|
---|
Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation 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 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22234A0062022-08-30030 August 2022 SLRA - Closed Public Meeting Summary - August 18, 2022 2024-02-01
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 August 12, 2014 Mr. Scott Batson Site Vice President Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
PUBLIC MEETING
SUMMARY
- OCONEE NUCLEAR STATION -
DOCKET NO. 50-269
Dear Mr. Batson:
This refers to the Regulatory Conference conducted at NRC Region II office on July 31, 2014, concerning the preliminary Greater than Green finding for Oconee Nuclear Station Unit 1, as documented in NRC inspection report 05000269/2014011. The meeting purpose was to provide an opportunity for you to explain your position regarding the preliminary finding and to address the failure to promptly identify and correct a condition adverse to quality as required by 10 CFR 50, Appendix B, Criterion XVI. Enclosed are a list of attendees and a copy of the additional slide you presented at the meeting. The main set of presentation slides is available in the NRCs Agencywide Documents Access and Management System under accession numbers ML14211A213 and ML14211A216.
In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRC's Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room (PDR) or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this meeting, please contact me at 404-997-4551.
Sincerely,
/RA/
Gerald J. McCoy, Chief Reactor Projects Branch 1 Division of Reactor Projects
Enclosures:
- 1. List of Attendees
- 2. Handout - Additional Slide Presented by Licensee cc: Distribution via Listserv
August 12, 2014 Mr. Scott Batson Site Vice President Duke Energy Carolinas, LLC Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672
SUBJECT:
PUBLIC MEETING
SUMMARY
- OCONEE NUCLEAR STATION - DOCKET NO.
50-269
Dear Mr. Batson:
This refers to the Regulatory Conference conducted at NRC Region II office on July 31, 2014, concerning the preliminary Greater than Green finding for Oconee Nuclear Station Unit 1, as documented in NRC inspection report 05000269/2014011. The meeting purpose was to provide an opportunity for you to explain your position regarding the preliminary finding and to address the failure to promptly identify and correct a condition adverse to quality as required by 10 CFR 50, Appendix B, Criterion XVI.
Enclosed are a list of attendees and a copy of the additional slide you presented at the meeting. The main set of presentation slides is available in the NRCs Agencywide Documents Access and Management System under accession numbers ML14211A213 and ML14211A216.
In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRC's Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room (PDR) or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this meeting, please contact me at 404-997-4551.
Sincerely,
/RA/
Gerald J. McCoy, Chief Reactor Projects Branch 1 Division of Reactor Projects
Enclosures:
- 1. List of Attendees
- 2. Handout - Additional Slide Presented by Licensee cc: Distribution via Listserv Distribution:
L. Douglas, EICS Program Office Project Manager Public Document Room NRC Resident Inspectors RIDSNRRDIRS Responsible Branch Chief RidsNrrPMOconee Resource PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER:_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DRP SIGNATURE /AMR4/ /GJM1/
NAME ARuh GMcCoy DATE 8/12/2014 8/12/2014 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\DRPII\RPB1\OCONEE\MEETINGS\OCO REG CONF
SUMMARY
.DOCX
PUBLIC MEETING ATTENDANCE LIST We sincerely appreciate your presence at, and your interest in, the Nuclear Regulatory Commissions Public Meeting with Duke Energy Carolinas, LLC.
We ask that everyone print your name and affiliation below.
31 July2014 Name Affiliation L-Qurer Cos Dor_WUs Steve Vaunm
-ic Pv\\
c_Lee.
Ae.n Wn 9 NC bocc&c& Cu Nc
)UtiQOiX NRC W NRC.
(c-wa kRc Na4zxscx Cas NRO
&csoc eerch N Gx4 Duke 4
Lynco rcc- 5cx.r Cco\o SixP bi cc tJ\oM -roc-ur #ciy Assock R i cc Enclosure 1
PUBLIC MEETING ATTENDANCE LIST We sincerely appreciate your presence at, and your interest in, the Nuclear Regulatory Commissions Public Meeting with Duke Energy Carolinas, LLC.
We ask that everyone print your name and affiliation below.
31 July2014 Name Affiliation
-)/\/( Lyt r-c iRO //L o7C&
cJEF CU2cz6 c/A/ /t 12//
3bfl Dc.vd ct,flc N1c.
P N C ) jjj
[cL 1 L ,tJt fir ec& c fRii Th.Gç-k Lsr N(LC /p Mcv, NCiRJL Enclosure 1
PUBLIC MEETING ATTENDANCE LIST We sincerely appreciate your presence at, and your interest in, the Nuclear Regulatory Commissions Public Meeting with Duke Energy Carolinas, LLC.
We ask that everyone print your name and affiliation below.
31 July 2014 Name Affiliation Ee 7
JL4a{
4 !;/
- z
- A tJ:/ ç(/dC /iv9fr
-ve- 2f5 ke( i
,)
or1_
1 c(
E4uL PEr-L 1\
Fc A/VCc /mi7 L(L l-(NJ(6-1
-a c4 C)
Enclosure 1
PUBLIC MEETING ATTENDANCE LIST We sincerely appreciate your presence at, and your interest n, the Nuclear Regulatory Commissions Public Meeting with Duke Energy Carolinas, LLC.
We ask that everyone print your name and affiliation below.
31 July2014 Name Affiliation 4 IsA &
zj J\C 12tv If\:\
)L--- ti.- ; S Jv/ I Le) 7D)T 42<- JL Enclosure 1
- CRP (6E-04) x CCDP represents increase in risk with the following assumptions:
- Leak is assumed to exist for 1 year
- Large uncertainty in crack length applied
- Bounding stress applied to grow crack
- No repair of leak for one year
- [CRP (6E-04) x CCDP x fi x f2] 1(1 year) = change in CDF = <<1 OE-7 Iyr
- fi: HPI Thru wall crack is not identified and not repaired is <1 E-02
- f2: bounding stresses are expected to occur is <1 E-02 Result: Increase in CDF in this approach is very low safety significance For Information Only Enclosure 2