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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
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1 NRR-PMDAPEm Resource From: Klett, Audrey Sent: Wednesday, June 28, 2017 3:08 PM To: Wasik, Christopher J; Shingleton, Boyd
Subject:
Draft Oconee Public Meeting Summary Attachments:
MF9754-56 Oconee Public Meet ing Summary Rev02.docxHi Chris, Hi Boyd, Attached is a draft of the meeting summary. It has not gone through NRC management concurrence yet. If you have any comments or clarifications on how I captured what was discussed during the meeting, please let me know. Please also let me know if it contains any proprietary information.
Thanks, Audrey
Hearing Identifier: NRR_PMDA Email Number: 3616 Mail Envelope Properties (Audrey.Klett@nrc.gov20170628150700)
Subject:
Draft Oconee Public Meeting Summary Sent Date: 6/28/2017 3:07:31 PM Received Date: 6/28/2017 3:07:00 PM From: Klett, Audrey Created By: Audrey.Klett@nrc.gov Recipients: "Wasik, Christopher J" <Christopher.Wasik@duke-energy.com> Tracking Status: None "Shingleton, Boyd" <Boyd.Shingleton@duke-energy.com> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 332 6/28/2017 3:07:00 PM MF9754-56 Oconee Public Meeting Summary Rev02.docx 38867 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
LICENSEE: Duke Energy Carolinas, LLC
FACILITY: Oconee Nuclear Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF JUNE 27, 2017, MEETING WITH DUKE ENERGY CAROLINAS, LLC TO DISCUSS PROPOSED LICENSE AMENDMENT REQUEST FOR OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 REGARDING THERMAL MARGIN FOR THE STANDBY SHUTDOWN FACILITY (CAC NOS. MF9754, MF9755, AND MF9756)
On June 27, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff held a Category 1 public meeting with representatives from Duke Energy Carolinas, LLC (the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss a proposed license amendment request regarding thermal margin for the Standby Shutdown Facility (SSF) at the Oconee Nuclear Station, Units 1, 2, and 3 (Oconee). The meeting notice and agenda, dated June 14, 2017, are available in NRC's Agencywide Documents Access and Management System under Accession No. ML17165A377. A list of attendees and the meeting presentation material are enclosed.
The licensee gave a presentation of its planned license amendment request to modify the Oconee Updated Final Safety Analysis Report (UFSAR). Enclosure 2 of this meeting summary contains the presentation slides, proposed UFSAR changes, and other background information that the licensee provided to the staff. The licensee gave a brief overview of the purpose and requirements of the SSF. The licensee explained that during a review of the SSF in 2011, it identified that an unanalyzed condition exists during some limited operating conditions that exist during startup and shutdown (i.e., in conditions involving lower decay heat) in plant modes when operability of the SSF is required by Technical Specifications. During those conditions, one of the UFSAR success criteria for use of the SSF cannot be met, and the licensee has to declare the SSF inoperable per its Technical Specifications. The licensee proposed to use previously approved thermal-hydraulic methodologies to justify revising the UFSAR success criteria to permit water solid conditions in the pressurizer without water relief through the pressurizer safety valves and to credit ambient losses, makeup, and letdown (after plant modifications to enhance letdown capability) for decay heat removal. The licensee also stated that it wishes to use operation of atmospheric dump valves to enhance SSF event mitigation. The licensee also discussed plant modifications to support SSF capability during a turbine building flooding event. The licensee stated that it was not proposing any changes to the Technical Specifications, including those for the atmospheric dump valves.
The staff asked the licensee questions about its ability to safely shut down the plant during water solid conditions in the reactor coolant system and whether pressurizer safety relief valves were qualified for liquid discharge. The staff also asked the licensee how it intends to use thermal-hydraulic analyses in its justification of the proposed changes. The licensee stated that thermal-hydraulic analyses would be performed using NRC-approved RETRAN-3D models for Oconee, and that the RELAP5/MOD2-B&W analysis will serve as a benchmark of the RETRAN-3D analyses. The intent of the benchmark is to provide additional support for RETRAN-3D analyses that result in water-solid conditions in the pressurizer. The licensee stated it would support a staff audit of such analyses if needed. The staff also asked the licensee whether the bases for any technical specifications requirements (e.g., limiting conditions for operation, surveillance requirements, or completion times) would be affected by the proposed changes.
The licensee plans to submit its license amendment request in August 2017 and request the staff to complete its review in 12 to 18 months fr om the submittal date. The staff will provide its projected review schedule as part of its acceptance review of the submittal. The staff did not make any regulatory decisions or commitments at the meeting. No members of the public were in attendance at the meeting nor announced over the telephone.
Any inquiries can be directed to Ms. Audrey Klett at 301-415-0489 or Audrey.Klett@nrc.gov.
Audrey Klett, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-269, 50-270, and 50-289
Enclosures:
- 1. List of Attendees
- 2. Meeting Presentation Material
cc w/encls: Distribution via Listserv
ML17179A347
- by email OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DSS/SRXB/BC* DSS/SNPB/BC* NAME AKlett KGoldstein EOesterle RLukes DATE / /17 / /17 / /17 / /17 OFFICE DSS/SBPB/BC* DSS/STSB/BC (A)* DORL/LPL2-1/BC DORL/LPL2-1/PMNAME RDennig JWhitman MMarkley AKlett DATE / /17 / /17 / /17 / /17 Enclosure 1 LIST OF ATTENDEES JUNE 27, 2017, MEETING WITH DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 PROPOSED LICENSE AMENDMENT REQUEST REGARDING THERMAL MARGIN FOR THE STANDBY SHUTDOWN FACILITY U.S. Nuclear Regulatory Commission Michael T. Markley Eric Oesterle Reed Anzalone
Robert Beaton
Jerome Bettle Matthew Hamm Audrey Klett, Duke Energy Carolinas, LLC Chris Wasik Boyd Shingleton Philip North Greg Byers Adam Bingham
David Wilson Dave Baxter Tracy Saville*
Mark Handrick*
Scott Thomas*
Jeff Abbott*
Lee Kanipe*
Ken Grayson*
Paul Mabry*
Tim Brown*
Jeremy Moyer*
- Participated by phone Enclosure 2
Meeting Presentation Material