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MONTHYEARML12073A3542012-03-0909 March 2012 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model Project stage: Request ML12300A2012012-10-26026 October 2012 NRC Request for Additional Information on Errors Reported Per 10 CFR 50.46, ME9119 Project stage: RAI ML12348A0552012-12-0707 December 2012 Response to RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis Project stage: Request ML13060A4172013-03-0101 March 2013 NRC Request for Additional Information on Errors Reported Per 10 CFR 50.46 (TACs ME9119, ME9120, ME9121) Project stage: RAI ML13102A0332013-04-0404 April 2013 Response to NRC RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis Project stage: Request ML13237A0022013-08-23023 August 2013 NRR E-mail Capture - Oconee Nuclear Station, Units 1, 2, and 3, NRC Request for Additional Information on Errors Reported Per 10 CFR 50.46 (TACs ME9119, ME9120, ME9121) Project stage: RAI ML13309A4462013-09-12012 September 2013 E-mail from R.Guzman to T.Byrne Request for Additional Information on Errors Reported Per 10 CFR 50.46 (TACs ME9119, ME9120, ME9121) Project stage: RAI RA-13-1002, Response to Supplemental NRC RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident2013-10-10010 October 2013 Response to Supplemental NRC RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Project stage: Request ML13338A3452013-12-0505 December 2013 Closure Evaluation for Report Concerning Significant Emergency Core Cooling System Evaluation Model Errors/Changes Project stage: Other 2013-12-05
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Category:E-Mail
MONTHYEARML23349A0272023-12-15015 December 2023 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 5.5.2 ML23284A3322023-10-11011 October 2023 Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060) ML23270B8362023-09-26026 September 2023 Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards ML23267A0032023-09-21021 September 2023 RP Inspection Document Request ML23269A0412023-08-22022 August 2023 Code Case N-752 Audit; August 22, 2023, E-mail Providing Additional Information Regarding Design and Quality Program Requirements 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) ML23144A0862023-05-24024 May 2023 Acceptance of Requested Licensing Action Proposed Relief Request (RA-23-0018) to Use ASME Code Case 853 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) ML23125A1452023-05-0505 May 2023 Change in Estimated Review Schedule and Level of Effort for Proposed Alternative to Use Code Case N-752 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) 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) 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) ML23038A1832023-02-0707 February 2023 Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752 ML23031A1552023-01-17017 January 2023 1/17/2023 Email from John Moses, Deputy Director, Division of Rulemaking, Environmental, and Financial Support, to Diane Curran, Counsel to Beyond Nuclear and the Sierra Club, Request for Extension of Scoping Comment Period for Oconee EIS ML22294A0812022-10-21021 October 2022 Nrc/Duke Steam Generator Inspection Call for November 8, 2022 NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) 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 ML22235A6552022-08-23023 August 2022 Acceptance of Requested Licensing Action Proposed Alternative to Use ASME Code Case N-752 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22234A1262022-07-0808 July 2022 Email from NRC to Duke - Feedback on Trp 76 RAI Responses - July 8, 2022 ML22234A1272022-06-14014 June 2022 Email from NRC to Duke - Feedback on Trp 76 RAI Responses - June 14, 2022 ML22154A2142022-06-0101 June 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - 2nd Round RAI B2.1.7-4b 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 ML22124A2052022-05-0404 May 2022 Summary of May 4, 2022, Clarification Call with Duke Energy Carolinas, LLC, Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System ML22124A1612022-05-0303 May 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22122A0192022-04-28028 April 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A1322022-04-27027 April 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round Requests for Additional Information (FE 3.5.2.2.2.6 - Irradiation Structural) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22130A0112022-04-25025 April 2022 Email: Oconee SLRA - RAI 4.6.1-1a - NRC Staff Comments ML22112A1892022-04-22022 April 2022 Acceptance Review for Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9 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 ML22113A0082022-04-20020 April 2022 Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Additional Information 3.1.2-1 ML22088A0452022-03-28028 March 2022 Radiation Safety Baseline Inspection Initial Information Request Inspection Report 2022002 ML22081A0052022-03-21021 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B4.1-3 ML22080A0792022-03-16016 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 4 (2nd Round Rais) ML22075A2032022-03-11011 March 2022 Email from Duke to NRC - Follow-Up Items from March 7, 2022 Public Meeting ML22074A0022022-03-11011 March 2022 Email from Duke to NRC - Follow-up Item from March 7, 2022 Public Meeting - SSW Tendon AMP ML22069A0022022-03-0808 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 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 ML22063A1152022-02-23023 February 2022 Email from Duke to NRC - Follow Up Item from February 17, 2022 Public Meeting ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22035A1892022-01-31031 January 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Request for Public Meeting ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22019A1032022-01-18018 January 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 3 ML22012A0432022-01-11011 January 2022 SLRA - Requests for Additional Information - Set 2 2023-09-26
[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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From: Boska, John Sent: Friday, October 26, 2012 10:38 AM To: Alter, Kent R Cc: 'Guill, Paul F'
Subject:
Oconee Units 1, 2, and 3, NRC Request for Additional Information on Errors Reported per 10 CFR 50.46, ME9119 Importance: High By letter dated March 9, 2012 (Agencywide Documents Access and Management System Accession No. ML12073A354), Duke Energy Carolinas, LLC, the licensee for Oconee Nuclear Station, Units 1, 2, and 3, submitted a 30-day report of changes to or errors discovered in an evaluation model or in the application of such a model that affects the peak cladding temperature (PCT) calculation. This report was submitted pursuant to the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.46, which requires, in part, that licensees report a change in the evaluation model used resulting in a significant change in PCT (greater than 50°F). The intent of this requirement is to enable the staff to establish the safety significance of this change (See Federal Register (FR) Volume 53, No. 180, pp. 35996-36005). As described in the Nuclear Reactor Regulation staffs action plan for determining, restoring, and ensuring compliance with 10 CFR 50.46 requirements, this 50.46 report review is being coordinated with reviews of similar reports submitted by other licensees using the same emergency core cooling system evaluation model.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific questions are found below. On October 25, 2012, the Duke staff indicated that a response to the RAI would be provided within 45 days of the date of this email.
REQUEST FOR ADDITIONAL INFORMATION:
- 1. There are two changes to peak cladding temperature (PCT) for Large Break Loss of Coolant Accident (LBLOCA) analysis discussed in the report submitted by the licensee. The first change is an Evaluation Model (EM) application error in the determination of the end of Emergency Core Cooling System (ECCS) bypass which resulted in an 80°F decrease in PCT. The second change is an EM modeling change to include the effects of the upper plenum column weldments which resulted in an 80°F increase in PCT.
Provide the analysis that lead to each change having an 80 degree change in PCT.
- 2. 10 CFR 50.46(a)(3)(ii) states: " ... If the change or error is significant, the applicant or licensee shall provide this report within 30 days and include with the report a proposed schedule for providing a reanalysis or taking other action as may be needed to show compliance with 50.46 requirements ... "
The PCT for LBLOCA for Oconee Units 1, 2, and 3 has changed by an absolute value of 160°F since the analysis was performed. Simply reporting the changes and errors in the methodology does not satisfy the intent of the regulation. Justify not providing a schedule for reanalysis or taking other action to show compliance with Section 50.46.
John Boska
Oconee Project Manager, NRR/DORL U.S. Nuclear Regulatory Commission 301-415-2901 email: john.boska@nrc.gov