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Category:E-Mail
MONTHYEARIR 05000261/20240042024-10-0303 October 2024 Document Request for Robinson Nuclear Plant - Radiation Protection Inspection - Inspection Report 05000261/2024004 ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24164A0052024-06-11011 June 2024 NRR E-mail Capture - Request for Additional Information Regarding Dukes February 15, 2024, Relief Request RA-23-0300 for Robinson ML24079A3062024-03-19019 March 2024 NRR E-mail Capture - Acceptance Review Results for Robinson - Proposed Relief Request RA-23-0300 ML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Dukes 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 Dukes 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 Dukes 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 2024-06-24
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From:Uribe, JuanTo:"Maysam, Al"; Paul.Guill@duke-energy.com
Subject:
Robinson RAI regarding NTTF 2.1-FloodingDate:Monday, December 14, 2015 9:52:00 AMAl, Paul: As previously discussed, here is the info need that will be docketed as an RAI as part of the review.Please reference this email as the source in the response letter.
Thanks Robinson Info Needs-12/14/2015 1. Starting Water Level for the Robinson Dam Overtopping Failure in HEC-RAS: NRC staff's review of the HEC-RAS dam failure file revealed that the breach starting elevation is set to the top of the embankment elevation of 229.075 ft NAVD88. However, this assumption does not consider the time needed to erode the downstream face of the dam and is also not supported by the NWS BREACH model output data. USACE Guide (TD-39, "Using HEC-RAS for Dam Break Studies," August 2014, p.9) states that "the HEC-RAS breach start time is considered to be when the erosion process has mitigated to the upstream face of the dam." Provide additional information that justifies selecting a breach starting elevation set to the top of the embankment elevation. JUAN F. URIBE PROJECT MANAGER NRR/JLD/JHMB 301-415-3809 l O-13F10 l Juan.Uribe@nrc.gov U.S. Nuclear Regulatory Commission Please consider the environment before printing this e-mail From:Uribe, JuanTo:"Maysam, Al"; Paul.Guill@duke-energy.com
Subject:
Robinson RAI regarding NTTF 2.1-FloodingDate:Monday, December 14, 2015 9:52:00 AMAl, Paul: As previously discussed, here is the info need that will be docketed as an RAI as part of the review.Please reference this email as the source in the response letter.
Thanks Robinson Info Needs-12/14/2015 1. Starting Water Level for the Robinson Dam Overtopping Failure in HEC-RAS: NRC staff's review of the HEC-RAS dam failure file revealed that the breach starting elevation is set to the top of the embankment elevation of 229.075 ft NAVD88. However, this assumption does not consider the time needed to erode the downstream face of the dam and is also not supported by the NWS BREACH model output data. USACE Guide (TD-39, "Using HEC-RAS for Dam Break Studies," August 2014, p.9) states that "the HEC-RAS breach start time is considered to be when the erosion process has mitigated to the upstream face of the dam." Provide additional information that justifies selecting a breach starting elevation set to the top of the embankment elevation. JUAN F. URIBE PROJECT MANAGER NRR/JLD/JHMB 301-415-3809 l O-13F10 l Juan.Uribe@nrc.gov U.S. Nuclear Regulatory Commission Please consider the environment before printing this e-mail