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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
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
ML22154A2142022-06-0101 June 2022
Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - 2nd Round RAI B2.1.7-4b
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] |
Text
From: Guill, Paul F To: Wu, Angela; Johnson, Marieliz Cc: Gambrell, Reene; Robison, Greg; Nader, Rounette K; Roberts, Daniel William; Peltola, David W; Saville, Chris
Subject:
[External_Sender] Follow-up to 2/17/22 Oconee SLR public meeting Date: Wednesday, February 23, 2022 9:57:28 AM
- Angela, In response to the NRC staff request during the February 17, 2022 Oconee SLRA - Public Meeting, the following information is provided:
As part of subsequent license renewal (SLR), the High Pressure Injection (HPI) stop valve-to-check valve welds were identified as a Sentinel environmentally-assisted fatigue (EAF) location and were evaluated to the requirements of ASME Code,Section XI, Appendix L. The maximum 10-year Appendix L operating period was evaluated for these welds using a flaw tolerance methodology.
The design transients that contribute to fatigue on these welds are Transient 8E (Manual Actuation of HPI after Reactor Trip (Upset)), Transient 9 (Rapid Depressurization (Upset)), and Transient 22A (High Pressure Injection Test (Normal)). All other transients are negligible from the standpoint of fatigue.
The 60-year design transient allowable cycles are 70 cycles for Transient 8E, 40 cycles for Transient 9, and 40 cycles for Transient 22A. The flaw tolerance evaluation considered these 60-year transients, which are bounding for the projections for 80 years in SLRA Table 4.3.1-1, to evaluate the 10-year operating period. The flaw tolerance evaluation is an iterative analysis that computes projected flaw growth on a yearly basis to ultimately determine the maximum number of years allowed before the flaw reaches the size limitation described in the AMSE Code,Section XI criteria. As an input to this analysis, the 60-year design cycles were annualized for each iteration (the design cycles were divided by 60 years).
