Letter Sequence RAI |
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MONTHYEARML13039A1312013-02-11011 February 2013 Request for Additional Information Related to Reactor Vessel Internals Inspection Plan Based on MRP-227-A Project stage: RAI ML13204A2122013-07-24024 July 2013 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15033A3852015-02-11011 February 2015 Request for Withholding Information Form Public Disclosure (TAC Nos ME9024, ME9025, and ME9026 Project stage: Withholding Request Acceptance ML15056A6662015-04-0707 April 2015 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML15050A6712015-06-19019 June 2015 Issuance of Amendments Regarding Inspection Plan for Reactor Vessel Internals Project stage: Approval 2015-02-11
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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
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 February 11, 2013 Mr. Preston Gillespie Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, REQUEST FOR ADDITIONAL INFORMATION RELATED TO REACTOR VESSEL INTERNALS INSPECTION PLAN BASED ON MRP-227-A (TAC NOS. ME9024, ME9025, AND ME9026)
Dear Mr. Gillespie:
By letter dated June 28, 2012, Duke Energy Carolinas, LLC submitted a license amendment request on the inspection plan for the reactor vessel internals (RVI) components at Oconee Nuclear Station (ONS), Units 1, 2, and 3 to the U.S. Nuclear Regulatory Commission (NRC) staff for review. This RVI inspection plan is based on MRP-227 -A, "Material Reliability Program:
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," and supersedes the previous inspection plan submitted on November 8,2010.
The 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). Please provide a response to these RAls within 45 days of the date of this letter.
If you have any questions, please call me at 301-415-2901.
Sincerely, o.~
~ hn P. Boska, Senior Project Manager lant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
RAI cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION (RAn REGARDING REACTOR VESSEL INTERNALS INSPECTION PLAN DUKE ENERGY CAROLINAS. LLC OCONEE NUCLEAR STATION. UNITS 1, 2. AND 3 DOCKET NOS. 50-269. 50-270. AND 50-287 By letter dated June 28, 2012, Agencywide Documents Access and Management System Accession Nos. ML12187A214 and ML12187A215, Duke Energy Carolinas, LLC (Duke Energy) submitted an inspection plan for the reactor vessel internals (RVI) components at Oconee Nuclear Station (ONS), Units 1, 2, and 3 to the U.S. Nuclear Regulatory Commission (NRC) staff for review. This RVI inspection plan is based on MRP-227 -A, "Material Reliability Program:
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," and supersedes the previous inspection plan submitted on November 8, 2010. The NRC staff is reviewing the submittal and has the following questions:
RAI-1
Topical Report Condition 7 of the NRC staff's safety evaluation (SE), Revision (Rev.) 1, dated December 16, 2011, on MRP-227-A, "Material Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," states: "MRP-227, Appendix A shall be updated to include ... the Operating Experience Summary." Appendix A of MRP-227-A discussed operating experience under various degradation mechanisms for the reactor vessel internals (RVI) components of all nuclear steam supply system (NSSS) designs, including Babcock and Wilcox (B&W) plants. Please (1) identify the MRP-227-A, Appendix A experience which were contributed by the Oconee Nuclear Station (ONS), Units 1, 2, and 3 and (2) provide ONS experience on RVI degradations that were not discussed in Appendix A of MRP-227-A.
RAI-2
Historically, the following materials used in the pressurized water reactor (PWR) RVI components were known to be susceptible to some of the aging degradation mechanisms that are identified in MRP-227-A. In this context, the NRC staff requests that the licensee confirm that these materials are not currently used in the RVI components at ONS.
(1) Nickel base alloys -lnconeI600; Weld Metals - Alloy 82 and 182 and Alloy X-750 (2) Stainless steel type 347 material (excluding baffle-former bolts)
(3) Precipitation hardened (PH) stainless steel materials 4 and 15-5 (4) Type 431 stainless steel material
2 If one or more of these materials were used in the RVI components at ONS, provide information regarding their proposed inspections and basis to demonstrate that the proposed inspections are consistent with the intent of MRP-227-A
RAI-3
Section 4.1.3.1 of ANP-2951, Rev. 2, "Inspection Plan for the Oconee Nuclear Station Units 1, 2, and 3 Reactor Vessel Internals," in Attachment 1 of the June 28, 2012, submittal identified transient cycle count assumptions for the replacement bolting as a time-limited aging analysis (TLAA). Confirm whether the replacement bolts are the lower thermal shield (LTS) bolts.
Regardless of the confirmation, will the MRP-227-A specified examination method, frequency, and coverage for this RVI component item coexist with the management of this TLAA? Identify all RVI component items which have plant-specific measures (e.g., TLAAs) to supplement or replace the MRP-227-A inspections. Provide justification if deviation from MRP-227-A is identified for some of these RVI component items.
RAI-4
Section 4.1.3.2 of ANP-2951, Rev. 2 states: "Section 6.5 of this report describes the resolution to Applicant/Licensee Action Item 6 from the SER concerning the justification of acceptability of inaccessible components."
Applicant/Licensee Action Item 6 of the SE for MRP-227 -A requires the applicant provide justification for the continued operability of each of the inaccessible components and, if necessary, provide a plan for the replacement of the components for NRC review and approval. To ensure that Applicant/Licensee Action Item 6 requirements will be completed in time to support the Oconee inspection plan, the NRC staff will impose Condition 1 to this SE requiring the licensee provide information requested in Applicant/Licensee Action Item 6 of the SE for MRP-227 -A:
This amendment requires the licensee provide the detailed analysis, replacement schedule, or justification for some other alternative process for:
- the core barrel cylinder and welds,
- the bolting (core barrel-to-former bolts, internal and external baffle-to-baffle (88) bolts, and associated locking devices),
by the end of one year from the initial inspection of the Primary or linked Primary component items if the inspection results indicate aging, which is the Implementation Date for this condition. Any "other alternative process" shall include justification of operation in the degraded condition on a generic or plant-specific basis.
In response to RAI-4, the licensee needs to indicate that it has reviewed Condition 1 and agrees with the imposition of it to the SE for this license amendment request (LAR).
3
RAI-5
Section 4.1.3.2 of ANP-2951, Rev. 2 states, "Section 6.6 of this report describes the resolution to Applicant/Licensee Action Item 7 from the SER concerning plant-specific analyses to demonstrate RV Internals components fabricated from CASS, martensitic stainless steel, or precipitation-hardened stainless steel will maintain their functionality during the period of extended operation."
Commitment No.4 in Attachment 2 of the June 28, 2012, submittal specified the due date for addressing Action Item 7 as November 29, 2013. Instead of using the proposed Commitment No.
4, the NRC staff will impose Condition 2 to this SE requiring the licensee provide information requested in Applicant/Licensee Action Item 7 of the SE for MRP-227-A:
This amendment requires the licensee provide the plant-specific analyses to demonstrate that B&W IMI guide tube assembly spiders and CRGT spacer castings will maintain their functionality during the period of extended operation by November 29,2013, which is the Implementation Date for this condition. These analyses shall consider loss of fracture toughness due to thermal and irradiation embrittlement, and may also need to consider limitations on accessibility for inspection and the resolution/sensibility of the inspection techniques.
In response to RAI-5, the licensee needs to justify that the proposed date of November 29, 2013, is appropriate and to indicate that it has reviewed Condition 2 and agrees with the imposition of it to the SE for this LAR.
RAI-6
Section 4.1.6 of ANP-2951, Rev. 2 states that, "The "Primary" requirement from MRP-227-A for a one-time physical measurement of the interference fit between the plenum cover weldment rib pads and the RV flange was performed at ONS between 2006 and 2008 in order to provide data to the investigation." Discuss the impact of these measurements on the MRP-227-A specified subsequent visual (VT-3) examination on the 10-year inservice inspection (lSI) interval for ONS, Units 1, 2, and 3.
RAI-7
Section 4.2 of ANP-2951, Rev. 2 states that, "visual examination of baffle-to-baffle and baffle-to-former bolts at each RFO [refueling outage]." Confirm that Duke Energy will perform ultrasonic testing (UT) examinations for baffle-to-baffle and baffle-to-former bolts in accordance with Examination Method/Frequency of MRP-227 -A, and the stated visual examinations simply supplement the UT examinations. Justify if this is not the case.
RAI-8
Table 4-2 of ANP-2951, Rev. 2 defined "typical" ONS core support structure components for Examination Category B-N-3 of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code (ASME Code),Section XI. Describe the process and effort in making Table 4-2 to ensure that Table 4-2 did not miss any important core support structure components. Identify the
4 ONS core support structure components which were inspected as B-N-3 Examination Category in the past but are not included in Table 4-2 and provide justification, including past inspection results, for their exclusion.
RAI-9
Section 4.2.5 of ANP-2951, Rev. 2 states that, "Failure of the original Alloy A-286 LTS bolts in the 1980s led to the replacement of all the original LTS bolts with replacement studs/nuts at the three ONS units." The replacement studs/nuts are made from Alloy X-750 in the high temperature heat-treatment condition. Discuss the inspection results accumulated in the past 30 years at the three ONS units for the replacement LTS bolts to demonstrate that this operating experience supports the MRP-227 -A specified examination method/frequency/coverage for this RVI component item.
RAI-10
Section 4.2.6 of ANP-2951, Rev. 2 states that, "The Alloy X-750 dowels, Type 304 screws, and their locking welds [related to plenum cover ribs for ONS, Unit 1 only] were unknown and were not screened for aging degradation mechanisms, nor evaluated for inclusion in MRP-227." Confirm that this RVI component item is within the scope of the LR in accordance with 10 CFR 54.4 and will be included in your response to address Applicant/Licensee Action Item 2 of the SE for MRP-227-A regarding whether Tables 4-1 and 4-2 in MRP-189, Rev. 1 and Tables 4-4 and 4-5 in MRP-191 have missed any RVI component items that should be within the scope of the LR.
RAI-11
Section 4.2.7 of ANP-2951, Rev. 2 states that, "UT examinations for the LCB [lower core barrel]
bolts are planned during the RV Internals inspections in 2012,2013, and 2014, in compliance with the MRP-227-A examinations requirement for the LCB bolts." Provide similar information on examinations of all kinds (i.e., visual or UT) for all other RVI component items to be performed before the end of the current 40-year license in compliance with the MRP-227 -A examinations requirement.
RAI-12
Section 5.1.1 of ANP-2951, Rev. 2 states that, "See Section 2.4 of this report for a discussion of the scope of the components considered for inspection for the program to manage the aging of the ONS RV Internals." The NRC staff reviewed Section 2.4 and did notfind a clear definition of the scope of the components. Hence, the NRC staff requested the licensee confirm that the ONS RVI inspection plan includes all RVI component items listed in Tables 4-1 (Primary) and 4-4 (Expansion) of MRP-227-A and those listed in Table 4-2 (Existing) of ANP-2951, Rev. 2. If it is not confirmed, demonstrate that the ONS RVI inspection plan is still appropriate.
RAI-13
Section 6.3 of ANP-2951, Rev. 2 discussed Applicant/Licensee Action Item 2 of the SE for MRP-227-A regarding whether Tables 4-1 and 4-2 in MRP-189, Rev. 1 and Tables 4-4 and 4-5 in MRP-191 have missed any RVI components that should be within the scope of the LR to support
5 the current review. Commitment No.1 in Attachment 2 of the June 28,2012, submittal specified the due date for addressing Action Item 2 as May 31,2013. Please provide this information in response to this RAI, as the NRC staff needs it in order to make a decision on this license amendment.
RAI-14
Section 6.4 of ANP-2951, Rev. 2 discussed Applicant/Licensee Action Item 4 of the SE for MRP-227-A regarding whether the core support structure upper flange weld was stress relieved during the original fabrication of the RV in order to determine whether this RVI component item should be revised from Expansion Category to Primary Category. Commitment No.2 specified the due date for addressing Action Item 4 as February 29, 2013. Please provide this information in response to this RAI, as the NRC staff needs it in order to make a decision on this license amendment.
RAI-15
Section 2.5 of Appendix 0 of ANP-2951, Rev. 2 indicated that an operability assessment considering UT results and future LCB bolt failure was performed for Arkansas Nuclear One, Unit 1 (ANO-1). This section also revealed the technical elements addressed in this ANO-1 operability assessment. Confirm that if relevant conditions have been identified in the UCB or LCB bolts at any of the ONS units, an operability evaluation required by WCAP-17096, Rev. 2 will be performed consistent with the ANO-1 operability assessment and provided to NRC for review. To support evaluation of this potential future operability assessment, Reference 14 regarding minimum number of bolts required for operation shall also be provided at that time.
ML13039A131 *See memo OFFICE NRR/lPl2*1IPM NRRllPl2-lILA NRR/EVIB/BC* NRR/lPl2-1/BC NRR/lPl2-lIPM NAME JBoska SFigueroa SRosenberg RPascarelli JBoska DATE 2/11/13 2/11/13q 11/1/12 2111113 2/11113