18018 October 2023
Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402
IR 05000348/20234412023-10-12012 October 2023
Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter)
ML23241B0212023-09-12012 September 2023
Review of Quality Assurance Topical Report
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
IR 05000348/20230902023-08-31031 August 2023
NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation
ML23164A1202023-08-30030 August 2023
Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code
ML23240A0012023-08-30030 August 2023
Correction to Issuance of Amendment Nos. 241, 242, 243, and 244
ML23235A2962023-08-24024 August 2023
Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances)
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-23-0713, 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-23-0704, 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
IR 05000348/20330012023-08-14014 August 2023
NRC Operator License Examination Report 05000348/203301 and 05000364/2023302
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
IR 05000348/20230022023-08-10010 August 2023
Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation
ML23221A3062023-08-0909 August 2023
Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter)
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
ML23202A1122023-08-0202 August 2023
Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
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
ML23136B1542023-07-0303 July 2023
Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis
IR 05000348/20230102023-06-29029 June 2023
Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010
NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023
Quality Assurance Topical Report Submittal
ML23164A2182023-06-14014 June 2023
Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter
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
IR 05000348/20234402023-05-0505 May 2023
Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover
IR 05000348/20230012023-05-0404 May 2023
Integrated Inspection Report 05000348/2023001 and 05000364/2023001
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
2024-01-30
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 6, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P. 0. Box 1295 I Bin- 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY, UNITS 1 AND 2- ACCEPTANCE REVIEW CONCERNING ALTERNATIVE TO INSERVICE INSPECTION FOR REACTOR VESSEL FLANGE LEAK-OFF LINES (TAC NOS. MF4206 AND MF4207)
Dear Mr. Pierce:
By letter dated May 28, 2014 (Agencywide Documents Access and Management System
- Accession No. ML14148A492), the Southern Nuclear Operating Company, Inc., submitted a request for approval to use an alternative to the American Society of Mechanical Engineers (ASME)Section XI code requirement of subarticle IWC-5220 for leakage testing of the Class 2 reactor vessel flange leakoff lines. The request, if approved, would be applicable to the fourth 10-year inservice inspection interval.
- Pursuant to Section 50.55a(a)(3)(ii), the licensee requested to use the proposed alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The purpose of this correspondence is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to
- identify whether the request has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed your request and concluded that it does provide technical information in sufficient detail to enable the NRC staff to continue its detailed technical review and make an independent assessment regarding the acceptability of the proposed request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified in "requests for additional information" despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
C. R. Pierce If you have any questions, please contact me on {301) 415-1009.
Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-348 and 50-364 cc: Distribution via Listserv
ML14154A087 OFFICE NRR/LPLII-1/PM NRR/LPLII-1/LA NRR/LPLII-1/BC NRR/LPLII-1/PM NAME SWilliams SFigueroa RPascarelli SWilliams DATE 06/03/14 06/05/14 06/05/14 06/06/14
