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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
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MuDuke r-WEnergy T. PRESTON Vice Oconee GILLESPIE, Jr.
President Nuclear Station Duke Energy ONO VP / 7800 Rochester Hwy.
Seneca. SC 29672 864-873-4478 864-873-4208 fax T.Gillespie@duke-energy.corn May 2, 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Oconee Nuclear Station Docket Number 50-269, 50-270, 50-287 Emergency ResponseData System (ERDS) 10CFR50, Appendix E, Section VI, 3a requires that any software change that affects the transmitted data points identified in the Emergency Response Data System (ERDS) Data Point Library must be submitted to the NRC within 30 days after changes are completed.
Ediiorial changes to the Data Point Library were due to an Engineering Change #90482, Unit 1 Reactor Protection System Replacement. These changes are editorial in nature and will not affect parameters or ranges required by the NRC.
The ERDS parameter points affected are attached for your information and to update your Data Point Library.
If there are any questions regarding the software change, please contact Ray Waterman at (864) 873-3825.
Sincerely, T. Preston Gillespie, Jr.
Vice President Oconee Nuclear Station www. duke-energy.corn
U. S. Nuclear Regulatory Commission May 2, 2011 Page 2 Copy w/attachment Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John Stang, Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 8 G9A Washington, D. C. 20555 Mr. Bezakulu Alemu IT Specialist, Nuclear Security Incident Response 11545 Rockville Pike - 4A29 Rockville, MD 20852 Andy Sabisch/Oconee Resident Inspector
Oconee Nuclear Station Seneca, SC EC 90482 (Unit 1 RPS Replacement) addresses changes made to OAC PIDs that are ERDS points. This information is editorial in nature. It does not affect parameters or ranges required by the NRC.
NRC ERDs Parameter - NI POWER RNG Old Point ID - OIA1544 New Point ID - 01E4066 Old plant spec_pnt - NI 5 PR FLUX New plant specpnt - 1A NI-5 POWER RANGE FLUX NRC ERDs Parameter - CORE FLOW3 Old Point ID - 01A1549 New Point ID - 01E4091 Old plant spec_pnt - RPS CH A TOTAL RCS FLOW New plant spec_pnt - 1A RPS RC TOTAL FLOW (KLB/HR)
EC 90423 (Unit 1 ES Replacement) addresses changes made to OAC PIDs that are ERDS points. This information is editorial in nature. It does not affect parameters or ranges required by the NRC.
NRC ERDs Parameter - RCS PRESSURE Point ID - 01A1416 Old alarmpoint - LOW = 550 HIGH = 2400 New alarmpoint - NONE NRC ERDs Parameter - RCS PRESSURE4x Point ID - 01A1417 Old alarm_point - LOW = 550 HIGH = 2400 New alarmpoint - NONE Other editorial changes made:
NRC ERDs Parameter - BWST LEVEL1 Point ID - 01E2278 Old alarmpoint - LOW = 19 HIGH = 49 New alarmpoint - LOW = 47 HIGH = 49 NRC ERDs Parameter - BWST LEVEL2 Point ID - 01E2297 Old alarm_point - LOW = 19 HIGH = 49 New alarm_point - LOW = 47 HIGH = 49 NRC ERDs Parameter - COND AE RAD1 Point ID - O1A1674 Old plant specpnt - 1RIA-4CSAE EXHAUST New plant specpnt - 1 RIA-40 CSAE EXHAUST NRC ERDs Parameter - CORE FLOW2 Point ID -01 P1903 Old maximum-instr.range - 9000 New maximum-instr-range - 90000 NRC ERDs Parameter - CTMNT SP NR1 Point ID - O1A0049 Old plant specpnt - LWD RB NOR SUMP LVL New plant specpnt - RB NORMAL SUMP LEVEL Old engrunits/digstate - INCH New engrunits/digstate - INCHES Page 1 of 3
Oconee Nuclear Station Seneca, SC NRC ERDs Parameter - CTMNT SP NR6x Point ID - OlA0050 Old plant specpnt - RB EMER SUMP LEVEL New plant specpnt - RB EMER SUMP LEVEL (TRAIN B)
Old alarmpoint - HIGH = 2.5 New alarmpoint - HIGH = 2 NRC ERDs Parameter - CTMNT TEMP Point ID - O1A0006 Old alarmpoint - HIGH = 175 New alarm_point - HIGH = 140 NRC ERDs Parameter-CTMNT TEMP13x Point ID - O1A0043 Old plant specpnt - RB DOME TEMP New plant specpnt - RB DOME TEMP A NRC ERDs Parameter - HL TEMP 2B Point ID - 01E2280 Old engrunits/digstate - DEGF New engrunits/digstate - DEG F NRC ERDs Parameter - HPSI FLOW1 Point ID - O1A1238 Old plant specpnt - HP1HDR 1A INJECTION FLOW New plant specpnt - HPI HDR 1A INJECTION FLOW NRC ERDs Parameter - HPSI FLOW2 Point ID - O1A1239 Old plant spec_pnt - HP1 HDR 1B INJECTION FLOW New plant spec_pnt - HPI HDR 1B INJECTION FLOW NRC ERDs Parameter - LPSI FLOW1 Point ID - 01A1310 Old plant specpnt - LPI HDR 1A INJECTION FLOW New plant specpnt - LPI HDR 1A INJECTION FLOW Old alarm_point - LOW = 800 High = 3700 New alarmpoint - LOW = 800 High =
NRC ERDs Parameter - LPSI FLOW2 Point ID - 01A1311 Old plant specpnt - LP1 HDR 1B INJECTION FLOW New plant specpnt - LPI HDR 1B INJECTION FLOW Old alarm_point - LOW = 800 High = 3700 New alarmpoint - LOW = 800 High =
NRC ERDs Parameter - RCS CHG MU Point ID - 01A1044 Old plant specpnt - HP1 LETDOWN FLOW New plant specpnt - HPI LETDOWN FLOW NRC ERDs Parameter - REAC VES LV3 Point ID - 01 E2287 Old plant specpnt - HOT LEG A LEVEL New plant specpnt - RC HOT LEG A LEVEL NRC ERDs Parameter - REAC VES LV4 Point ID - 01E2288 Old plant spec_pnt - HOT LEG B LEVEL New plant spec_pnt - RC HOT LEG B LEVEL Page 2 of 3
Oconee Nuclear Station Seneca, SC NRC ERDs Parameter - SG LEVEL 1A Point ID - 01 E2002 Old alarmpoint - Low = High - 630.00 New alarmpoint - Low- 471 High =
NRC ERDs Parameter - SG LEVEL 2B Point ID - 01E2007 Old alarmpoint - High = 630.00 New alarm_point - Low= 471 High =
NRC ERDs Parameter- SG PRESS 1A Point ID - 01 E2031 Old plant spec_pnt - SG 1A OUTLET PRESSURE 3 New plant specpnt - SG 1A OUTLET PRESS 3 NRC ERDs Parameter - SG PRESS 2B Point ID - 01E2027 Old plant specpnt - SG 1B OUTLET PRESSURE 3 New plant spec_pnt - SG 1 B OUTLET PRESS 3 NRC ERDs Parameter - STAB CLASS1 Point ID -01 P01 60 Old plant specpnt - ENVIRONMENTAL AVERAGE DELTA TEMPE New plant spec_pnt - ENVIRONMENTAL AVERAGE DELTA TEMPERATURE NRC ERDs Parameter - SUB MARGIN1 Point ID - 01 P0793 Old plant spec_pnt - RCS LOOP A SAT TEMP MARG New plant specpnt - RCS LOOP A SAT TEMP MARGIN Old engrunits/digstate - DEGF New engrunits/digstate - DEG F NRC ERDs Parameter - SUB MARGIN2 Point ID - 01 P0794 Old plant specpnt - RCS LOOP B SAT TEMP MARG New plant spec.pnt - RCS LOOP B SAT TEMP MARGIN Old engrunits/digstate - DEGF New engrunits/digstate - DEG F NRC ERDs Parameter - WIND DIR3 Point ID - 01P0157 Old minimuminstr range - NONE New minimum-instr range - 0 Page 3 of 3