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Category:Letter
MONTHYEARIR 05000413/20240032024-11-0404 November 2024 Integrated Inspection Report 05000413/2024003 and 05000414/2024003 ML24297A6222024-10-11011 October 2024 PCA Letter to NRC Catawba Hurricane Helene IR 05000413/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000413/2024011 and 05000414/2024011 ML24255A8312024-09-23023 September 2024 Project Manager Assignment ML24261B9782024-09-19019 September 2024 Notification of an NRC Fire Protection Team Inspection NRC Inspection Report 05000413-2024010, 05000414-2024010 and Request for Information IR 05000414/20240912024-09-0505 September 2024 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter-NRC Inspection Report 05000414-2024091 IR 05000413/20240052024-08-26026 August 2024 Updated Inspection Plan for Catawba Nuclear Station (Report 05000413/2024005 & 05000414/2024005) ML24235A1542024-08-22022 August 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000413-2024402 and 05000414-2024402) IR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) IR 05000413/20243012024-03-12012 March 2024 – Notification of Licensed Operator Initial Examination 05000413/2024301 and 05000414/2024301 ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) 05000414/LER-2024-001, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan2024-03-0404 March 2024 Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan IR 05000413/20230062024-02-28028 February 2024 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - (NRC Inspection Report 05000413/2023006 and 05000414/2023006) IR 05000413/20230042024-02-0202 February 2024 – Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 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 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 – Integrated Inspection Report 05000413/2023001 and 05000414/2023001 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 IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20234012023-03-0101 March 2023 – Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 05000414/LER-2022-003, Manual Reactor Trip and Auxiliary Feedwater System Actuation2022-12-23023 December 2022 Manual Reactor Trip and Auxiliary Feedwater System Actuation IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 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 05000414/LER-2022-002, Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination2022-12-0606 December 2022 Indications Identified During Reactor Vessel Head Penetration Embedded Flaw Repair Surface Examination 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 2024-09-05
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-23-0245, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2024-06-18018 June 2024 License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable ML23188A0732023-07-0707 July 2023 Acceptance of Requested Licensing Action License Amendment Application to Revise Control Room Cooling Technical Specifications RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RA-18-0156, Administrative License Amendment Request Proposing to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability2019-09-0404 September 2019 Administrative License Amendment Request Proposing to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-0036, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2019-07-0101 July 2019 License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-18-0198, (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-10-29029 October 2018 (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System RA-18-0094, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating2018-10-0808 October 2018 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating CNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time ML17165A4412017-07-21021 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-269-A, Revision 2 (CAC Nos. MF8983 and MF8984). 08/10/2017 RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17122A1162017-05-0202 May 2017 Catawba and McGuire - License Amendment Request Proposing Changes to Technical Specification 3.8.1, AC Sources - Operating. RA-16-0028, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2016-12-15015 December 2016 Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process CNS-16-030, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address ...2016-06-15015 June 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address ... RA-16-0021, License Amendment Request Proposing an Updated Final Safety Analysis Report Revision to Reflect Electrical Power Systems Alignments for Shared Systems2016-05-26026 May 2016 License Amendment Request Proposing an Updated Final Safety Analysis Report Revision to Reflect Electrical Power Systems Alignments for Shared Systems CNS-16-014, License Amendment Request (LAR) to Adopt National Fire Protection (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, LAR Submittal to Correct a Legacy Submittal Discrepancy And.2016-03-23023 March 2016 License Amendment Request (LAR) to Adopt National Fire Protection (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, LAR Submittal to Correct a Legacy Submittal Discrepancy And. CNS-16-015, Technical Specification Bases Changes2016-02-18018 February 2016 Technical Specification Bases Changes CNS-16-001, License Amendment Request (LAR) to Revise Technical Specifications (TS) Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-01-18018 January 2016 License Amendment Request (LAR) to Revise Technical Specifications (TS) Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-12-11011 December 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants RA-15-0020, License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding2015-08-20020 August 2015 License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding RA-15-001, Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Foot2015-07-15015 July 2015 Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footn RA-15-0013, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112015-07-15015 July 2015 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4392015-06-24024 June 2015 Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-523, Rev. 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 1 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 CNS-15-058, Proposed Technical Specifications (TS) Amendments, TS 3.4.1, Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits2015-06-12012 June 2015 Proposed Technical Specifications (TS) Amendments, TS 3.4.1, Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ML15125A1352015-04-30030 April 2015 License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors, Dated November 2012 CNS-14-128, License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable.2014-11-24024 November 2014 License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable. RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area2014-07-21021 July 2014 License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate2014-06-23023 June 2014 License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.2014-02-17017 February 2014 Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System. CNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology2013-11-14014 November 2013 License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology ML13032A0332013-01-21021 January 2013 License Amendment Request for Technical Specification (TS) 3.6.14, Divider Barrier Integrity. ML1207600792012-06-25025 June 2012 Issuance of Amendment Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications 2024-06-18
[Table view] |
Text
P Duke JAMES R. MORRIS Vice President Energy. Catawba Nuclear Station 4800 Concord Rd. / CNOI VP York, SC 29745-9635 803 831 4251 803 831 3221 fax November 22, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Unit 1 Docket Number 50-413 Proposed Amendment to Facility Operating License (FOL)
FOL Condition Regarding Extension of Time Limit to Complete Emergency Core Cooling Systems (ECCS) Sump Modification
Reference:
Letter from Dhiaa M. Jamil (Duke) to NRC, dated November 1, 2006 In accordance with the provisions of 10 CFR 50.90, Duke proposes to revise the Catawba Unit 1 FOL to provide for an extension of the time limit to complete the required modification to the ECCS sump. Our commitment to submit this amendment to the Catawba Unit 1 FOL was transmitted to the NRC via the reference letter.
In this submittal, Duke is proposing to modify the Catawba Unit 1 FOL to add a license condition which requires that 1) Unit 1 will enter Mode 5 for the outage to install the sump strainer modification no later than May 19, 2008 and that 2) the Unit 1 sump strainer modification will be completed prior to entry into Mode 4 after May 19, 2008.
The contents of this amendment request package are as follows:
Attachment 1 provides a marked copy of the affected FOL pages for Catawba Unit 1, showing the proposed change. Attachment 2 provides a reprinted copy of the affected FOL pages for Catawba Unit 1, incorporating the proposed change. Attachment 3 provides a description of the proposed change and justification for the change. Pursuant to 10 CFR 50.92, Attachment 4 documents the determination that the amendment contains No Significant Hazards www.duke-energy. corn 40DI
U.S. Nuclear Regulatory Commission Page 2 November 22, 2006 Considerations. Pursuant to 10 CFR 51.22(c) (9), Attachment 5 provides the basis for the categorical exclusion from performing an Environmental Assessment/Impact Statement.
Amendment implementation will be accomplished within 30 days of NRC approval and in any event, no later than December 31, 2007, which is the existing commitment date for resolution of Generic Safety Issue (GSI)-191 for Catawba Unit 1.
In accordance with Duke administrative procedures and the Quality Assurance Program Topical Report, this proposed amendment has been previously reviewed and approved by representatives of the Catawba Plant Operations Review Committee and the Duke Nuclear Safety Review Board.
Pursuant to 10 CFR 50.91, a copy of this proposed amendment is being sent to the appropriate state official.
Inquiries on this matter should be directed to L.J. Rudy at (803) 831-3084.
Very truly yours, James R. Morris LJR/s Attachments
U.S. Nuclear Regulatory Commission Page 3 November 22, 2006 James R. Morris affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
JamdyR. Morris, Vice President Subscribed and sworn to me:
Date My commission expires: 7---/o- 1 Date SEAL
U.S. Nuclear Regulatory Commission Page 4 November 22, 2006 xc (with attachments):
W.D. Travers U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 A.T. Sabisch Senior Resident Inspector (CNS)
U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.F. Stang, Jr. (addressee only)
NRC Project Manager (CNS)
U.S. Nuclear Regulatory Commission Mail Stop 8 H4A Washington, D.C. 20555-0001 H.J. Porter, Assistant Director Division of Radioactive Waste Management Bureau of Land and Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201
ATTACHMENT 1 MAKED-UP FOL PAGES FOR CATAWBA
(6) Additional Conditions The Additional Coqntions contained InAppendix B, as revised through Amendment No. V are hereby incorporated Into this renewed operating license. Duke Power Company LLC shall operate the facility in accordance with the Additional Conditions.
D. The facility requires exemptions from certain requirements of Appendix J to 10 CFR Part 50, as delineated below and pursuant to evaluations contained in the referenced SER and SSERs. These Include, (a) partial exemption from the requirement of paragraph IILD.2(b)(ii) of Appendix J, the testing of containment airlocks at times when the containment integrity is not required (Section 6.2.6 of the SER, and SSERs
- 3 and #4), (b) exemption from the requirement of paragraph Ill.A.(d) of Appendix J, Insofar as it requires the venting and draining of lines for type Atests (Section 6.2.6 of SSER #3), and (c) partial exemption from the requirements of paragraph 111.B of Appendix J, as it relates to bellows testing (Section 6.2.6 of the SER and SSER #3).
These exemptions are authorized by law, will not present an undue risk to the public health and safety, are consistent with the common defense and security, and are consistent with certain special circumstances as discussed In the referenced SER and SSERs. These exemptions are, therefore, hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent authorized herein, In conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E. Physical Protection Duke Power Company LLC shall fully Implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification and safeguards contingency plans Including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and10 CFR 50.54(p). The combined set of plans, which contains safeguards Information protected under 10 CFR 73.21, is entitled: "Duke Energy Physical Security Plan" submitted by letter dated September 8, 2004, and supplemented on September 30, 2004, October 15, 2004, October 21, 2004 and October 27, 2004.
F. ReportinatotheCommission Deleted by Amendment No.230 -
II Renewed License No. NPF-5 Amendment No.
APPENDIX B rG 1';rG;U1AT10HI 0iN ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-35 Duke Power Company LLC shall comply with the following conditions on the schedules I noted below:
Amendment Implementation Number Additional Condition Date 159 This amendment requires the licensee to use Immediately administrative controls, as described in the upon issuance licensee's letter of March 7, 1997, and of the evaluated in the staff's safety amendment evaluation dated April 29, 1997, to restrict the dose-equivalent iodine levels to 0.46 microCurie per gram (in lieu of the limit in TS Section 3.4.8.a), and to 26 microCurie per gram (in lieu of the limit of TS Figure 3.4-1),
until this license condition is removed by a future amendment.
173 The licensee Is authorized to relocate certain All relocation to be requirements included in appendix A to completed by licensee-controlled documents. January 31, 1999.
Implementation of this amendment shall include the relocation of these requirements to the appropriate documents as described in the licensee's letters dated May 27, 1997, as amended by letters dated March 9, March 20, April 20, June 3, June 24, July 7, July 21, August 5, September 8, and September 15, 1998, and evaluated in the NRC staff's Safety Evaluation associated with this amendment.
Renewed License No. NPF-35 Amendment No. 229
-I-
Amendment Implementation Number Additional Condition Date 173 The schedule for the performance of new and By January 31, 1999 revised surveillance requirements shall be as follows:
For surveillance requirements (SRs) that are new in Amendment No. 173 the first performance Is due at the end of the first surveillance interval that begins at implementation of Amendment No. 173. For SRs that existing prior to Amendment No.
173, including SRs with modified acceptance criteria and SRs who Intervals of performance are being extended, the first performance is due at the end of the first surveillance Interval that begins on the date the surveillance was last performed prior to implementation of amendment No. 173. For SRs that existed prior to Amendment No. 173, whose intervals of performance are being reduced, the first reduced surveillance Interval begins upon completion of the first surveillance performed after implementation of Amendment No. 173 180 The maximum rod average bumup for any rod Within 30 days of shall be limited to 60 GWd/mtU until the date of amendment.
completion of an NRC environmental assessment supporting an increased limit.
a-Amendment No.
INSERT for Catawba Unit 1 FOL page:
In association with the ECCS sump strainer modification and Generic Safety Issue (GSI)-191 requirements:
- 1. Unit 1 shall enter Mode 5 for the outage to install the sump strainer modification no later than May 19, 2008 and
- 2. The Unit 1 sump strainer modification shall be completed prior to entry into Mode 4 after May 19, 2008.
ATTACHMENT 2 REPRINTED FOL PAGES FOR CATAWBA
Amendment Implementation Number Additional Condition Date 173 The schedule for the performance of new and By January 31, 1999 revised surveillance requirements shall be as follows:
For surveillance requirements (SRs) that are new in Amendment No. 173 the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment No. 173. For SRs that existing prior to Amendment No. 173, including SRs with modified acceptance criteria and SRs who intervals of performance are being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of amendment No. 173. For SRs that existed prior to Amendment No. 173, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of Amendment No. 173 180 The maximum rod average bumup for any rod Within 30 days of shall be limited to 60 GWd/mtU until the date of amendment.
completion of an NRC environmental assessment supporting an increased limit.
In association with the ECCS sump strainer Within 30 days of modification and Generic Safety Issue (GSI)- date of amendment 191 requirements: and no later than December 31, 2007
- 1. Unit 1 shall enter Mode 5 for the outage to install the sump strainer modification no later than May 19, 2008 and
- 2. The Unit 1 sump strainer modification shall be completed prior to entry into Mode 4 after May 19, 2008.
Amendment No.
ATTACHMENT 3 DESCRIPTION OF PROPOSED CHANGE AND JUSTIFICATION
Description of Proposed Change The Catawba Unit 1 FOL is marked up to add a new license condition as follows:
"In association with the ECCS sump strainer modification and Generic Safety Issue (GSI)-191 requirements:
- 1. Unit 1 shall enter Mode 5 for the outage to install the sump strainer modification no later than May 19, 2008 and
- 2. The Unit 1 sump strainer modification shall be completed prior to entry into Mode 4 after May 19, 2008."
Justification On November 1, 2006, Duke provided a letter to the NRC which summarized Catawba's plans for installing the ECCS sump strainer modification on Unit 1 in response to the requirements of Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors." This letter discussed in detail Duke's request for a delay in implementing the modification on Unit 1 and provided information concerning final design issues and delays, material delivery delays, ALARA concerns, and a recovery plan. The letter provided the technical justification for the proposed extension to the time limit for implementing the requirements of this GL. The letter also stated Duke's commitment to submit a proposed condition into the Unit 1 FOL to incorporate the proposed modification completion date. The commitment stated that the FOL condition would be submitted no later than November 30, 2006.
This submittal fulfills Duke's commitment to propose the Unit 1 FOL condition. Since no new technical information is being submitted in conjunction with the proposed FOL condition, this submittal is considered administrative in nature.
Following NRC approval of the proposed FOL condition, implementation will be accomplished within 30 days of approval and in any event, no later than December 31, 2007, which is the existing commitment date for resolution of GSI-191 for Catawba Unit 1.
Attachment 3 Page 1
ATTACHMENT 4 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION
No Siqnificant Hazards Consideration Determination As required by 10 CFR 50.91(a) (1), this discussion is provided to demonstrate that the proposed license amendment involves no significant hazards consideration.
Conformance of the proposed amendment to the standards for a determination of no significant hazards as defined in 10 CFR 50.92 is shown in the following:
- 1) The proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed license amendment delineates a new Unit 1 FOL condition to implement a completion date associated with the ECCS sump strainer modification. The proposed license amendment is administrative in nature and is being submitted to fulfill a commitment made in previous Duke licensing correspondence. Therefore, the proposed license amendment has no effect upon either the probability or consequences of an accident previously evaluated.
- 2) The proposed license amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
As stated above, the proposed license amendment is administrative in nature and does not change the manner in which Unit 1 is designed or operated. Therefore, the proposed license amendment cannot create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) The proposed license amendment does not involve a significant reduction in a margin of safety.
Margin of safety is related to the confidence in the ability of the fission product barriers to perform their intended functions. These barriers include the fuel cladding, the reactor coolant system, and the containment. The performance of these barriers will not be affected by the addition of the proposed FOL condition. Being administrative in nature, the proposed license amendment therefore does not involve a significant reduction in any safety margin.
Attachment 4 Page 1
Based on the preceding discussion, it is concluded that the proposed license amendment does not involve a significant hazards consideration finding as defined in 10 CFR 50.92.
Attachment 4 Page 2
ATTACHMENT 5 ENVIRONMENTAL A~NALYSI S
Environmental Analysis Pursuant to 10 CFR 51.22(b), an evaluation of this license amendment request has been performed to determine whether or not it meets the criteria for categorical exclusion set forth in 10 CFR 51.22(c) (9) of the regulations.
Implementation of this amendment will have no adverse impact upon Catawba Unit 1; neither will it contribute to any additional quantity or type of effluent being available for adverse environmental impact or personnel exposure.
It has been determined there is:
- 1. No significant hazards consideration,
- 2. No significant change in the types, or significant increase in the amounts, of any effluents that may be released offsite, and
- 3. No significant increase in individual or cumulative occupational radiation exposures involved.
Therefore, this amendment to the Catawba Unit 1 FOL meets the criteria of 10 CFR 51.22(c) (9) for categorical exclusion from an environmental impact statement.
Attachment 5 Page 1