Letter Sequence Other |
---|
|
|
MONTHYEARML0603800022006-02-0909 February 2006 Letter MC4698, RAI for GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors. Project stage: RAI ML0710701332007-03-14014 March 2007 Task Order No. 004 to Delivery No. DR-03-06-046 Project stage: Other ML0817506352008-07-0101 July 2008 Generic Letter 2004-02, Supplemental Response Project stage: Other LR-N13-0148, Generic Letter 2004-02 In-Vessel Downstream Effects Resolution2013-07-11011 July 2013 Generic Letter 2004-02 In-Vessel Downstream Effects Resolution Project stage: Request ML13219A1102013-07-31031 July 2013 Closure Options for Generic Safety Issue (GSI)-191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter (GL) 2004-02... Project stage: Request ML13339A7892013-12-0505 December 2013 12/5/13 e-mail from R.Guzman to B.Meixell GSI-191 Closure Options Due Date Request Project stage: Other ONS-2014-024, Closure Option 1 Response for Generic Safety Issue (GSI)-1 91, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter (GL) 2004-02, Potential Impact of Deb2014-02-27027 February 2014 Closure Option 1 Response for Generic Safety Issue (GSI)-1 91, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance in Resolution of Final Issues Related to Generic Letter (GL) 2004-02, Potential Impact of Debris. Project stage: Request ML14113A2212014-04-30030 April 2014 NRC Staff Review of the Documentation Provided by PSEG Nuclear LLC for the Salem Generating Station Units 1 and 2 Concerning Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Project stage: Request ML14219A4822014-08-27027 August 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML14218A8072014-08-27027 August 2014 NRC Staff Review of the Documentation Provided by Duke Energy for the Oconee Nuclear Station Concerning Resolution of GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat Project stage: Request 2013-07-11
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML24257A0212024-09-11011 September 2024 Document Request for Oconee Nuclear Station - Radiation Protection Inspection - Inspection Report 2024-04 ML24234A2972024-08-21021 August 2024 August 21, 2024 - Oconee Nuclear Station, Units 1, 2, and 3 - Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.7.7 ML24211A0872024-07-27027 July 2024 EN 57079 Paragon Energy Solutions Final - No Active Links ML24197A2292024-07-15015 July 2024 Email from Mark Yoo (NRC) to Steve Snider (Duke) - Oconee SLRA - RAI - 2024 Annual Update ML24190A0462024-07-0505 July 2024 Notification of Inspection and Request for Information ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24143A1322024-05-22022 May 2024 May 22, 2024, Verbal Authorization for Duke Energy Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI (RA-24-0152) (EPID L- 2024-LLR-0034) ML24127A0892024-05-0202 May 2024 57079-EN57079-1 - Redline Strikethrough e-mail Re Part 21 Interim Notification of Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24086A3772024-03-26026 March 2024 Request for Additional Information License Amendment Request to Revise Technical Specification 5.5.2 ML24036A1442024-02-27027 February 2024 NRC to Fws, NRC Request for Concurrence with Endangered Species Act Determinations for Oconee Nuclear Station, Units 1, 2, and 3, Proposed Subsequent License Renewal in Oconee County, South Carolina (Consultation Code: 2023-0054989) ML24054A0492024-02-21021 February 2024 Notification of Oconee Nuclear Station FEI Inspection and Information Request-Email ML23349A0272023-12-15015 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 ML22113A0082022-04-20020 April 2022 Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Additional Information 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 ML22088A0452022-03-28028 March 2022 Radiation Safety Baseline Inspection Initial Information Request Inspection Report 2022002 2024-09-11
[Table view] |
Text
From: Guzman, Richard Sent: Thursday, December 05, 2013 1:54 PM To: 'Meixell, Bob' Cc: Wilson, David A; Mabry, Paul E; Wasik, Christopher J; Lynch, Brandon
Subject:
RE: Oconee GSI-191 Closure Options due Date Request Bob, The requested extension to February 27, 2014, for Oconee's subject follow-up response, is acceptable. As we discussed, this e-mail exchange will be added to ADAMS and serve as the
official agency record documenting NRC sta ff's administrative acknowledgement for this schedule change.
Thanks, Rich Guzman Sr. Project Manager NRR/DORL US NRC 301-415-1030
From: Meixell, Bob [1]
Sent: Tuesday, December 03, 2013 1:19 PM To: Guzman, Richard Cc: Meixell, Bob; Wilson, David A; Mabry, Paul E; Wasik, Christopher J; Lynch, Brandon
Subject:
Oconee GSI-191 Closure Options due Date Request Rich,
I am requesting your consideration of a change in the due date for Oconee's next GSI-191 submittal as discussed in the attached letter.
Recent correspondence indicates the NRC has postponed planned GSI-191 site visits in the first quarter of 2014 and will not close-out this issue until the Boron Precipitation issue is addressed.
I attached Oconee's July 31, 2013, Closure Options letter for your reference, and I would like to discuss our planned December 15, 2013, submittal date that was included in this letter.
December 15 th, (should have been December 16 th as the 15 th is Sunday) is a date we chose internally and was not a hard NRC commitment.
I am requesting to change the date for Oconee's follow-up response to February 27, 2014, due to concurrent outages on Oconee Units 1 and 2 and the upcoming holidays. Since the NRC is not going to process final closure until after the first quarter of 2014, we do not see the new due date having any impact on our current GSI-191 status or on Oconee's closure status.
Please call me or respond with your thoughts on this request.
Thanks, Bob
Bob Meixell Senior Licensing Specialist Regulatory Affairs Oconee Nuclear Station (864) 873-3279 The Core 4:
(1) Job Briefs (2) Take A Minute (3) CCV & Validate Assumptions (4) Procedure Use and Adherence