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| | issue date = 06/21/2013 | | | issue date = 06/21/2013 |
| | title = Request for Additional Information Regarding Amendment Application Related to Reactor Coolant System Pressure and Temperature Limit Curves (TAC Nos. MF0763, MF0764, and MF0765) | | | title = Request for Additional Information Regarding Amendment Application Related to Reactor Coolant System Pressure and Temperature Limit Curves (TAC Nos. MF0763, MF0764, and MF0765) |
| | author name = Boska J P | | | author name = Boska J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Batson S | | | addressee name = Batson S |
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| | docket = 05000269, 05000270, 05000287 | | | docket = 05000269, 05000270, 05000287 |
| | license number = DPR-038, DPR-047, DPR-055 | | | license number = DPR-038, DPR-047, DPR-055 |
| | contact person = Boska J P, NRR/DORL/LPLII-1, 415-2901 | | | contact person = Boska J, NRR/DORL/LPLII-1, 415-2901 |
| | case reference number = TAC MF0763, TAC MF0764, TAC MF0765 | | | case reference number = TAC MF0763, TAC MF0764, TAC MF0765 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| By letter dated February 22,2013, Duke Energy Carolinas, LLC (Duke), submitted an application for a proposed amendment for the Oconee Nuclear Station, Units 1,2, and 3, which would revise the Technical Specifications for the Reactor Coolant System pressure-temperature limit curves. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). On June 10, 2013, the Duke staff indicated that a response to the RAI would be provided within 60 days of the date of this letter. If you have any questions, please call me at 301-415-2901. | | By letter dated February 22,2013, Duke Energy Carolinas, LLC (Duke), submitted an application for a proposed amendment for the Oconee Nuclear Station, Units 1,2, and 3, which would revise the Technical Specifications for the Reactor Coolant System pressure-temperature limit curves. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). On June 10, 2013, the Duke staff indicated that a response to the RAI would be provided within 60 days of the date of this letter. If you have any questions, please call me at 301-415-2901. |
| Sincerely, CJ:; | | Sincerely, CJ:; |
| Manager Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING TECHNICAL SPECIFICATION CHANGE REQUEST FOR PRESSURE-TEMPERATURE LIMIT CURVES DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1,2, AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287 Sy letter dated February 22,2013, Agencywide Documents Access and Management System Accession No. ML 130580060, Duke Energy Carolinas, LLC (Duke), submitted an application for a proposed amendment for the Oconee Nuclear Station, Units 1, 2, and 3, which would revise the Technical Specifications for the Reactor Coolant System pressure-temperature limit curves. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following questions: | | Manager Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING TECHNICAL SPECIFICATION CHANGE REQUEST FOR PRESSURE-TEMPERATURE LIMIT CURVES DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1,2, AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287 Sy letter dated February 22,2013, Agencywide Documents Access and Management System Accession No. ML130580060, Duke Energy Carolinas, LLC (Duke), submitted an application for a proposed amendment for the Oconee Nuclear Station, Units 1, 2, and 3, which would revise the Technical Specifications for the Reactor Coolant System pressure-temperature limit curves. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following questions: |
| RAI-1 (generic) | | RAI-1 (generic) |
| Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, Paragraph IV.A states that, "The pressure-retaining components of the reactor coolant pressure boundary [RCPBJ that are made of fem'tic materials must meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code [ASME Code, Section IIIJ, supplemented by the additional requirements set forth ... [in paragraph IV.A.2, "Pressure-Temperature (P-T) Limits and Minimum Temperature Requirements"]." Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the ferritic materials in the reactor vessel (RV) beltline (neutron fluence 1 x 10 17 n/cm 2 , E> 1 MeV), as well as ferritic materials not in the RV beltline (neutron fluence < 1 x 10 17 n/cm 2 , E> 1 MeV). Further, 10 CFR Part 50, Appendix G requires that all RCPS components must meet the American Society of Mechanical Engineers Code (ASIVIE Code), Section III requirements. | | Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, Paragraph IV.A states that, "The pressure-retaining components of the reactor coolant pressure boundary [RCPBJ that are made of fem'tic materials must meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code [ASME Code, Section IIIJ, supplemented by the additional requirements set forth ... [in paragraph IV.A.2, "Pressure-Temperature (P-T) Limits and Minimum Temperature Requirements"]." Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the ferritic materials in the reactor vessel (RV) beltline (neutron fluence 1 x 10 17 n/cm 2 , E> 1 MeV), as well as ferritic materials not in the RV beltline (neutron fluence < 1 x 10 17 n/cm 2 , E> 1 MeV). Further, 10 CFR Part 50, Appendix G requires that all RCPS components must meet the American Society of Mechanical Engineers Code (ASIVIE Code), Section III requirements. |
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MONTHYEARML13058A0592013-02-22022 February 2013 Licesne Amendment Request to Update Pressure-Temperature Limit Curves No. 2012-10 Project stage: Other ML13165A1472013-06-21021 June 2013 Request for Additional Information Regarding Amendment Application Related to Reactor Coolant System Pressure and Temperature Limit Curves Project stage: RAI ML13259A1202013-09-10010 September 2013 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 1 Project stage: Supplement ONS-2013-016, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 22013-10-25025 October 2013 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 2 Project stage: Supplement ML13322B2762013-11-14014 November 2013 11/14/13 e-mail from B.Shingleton to R.Guzman PT Curves LAR Supplement 2 - ONS Unit 3 Lower Nozzle Belt Forging Reported in ANP-3127, Revision 2 Project stage: Supplement ML13305A1222013-11-25025 November 2013 Enclosure 3 - Areva Document No. 32-9212003-000, Lst Considering RCS Piping and RVCH Limit for B&W Plant Designs, September 2012 Project stage: Request ONS-2013-023, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 32013-11-29029 November 2013 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10, Supplement 3 Project stage: Supplement ML13342A0022013-12-0505 December 2013 12/5/13 E-mail from R.Guzman to B.Shingleton - Follow-up RAI to Pressure Temperature Curve LAR Supplement 3, Oconee Nuclear Station Units 1, 2, and 3 (TAC Nos. MF0763/64/65) Project stage: RAI ML13350A0982013-12-16016 December 2013 E-mail from B.Shingleton to R.Guzman Clarification of Upper Shelf Energy Values for ONS Pressure-Temperature Curve 54 EFPY LAR Project stage: Other ML14028A4822014-01-31031 January 2014 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML14041A0932014-02-27027 February 2014 Issuance of Amendments Regarding Revised Pressure-Temperature Limits Project stage: Approval 2013-12-05
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Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22234A0062022-08-30030 August 2022 SLRA - Closed Public Meeting Summary - August 18, 2022 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23284A3322023-10-11011 October 2023 Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060) ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23156A2452023-06-0505 June 2023 Audit Summary and RAI-RCI - Revised Enclosure ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23095A0052023-04-0404 April 2023 002 Radiation Safety Baseline Inspection Information Request ML23086C0362023-03-27027 March 2023 Request for Additional Information Steam Generator Tube Inspection Report (03R31) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23038A1832023-02-0707 February 2023 Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752 ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final ML22251A2902022-09-0808 September 2022 Request for Additional Information Additional Mode Change Limitations Applicable to the Adoption of Technical Specifications Tasks Force Traveler (TSTF) No. 359, Revision 9 ML22234A0052022-08-30030 August 2022 SLRA - Feedback for RAI B2.1.7-4a to Duke - August 16, 2022 ML22157A0042022-06-0606 June 2022 10 CFR 50.59 Inspection Initial Information Request ML22157A0012022-06-0101 June 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Additional NRC Comments on RAI 4.6.1-1a ML22154A2122022-06-0101 June 2022 SLRA - 2nd Round RAI B2.1.7-4b ML22124A1632022-05-0303 May 2022 (Public) Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22124A1612022-05-0303 May 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22122A0182022-04-28028 April 2022 Attachment: Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A0192022-04-28028 April 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A1312022-04-27027 April 2022 (Public) Oconee SLRA - 2nd Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.6 Redacted ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22113A0092022-04-20020 April 2022 Attachment: Oconee SLRA - Final RAI 3.1.2-1 ML22112A0072022-04-20020 April 2022 Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Confirmation of Information 3.5.2.2.2.6-L ML22081A0062022-03-21021 March 2022 Attachment: Oconee SLRA - 2nd Round RAI B4.1-3 ML22081A0052022-03-21021 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B4.1-3 ML22080A0772022-03-16016 March 2022 SLRA - RAI Set 4 (2nd Round Rais) ML22069A0012022-03-0808 March 2022 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 4 ML22063A4502022-03-0404 March 2022 Request for Additional Information Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump RA-22-0036, Responses to NRC Request for Additional Information Set 22022-02-14014 February 2022 Responses to NRC Request for Additional Information Set 2 ML22019A1042022-01-18018 January 2022 Attachment: Oconee SLRA - Final Requests for Additional Information - Set 3 ML22019A2442022-01-18018 January 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000269/2022010, 05000270/2022010, 05000287/2022010) and Request for Information (RFI) ML22019A1032022-01-18018 January 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 3 ML22012A0422022-01-11011 January 2022 SLRA - Final Requests for Additional Information - Set 2 ML22010A1132022-01-0505 January 2022 SLRA - RCIs - Set 3 ML21333A0392021-11-29029 November 2021 RP Inspection Document Request ML21330A0192021-11-23023 November 2021 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 2 ML21327A2782021-11-23023 November 2021 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Final RAIs (Set 1 and 2nd Round RAI B2.1.27-1a) ML21327A2792021-11-23023 November 2021 SLRA - Final Requests for Additional Information - Set 1 ML21327A2802021-11-23023 November 2021 SLRA - Final 2nd Round RAI - RAI B2.1.27-1a ML21313A2342021-11-0404 November 2021 Attachment: Oconee SLRA - Final Requests for Confirmation of Information - Set 1 ML21274A0682021-10-0101 October 2021 Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria ML21273A0492021-09-30030 September 2021 Request for Additional Information Alternative Request (ON-RPI-OMN-28) to Use Code Case OMN-28 ML21271A5892021-09-28028 September 2021 SLRA - RAI B2.1.27-1 (Draft) ML21271A5902021-09-28028 September 2021 SLRA - RAI B2.1.27-1 (Final) ML21271A5882021-09-22022 September 2021 SLRA - Request for Additional Information B2.1.27-1 - Email from Angela Wu (NRC) to Steve Snider (Duke) ML21217A1912021-08-0505 August 2021 Request for Additional Information Alternative Request (RA-20-0334) Regarding Use of an Alternative to the ASME Code Case N-853 Acceptance Criteria ML21190A0172021-07-0808 July 2021 NRR E-mail Capture - Oconee Nuclear Station, Units 1, 2, and 3 - Request for Additional Information Alternative for ISI RPV Weld Examination from 10 to 20 Years (EPID-L-2021-LLR-0004) ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) 2023-07-03
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555"()001 June 21, 2013 Mr. Scott Batson Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752 OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION RELATED TO REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMIT CURVES (TAC NOS. MF0763, MF0764, AND MF0765)
Dear Mr. Batson:
By letter dated February 22,2013, Duke Energy Carolinas, LLC (Duke), submitted an application for a proposed amendment for the Oconee Nuclear Station, Units 1,2, and 3, which would revise the Technical Specifications for the Reactor Coolant System pressure-temperature limit curves. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). On June 10, 2013, the Duke staff indicated that a response to the RAI would be provided within 60 days of the date of this letter. If you have any questions, please call me at 301-415-2901.
Sincerely, CJ:;
Manager Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING TECHNICAL SPECIFICATION CHANGE REQUEST FOR PRESSURE-TEMPERATURE LIMIT CURVES DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1,2, AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287 Sy letter dated February 22,2013, Agencywide Documents Access and Management System Accession No. ML130580060, Duke Energy Carolinas, LLC (Duke), submitted an application for a proposed amendment for the Oconee Nuclear Station, Units 1, 2, and 3, which would revise the Technical Specifications for the Reactor Coolant System pressure-temperature limit curves. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following questions:
RAI-1 (generic)
Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G, Paragraph IV.A states that, "The pressure-retaining components of the reactor coolant pressure boundary [RCPBJ that are made of fem'tic materials must meet the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code [ASME Code, Section IIIJ, supplemented by the additional requirements set forth ... [in paragraph IV.A.2, "Pressure-Temperature (P-T) Limits and Minimum Temperature Requirements"]." Therefore, 10 CFR Part 50, Appendix G requires that P-T limits be developed for the ferritic materials in the reactor vessel (RV) beltline (neutron fluence 1 x 10 17 n/cm 2 , E> 1 MeV), as well as ferritic materials not in the RV beltline (neutron fluence < 1 x 10 17 n/cm 2 , E> 1 MeV). Further, 10 CFR Part 50, Appendix G requires that all RCPS components must meet the American Society of Mechanical Engineers Code (ASIVIE Code),Section III requirements.
The relevant ASME Code,Section III requirement that will affect the P-T limits is the lowest service temperature requirement for all reactor coolant pressure boundary (RCPB) components specified in Section III, NB-2332(b).
The P-T limit calculations for ferritic RCPS components that are not RV beltline shell materials may define P-T curves that are more limiting than those calculated for the RV beltline shell materials due to the following factors: RV nozzles, penetrations, and other discontinuities have complex geometries that may exhibit significantly higher stresses than those for the RV beltline shell region. These higher stresses can potentially result in more restrictive P-T limits, even if the reference temperature (RT NDT) for these components is not as high as that of RV beltline shell materials that have simpler geometries. Ferritic RCPS components that are not part of the RV may have initial RT NDT values, which may define a more restrictive lowest operating temperature in the P-T limits than those for the RV beltline shell materials.
Enclosure
-2 Consequently, please describe how the current P-T limit curves at 54 effective full power years (EFPY) for the Oconee units and the methodology used to develop these curves considered all RV materials (beltline and non-beltline) and the lowest service temperature of all ferritic RCPB materials, consistent with the requirements of 10 CFR Part 50, Appendix G in the proposed update. Your description shall include the following: Using a proposed composite heatup curve and a proposed cooldown curve as examples, point out the segments that were limited by closure head, outer nozzle, and beltline. Confirm availability of material data (initial RT NOT and copper and nickel contents) for all non-beltline materials for all three unit RPVs and demonstrate that none of them will become limiting under the 54 EFPY fluence. Confirm that the lowest service temperatures (LSTs) for all Ferritic RCPB components that are not part of the RV have been established for all three Oconee units, and the lowest temperature of 60 OF in the proposed P-T limits are higher than these LSTs. RAI-2 The fluence values at the one-quarter thickness (1/4T) and 3/4T of the RV in Table 3-1 of ANP-3127, Revision 1 (the ANP, Enclosure 2 of the February 22, 2013, submittal) appear to not be based on the same RV thickness for the same unit. Please confirm that you used Equation (3) in Regulatory Guide (RG) 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," to calculate the fluence at 1/4T and 3/4T of the RV. Please also provide the values that you used for "x" in Equation (3) in the ART calculations at 1/4T and 3/4T for the limiting materials shown in Table 3-1 and the RV radius that you used in the P-T limit calculations.
Provide the same information for Units 2 and 3. RAI-3 Table 3-2 of the ANP indicated that the copper value of the lower nozzle belt to the upper shell circumferential weld of Heat 406L44 for Unit 2 is 0.27% and for the same type of weld of Heat 821T44 for Unit 3 is 0.24%, both are 0.01% lowerthan the corresponding values in the approved license renewal application.
Since the accumulative effect of several small changes over the years can be significant, please provide justification for the revision.
RAI-4 Section 4.2 of the ANP states that, "A % tNB (tNB -the thickness at the nozzle belt) deep corner flaw is postulated on the inside surface of the reactor vessel inlet and outlet nozzles and core flood nozzle corner." This suggests that your nozzle methodology is more complete than that of BAW-10046, Revision 2, which performed analysis on outlet nozzles only, based on the belief that the outlet nozzle is the most limiting nozzle. Please confirm that actual calculations have been performed on inlet, outlet, and core flood nozzles to determine the most limiting P-T limits for nozzles in this license amendment request (LAR).
Section 4.4 of the ANP states, "The Pressure-Temperature limits derived for the reactor vessel head-to-flange conservatively bounds the minimum required temperature requirements as given in Table 1 of the Appendix G to 10 CFR Part 50." Please use a figure from Figure 7-1 to Figure 7-9 to support and explain this statement.
RAI-6 Section 4.6 of the ANP indicated that both ramped and stepped transient definitions are modeled for normal operation heatup and cooldown.
Please confirm whether the thermal stresses are based on (1) the stepped transient, which is likely to be limiting, or (2) the stepped and the ramped transients depending on time. If Case (2) applies, please provide a discussion of why the stepped transient may not be limiting.
RAI-7 Section 6 of the ANP discussed pressure corrections with the LlP listed in Table 6-1. Please confirm whether this LlP should be added to or subtracted from the calculated pressure values based on the ASME Code,Section XI, Appendix G methodology.
Likewise, how do you adjust the calculated 1/4T metal temperature to the "indicated reactor coolant system (RCS) inlet temperature?" RAI-8 Figures 7-1 and 7-2 of the ANP illustrate the P-T limits for heatup and cooldown, along with pressure temperature pairs of typical pOints along the P-T limit curves (on the left side of Figures 7-1 and 7-2). To assist the NRC staff verify the proposed heatup and cooldown curves, please use these pressure temperature pairs as examples and provide the corresponding thermal stress intensity factors (KitS).
June 21, 2013 Mr. Scott Batson Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752 OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION RELATED TO REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMIT CURVES (TAC NOS. MF0763, MF0764, AND MF0765)
Dear Mr. Batson:
By letter dated February 22,2013, Duke Energy Carolinas, LLC (Duke), submitted an application for a proposed amendment for the Oconee Nuclear Station, Units 1, 2, and 3, which would revise the Technical Specifications for the Reactor Coolant System pressure-temperature limit curves. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). On June 10, 2013, the Duke staff indicated that a response to the RAI would be provided within 60 days of the date of this letter. If you have any questions, please call me at 301-415-2901.
Sincerely, IRA! John P. Boska, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsAcrsAcnw_MailCtr Resource RidsNrrDorlDpr Resource LPLlI-1 RlF RidsNrrLASFigueroa Resource RidsNrrDorlLp2-1 Resource RidsNrrPMOconee RidsRgn2MailCenter Resource RidsNrrDeEvib SSheng ADAMS Accession No.: ML13165A147
- See memo dated 5/30/13 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/EVIB/BC*
NRR/LPL2-1/BC NRR/LPL2-1/PM NAME ,IBoska SFigueroa SRosenberg RPascarelii ,IBoska DATE 6/17113 6/19/13 5/30/13 6/21113 6/21/13 OFFICIAL RECORD COpy