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MONTHYEARNL-11-1543, Response to NRC Request for Additional Information Proposed Relief Request FNP-ISI-RR-012011-08-11011 August 2011 Response to NRC Request for Additional Information Proposed Relief Request FNP-ISI-RR-01 Project stage: Response to RAI NL-12-0498, Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-012012-03-0909 March 2012 Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01 Project stage: Response to RAI ML12138A0082012-05-0808 May 2012 Relief Request 12-MN-003 Project stage: Request ML12250A6622012-08-22022 August 2012 Relief Request 12-MN-003, Response to Request for Additional Information Project stage: Response to RAI CP-201300003, Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010)2013-01-16016 January 2013 Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010) Project stage: Request ML13018A0672013-01-18018 January 2013 Acceptance Review Email, Relief Request B-2, Alternative to ASME Code Requirements for Examination of Reactor Vessel Hot-Leg Nozzle Welds, the Third 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML13029A7382013-01-29029 January 2013 Request for Additional Information Email, Relief Request B-2, Alternative to ASME Code Requirements for Examination of Reactor Vessel Hot-Leg Nozzle Welds, for the Third 10-Year Inservice Inspection Interval Project stage: RAI CP-201300143, Response to RAI for Unit 1 Relief Request No. B-22013-02-0707 February 2013 Response to RAI for Unit 1 Relief Request No. B-2 Project stage: Response to RAI ML13056A5032013-03-15015 March 2013 Relief Request B-2, Alternative to ASME Code Requirements for Examination of Reactor Vessel Hot-Leg Nozzle Welds, for the Third 10-Year Inservice Inspection Interval Project stage: Other 2013-01-16
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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
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Mark J. Ajiuni, P.E. Southern Nuclear Nuclear Licensing Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 March 9, 2012 SOUTHERN COMPANY Docket Nos.: 50-348 NL-12-0498 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Response to NRC RAI Dated February 23, 2012 Reqarding Proposed Relief Request FNP-ISI-RR-01 Ladies and Gentlemen:
By letter dated March 28, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110871951), Southern Nuclear Operating Company (SNC) submitted a request for relief for Joseph M. Farley Nuclear Plant, Unit 1, that would allow the use of an alternate depth-sizing qualification for volumetric examinations of the reactor pressure vessel nozzle-to-safe end dissimilar metal welds from the inside surface. The U.S. Nuclear Regulatory Commission staff (NRC) issued a Request for Additional Information (RAI) by letter dated July 14, 2011 (ADAMS Accession No. ML11173A047), and SNC responded by letter dated August 11, 2011 (ADAMS Accession No. ML112232241). The NRC considered this issue further and found that additional information is needed to continue the review of this relief request. A second RAI was sent to SNC in letter dated February 23, 2012 (ADAMS Accession No. ML12048B330). The SNC responses to the second RAI are provided in the Enclosure.
The NRC commitments contained in this letter are provided as a table in . If you have any questions, please contact Jack Stringfellow at (205) 992-7037.
Sincerely, M. J. Ajluni Nuclear Licensing Director MJA/RMJ ALI -7
U. S. Nuclear Regulatory Commission NL-12-0498 Page 2
Enclosures:
- 1. Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01
- 2. List of Regulatory Commitments cc: Southern Nuclear Operatingq Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. A. Lynch, Vice President - Farley Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley
Joseph M. Farley Nuclear Plant - Unit 1 Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01 Enclosure I Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01
Enclosure to NL-12-0498 Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01 NRC Position related to RMS Error Adjustment:
If twice the RMS error is not to be added to the depth of the measured flaw, the NRC staff requests that the licensee commit in their RAI response that flaw evaluations of any flaws found in the inspections covered by this relief request, FNP-ISI-RR-01 be submitted to the NRC for review and approval prior to reactor startup. When submitting the evaluation, in addition to the typical information provided in a flaw evaluation, the following additional information (described below) will need to be included.
SNC Response to NRC Position related to RMS Error Adiustment:
Southern Nuclear Operating Company (SNC) does not intend to use the staff proposed root mean square (RMS) error adjustment. SNC believes that the proposed adjustment is overly conservative. The RMS error adjustment requested in FNP-ISI-RR-01, when combined with the margins required for evaluating flaws, provides reasonable assurance of the continued structural integrity of the subject welds. SNC understands that an industry assessment regarding this issue is forthcoming and has reviewed the statistical results. While these results support the basis for the requested RMS error adjustment proposed in FNP-ISI-RR-01, the staff has not approved the assessment at this time. In lieu of using the staff proposed RMS error adjustment, SNC commits that flaw evaluations of any flaw found in the inspections covered by relief request FNP-ISI-01 will be submitted to the NRC for review and approval prior to Unit 1 Cycle 25 reactor startup, except as noted in the following responses.
NRC Additional Information Request No. I related to Measured Flaw Size:
The measured flaw size(s).
SNC Response to NRC Request No. 1 for Measured Flaw Size:
If flaws are found, the measured flaw size, as determined by Ultrasonic Testing (UT), will be included in the evaluation.
NRC Additional Information Request No. 2 related to RMS Error Adjustment Details:
The RMS error that was added to the measured flaw size and how the RMS error was established. The RMS depth-sizing error for the personnel conducting the examination. The licensee may propose a smaller addition (less than twice the RMS error) to the flaw depth. A smaller addition to the flaw depth will need to be technically justified, which should include, as a minimum, a demonstration that the welds are easier to inspect than the Performance Demonstration Initiative Supplement 10 ID specimens (e.g. no probe lift-off, less than 1/32 inch surface waviness) in the area near the flaw and the area used for depth-sizing. Smooth ID surfaces and other factors will be taken into account by NRC staff when reviewing the flaw evaluation.
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Enclosure to NL-12-0498 Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01 SNC Response to NRC Request No. 2 related to Proposed RMS Error Adjustment:
The obtained procedure RMS sizing error provided in this relief request is a more appropriate value to use for an evaluation of a flaw through-wall measurement. Providing the RMS value for a single analyst does not provide additional assurance on the accuracy of the measurement.
Each analyst, while not qualified in accordance with Supplement 10, has demonstrated a capability of sizing to the same secondary acceptance criteria that is used to judge the procedure's performance. Additionally, the data obtained to provide a through-wall depth measurement of reported flaws in the field is encoded and stored digitally. The data is essentially portable and can be sent easily to various analysts for concurrent flaw through-wall measurement evaluation. Subsequently, the reported size of a flaw is not determined by a single analyst; the data is reviewed by several analysts and potentially outside consultants prior to supplying a final through-wall measurement determination used in the flaw analysis.
In addition, the individual depth sizing error performance is not provided to the utility or the vendor by the administrator of the qualification program. What is provided is the RMS error for the procedure and a list of candidates who have met or exceeded the procedure's RMS error performance value. It is SNC's understanding that the individual performance information could be made available to the staff directly via the EPRI Performance Demonstration Initiative (PDI) administrator, provided confidentiality controls are maintained; however, it is not in the best interest of the industry to have the individual results disclosed to a utility, its vendor, or the public, as it could compromise the integrity of the qualification program.
In order to provide additional comparative information of the Joseph M. Farley Nuclear Plant (FNP) dissimilar metal welds (DMWs) to be examined to the mockup welds, under which the Supplement 10 qualification is conducted, the following was obtained from the PDI administrator:
Procedures and personnel are qualified on realistic mock-ups that contain both field weld and shop weld configurations. The shop weld configurations contain an 82/182 dissimilar metal weld (Supplement 10) connecting a stainless steel-clad ferritic nozzle forging to a stainless steel safe-end, which is then joined using austenitic metal material to either a wrought austenitic pipe or a cast austenitic elbow (Supplement 2 weld). The field weld configurations do not have safe-ends and connect the stainless steel-clad nozzle forging directly to either a wrought austenitic pipe or a cast austenitic elbow (Supplement 10 weld) using 82/182 weld material. The Supplement 2 and Supplement 10 field welds contain the most aggressive geometry and are considered the most challenging; however the location of these welds with relation to the relativity smooth shop weld also provide challenges to the techniques. There are a total of six welds included in the PDI qualifications. Four of these welds are field welds (two dissimilar metal welds and two Supplement 2 welds) with similar geometric conditions and two dissimilar metal weld shop welds, one with a relatively long safe-end and the other with short safe-end that brings the geometry from the field weld into the scan area.
Since the majority of the sample set is comprised of flaws that are contained in field weld configurations that have similar material and geometric conditions the grading approach currently defined in the 2008 Addenda of Appendix VIII, CC-696 and the PDI qualification program continues to be technically appropriate. Separating Supplement 2 measurements from the measurements made on similar weld configuration using the exact same E1-2
Enclosure to NL-12-0498 Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01 techniques makes the evaluation more granular and reduces the overall confidence in the capabilities of the technique.
Given that one-third of the six total Supplement 2 and 10 PDI qualification welds and one-half of the four total Supplement 10 PDI qualification welds are comparable to the FNP configuration, it is reasonable to conclude that sizing flaws in the DMWs for which this relief request was submitted are less challenging than sizing flaws in the combinations of geometries demonstrated in the PDI mockups.
In summary, SNC believes that the proposed adjustment to the depth size measurement can be technically justified for the range of conceivable flaws.
NRC Additional Information Request No. 3 related to Eddy Current Testing:
Ifthe procedure uses eddy current, the determination by eddy current ifthe flaw is or is not surface breaking.
SNC Response to NRC Request No. 3 related to Eddy Current Testing:
SNC will perform the required evaluations to determine if the flaw(s) are surface breaking or not.
In the case of the examinations planned for spring 2012, the contracted examination vendor will deploy eddy current in order to make these determinations.
NRC Additional Information Request No. 4 related to Inner Diameter Profile of the Examination Area:
The inner diameter profile of the weld, pipe, nozzle, and safe end (as applicable) in the region at and surrounding the transducer locations used to depth size the flaw.
SNC Response to NRC Request No. 4 related to Inner Diameter Profile of the Examination Area:
If a flaw is detected and depth sizing is required, this information will be collected and provided with the evaluation.
NRC Additional Information Request No. 5 related to the Flaw Degradation Mechanism:
The suspected flaw degradation mechanism and the process used to determine the degradation mechanism.
SNC Response to NRC Request No. 5 related to the Flaw Degradation Mechanism:
The initial nondestructive examination (NDE) data coupled with additional data collected will be used to aid in this determination and will be provided.
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Joseph M. Farley Nuclear Plant - Unit I Response to NRC RAI Dated February 23, 2012 Regarding Proposed Relief Request FNP-ISI-RR-01 Enclosure 2 List of Regulatory Commitments
List of Regulatory Commitments The following table identifies those actions committed by Southern Nuclear Operating Company in this document for Farley Nuclear Plant. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
Commitment Due Date / Event SNC commits that flaw evaluations of detected flaws Prior to Unit 1 determined to be connected to the piping inner diameter Cycle 25 reactor surface during the examinations covered by relief request FNP- startup ISI-01 will be submitted to the NRC for review and approval, except as described in NL-12-0498.
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