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MONTHYEARML12278A3992012-08-31031 August 2012 WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant Project stage: Request RNP-RA/12-0100, Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals2012-09-26026 September 2012 Review Request for the PWR Vessel Internals Program Plan for Aging Management of Reactor Internals Project stage: Request ML12307A4082012-11-0202 November 2012 NRR E-mail Capture - Acceptance Review for the PWR Rector Vessel Internals Program Plan for Aging Management for H.B. Robinson Steam Electric Plant Unit No. 2 Project stage: Acceptance Review ML13079A2932013-03-27027 March 2013 Request for Additional Information Related to the Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals Project stage: RAI RNP-RA/13-0053, Response to NRC Request for Additional Information Related to Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals2013-05-23023 May 2013 Response to NRC Request for Additional Information Related to Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML13135A1842013-05-29029 May 2013 Request for Additional Information Related to the Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals Project stage: RAI RNP-RA/13-0073, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2013-07-25025 July 2013 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML13240A4992013-08-27027 August 2013 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Requests for Additional Information (Rais) Project stage: RAI ML13249A0002013-09-0505 September 2013 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Requests for Additional Information (Rais) (TAC No. ME9633) - Correction to RAI-3-3 Project stage: RAI ML13266A2402013-09-23023 September 2013 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Revised Requests for Additional Information (Rais) Project stage: RAI ML14016A2792014-01-0808 January 2014 NRR E-mail Capture - Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Request for Additional Information (Rais) Project stage: RAI RNP-RA/13-0134, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2014-01-0909 January 2014 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI RNP-RA/14-0028, Response to NRC Request for Additional Information Re Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2014-02-19019 February 2014 Response to NRC Request for Additional Information Re Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML14115A4402014-04-24024 April 2014 NRR E-mail Capture - H. B. Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Request for Additional Information (Rais) Project stage: RAI ML14167A3452014-06-16016 June 2014 NRR E-mail Capture - H. B. Robinson MRP-227-A RAI Status Project stage: RAI RNP-RA/14-0097, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2014-09-0505 September 2014 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML15009A2842015-01-22022 January 2015 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance RNP-RA/16-0011, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML16063A1032016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI ML16280A2002016-10-0505 October 2016 Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Response to RAI RNP-RA/17-0042, Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2017-06-29029 June 2017 Submittal of the PWROG-14048-P, Revision 1, to Satisfy the Regulatory Commitment Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals Project stage: Other 2013-09-05
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Category:E-Mail
MONTHYEARML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Duke'S August 20, 2023, License Amendment Request for Robinson, Unit 2 ML23262B4502023-09-19019 September 2023 NRR E-mail Capture - H. B. Robinson Steam Electric Plant, Unit 2 - Acceptance of License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures Based on Leak-Before-Break Methodology ML23220A2342023-08-0808 August 2023 NRR E-mail Capture - Robinson, Unit 2 - Acceptance Review Results for Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies 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) ML23131A4192023-05-10010 May 2023 003 Radiation Safety Baseline Inspection Information Request ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML23011A0152023-01-11011 January 2023 NRR E-mail Capture - Request for Additional Information to Duke'S Request for Robinson to Add Feedwater Isolation Function to TS 3.3.2 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML22285A1552022-10-12012 October 2022 NRR E-mail Capture - H. B. Robinson, Unit 2 - Acceptance of License Amendment Request Regarding the Addition of Feedwater Isolation Function to TS 3.3.2 and Removal of Obsolete Content from TS 2.1.1.1 and TS 5.6.5.b ML22222A1082022-08-10010 August 2022 NRR E-mail Capture - Request for Additional Information Regarding Duke'S Request to Remove 4.160 Kv Bus 2 from Surveillance Requirement 3.8.1.16 ML22146A3652022-05-25025 May 2022 Acceptance of Requested Licensing Action License Amendment Request for Application to Revise Surveillance Requirement 3.8.1.16 ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 ML22080A0042022-03-18018 March 2022 Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22012A3662022-01-12012 January 2022 Acceptance of Requested Licensing Action License Amendment Re2uest for Application to Revise Technical Specification to Adopt TSTF-577, Revised Frequencies for Steam Generating Tube Inspections ML22005A0872022-01-0505 January 2022 Acceptance of Requested Licensing Action Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21295A2992021-10-22022 October 2021 Document Request for Robinson Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021004 ML21286A6612021-10-13013 October 2021 Acceptance for Review of Proposed Alternative ISI-05-017 for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21119A2272021-04-29029 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-9, EPID: L-2021-LLR-0024 ML21116A2592021-04-26026 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-8, EPID: L-2021-LLR-0023 ML21116A2582021-04-26026 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-3, EPID: L-2021-LLR-0020 ML21113A1312021-04-23023 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-5, EPID: L-2021-LLR-0021 ML21110A1462021-04-20020 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results: IST-RR-7, EPID: L-2021-LLR-0022 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20353A1302020-12-18018 December 2020 2021 Hbr 50.59 Info Request - E-mail Request- Upcoming 50.59 Inspection (IP71111.17T)- Week of March 1-5, 2021 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) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20063M1942020-02-21021 February 2020 NRR E-mail Capture - Accepted for Review - Robinson Unit 2 One-Time Pressure Relief Valve Test Frequency Extension EPID: L-2020-LLR-0019 ML20085F9312020-02-20020 February 2020 SPRA - Spr Audit Questions - 2nd Batch ML20049A0342020-02-16016 February 2020 NRR E-mail Capture - Accepted for Review - Robinson Unit 2 to Correct Administrative Renewed Facility Operating License Error in the 50.69 LAR EPID: L-2020-LLL-0000 ML20063L4562020-02-0404 February 2020 NRR E-mail Capture - RAI - Robinson Relief Req Rx Vessel Cold Leg Nozzle Dissimilar Meter Butt Weld Inspection Interval EPID L-2019-LLR-0072 ML20087N6632020-02-0303 February 2020 SPRA - Spr Audit Questions Redacted ML20027C2042020-01-27027 January 2020 Audit Documents Needed for the Robinson Seismic Probabilistic Risk Assessment Review - FLEX and HRA References ML20015A1892020-01-13013 January 2020 Audit Documents Needed for the Robinson SPRA Review - Fragility Analysis ML20009C0922020-01-0808 January 2020 Audit Documents Needed for the Robinson SPRA Review - Seismic Hazard Analysis ML19365A0482019-12-30030 December 2019 Request for Eportal Access for Audit Review of the Robinson SPRA Supporting Documents ML19365A0462019-12-18018 December 2019 Audit Documents Needed for the Robinson SPRA Review ML19288A2942019-10-15015 October 2019 NRR E-mail Capture - RAIs for Robinson Revision to RPV Surveillance Program Withdrawal Schedule ML19283A0372019-09-26026 September 2019 Draft Requests for Additional Information for H.B. Robinson LAR to Revise TS 3.8.2, AC Sources - Shutdown, SR 3.8.2.1 ML19235A1202019-08-21021 August 2019 Acceptance Review for Robinson LAR to Add Feedwater Bypass Valve to TS 3.7.3 (L-2019-LLA-0170) 2024-01-02
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NRR-PMDAPEm Resource From: Lingam, Siva Sent: Tuesday, August 27, 2013 10:36 AM To: richard.hightower@pgnmail.com Cc: Broaddus, Doug; Rosenberg, Stacey; Cheruvenki, Ganesh; Alexander, Donna (Donna.Alexander@duke-energy.com)
Subject:
Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management - Requests for Additional Information (RAIs) (TAC No. ME9633)
Please note the following official RAIs for the subject matter. Please provide your responses as early as possible.
REQUEST FOR ADDITIONAL INFORMATION ON AGING MANAGEMENT PROGRAM FOR THE REACTOR VESSEL INTERNALS AT H. R. ROBINSON STEAM ELECTRIC PLANT, UNIT 2 PROGRESS ENERGY INC.
DOCKET NUMBER 50-261 By letter dated September 26, 2012 (Agencywide Documents Access and Management (ADAMS) Accession No. ML12278A398), as supplemented by letters dated May 23, 2013 (ADAMS Accession No. ML13156A144) and July 25, 2013 (ADAMS Accession No. ML13219A252), Carolina Power and light Company (currently known as Duke Energy Progress, inc.) (the licensee), submitted an aging management program (AMP) for the reactor vessel internals (RVI) at H.B. Robinson Steam Electric Plant, also known as Robinson Nuclear plant (RNP). The Materials Reliability Program (MRP)-227-A report, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, (ADAMS Accession No. ML120170453) and its supporting reports were used as technical bases for developing Robinsons AMP. The Nuclear Regulatory Commission (NRC) staff reviewed this report and issued a final safety evaluation (SE) on December 16, 2011 (ADAMS Accession No. ML11334A009). The NRC staff has developed a third set of RAIs as addressed below, and it includes issues related to Action Item 1 of the staffs SE for the MRP-227-A.
RAI-3-1 (Action Item 1 of the NRC staffs SE for MRP-227-A):
The NRC staff and EPRI met on November 28, 2012 (ADAMS Accession No. ML13014A672), January 22-23, 2013 (ADAMS Accession No. ML13042A048), and February 25, 2013 (ADAMS Accession No. ML13067A262) to facilitate development of a generic approach for resolution of Applicant/Licensee Action Item 1. As discussed in References 1 and 2, the NRC staff requests the licensee to provide the following information related to verification of the applicability of MRP-227-A to RNP. This is the initial RAI for Action Item 1.
- 1. Do the RNP RVI have non-weld or bolting austenitic stainless steel components with 20% cold work or greater, and if so do the affected components have operating stresses greater than 30 ksi? If so, perform a plant-specific evaluation to determine the aging management requirements for the affected components.
- 2. Have RNP ever utilized atypical fuel design or fuel management that could make the assumptions of MRP-227-A regarding core loading/core design non-representative for that plant, including power changes/uprates? If so, describe how the differences were reconciled with the assumptions of MRP-227-A or provide a plant-specific aging management program for affected components as appropriate.
RAI-3-2: In response to staffs RAI-5 (a) dated March 27, 2013 (ADAMS Accession No. ML13079A293), the licensee, by a letter dated May 23, 2013, provided a response which addresses the issue related to neutron embrittlement and irradiation induced stress corrosion cracking in cast austenitic stainless steel (CASS) lower support column bodies at RNP. The licensee stated that plant-specific acceptance criteria, WCAP-17254-P, were developed by Westinghouse and the acceptance criteria will demonstrate functionality of the CASS lower 1
support column bodies at RNP. MRP-227-A, Section 4.2.7, requires the plant-specific analysis for Licensee Action Item 7 demonstrating that the lower support column bodies will maintain their functionality during the period of extended operation (PEO) to be submitted along with a licensees submittal to apply the approved version of MRP-227. This analysis was not provided with the licensees submittal of the RVI Inspection Plan for RNP. Therefore, the NRC staff requests that the licensee submit WCAP-17254-P as part of the RVI AMP, for review and approval. Without an approved analysis, the NRC staff would not have reasonable assurance of the functionality of the lower support columns for the PEO. Therefore, the NRC staff requests the licensee to inspect the lower support column bodies during the initial inspections if WCAP-17254-P showed that these lower support column bodies (expansion components) could not maintain their intended function during PEO, or if the staff could not review and approve the analysis prior to the initial inspections of the relevant primary components.
RAI-3-3: In its response to the NRC staffs RAI-3, dated March 27, 2013, the licensee by a letter dated May 23, 2013, stated that Alloy X-750 material that is used for clevis insert bolts did not receive high temperature heat treatment (HTH) and, therefore, this material might be susceptible to primary water stress corrosion cracking (PWSCC). Appendix A to MRP-227-A indicates that failures of Alloy X-750 clevis insert bolts were reported by one Westinghouse-designed plant in 2010. A recent metallurgical analysis of bolts removed from this plant confirmed that the bolts cracked due to PWSCC. The only aging mechanism requiring management by MRP-227-A for the clevis insert bolts is wear. The clevis insert bolts are categorized as an Existing Programs component under MRP-227-A, with the ASME Code,Section XI Inservice Inspection Program credited for managing aging due to wear only. The ASME Code,Section XI specifies a VT-3 visual inspection for the clevis insert bolts which may not be adequate to detect cracking before it results in bolt failure.
Therefore, the licensee is requested to discuss if it will modify the MRP-227-A inspection requirement for clevis insert bolts to require an inspection that will detect cracking. If the inspection requirement is not modified, provide a technical justification for the adequacy of the existing VT-3 visual inspection requirement to detect cracking before it results in clevis insert bolt failure.
References:
- 1. Meeting Summary EPRI-Westinghouse January 22-23, 2013, February 21, 2013 (ADAMS Accession No. ML13042A048).
- 2. 2/25/2013 Summary of Telecon with EPRI and Westinghouse Electric Company, March 15, 2013 (ADAMS Accession No. ML13067A262).
Siva P. Lingam U.S. Nuclear Regulatory Commission Project Manager (NRR/DORL/LPL2-2)
Sequoyah Nuclear Plant St. Lucie Plant Robinson Steam Electric Plant Location: O8-D5; Mail Stop: O8-G9a Telephone: 301-415-1564; Fax: 301-415-1222 E-mail address: siva.lingam@nrc.gov 2
Hearing Identifier: NRR_PMDA Email Number: 816 Mail Envelope Properties (Siva.Lingam@nrc.gov20130827103600)
Subject:
Robinson, Unit 2 PWR Vessel Internal Program Plan for Aging Management -
Requests for Additional Information (RAIs) (TAC No. ME9633)
Sent Date: 8/27/2013 10:36:21 AM Received Date: 8/27/2013 10:36:00 AM From: Lingam, Siva Created By: Siva.Lingam@nrc.gov Recipients:
"Broaddus, Doug" <Doug.Broaddus@nrc.gov>
Tracking Status: None "Rosenberg, Stacey" <Stacey.Rosenberg@nrc.gov>
Tracking Status: None "Cheruvenki, Ganesh" <Ganesh.Cheruvenki@nrc.gov>
Tracking Status: None "Alexander, Donna (Donna.Alexander@duke-energy.com)" <Donna.Alexander@duke-energy.com>
Tracking Status: None "richard.hightower@pgnmail.com" <richard.hightower@pgnmail.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 6450 8/27/2013 10:36:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: