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| | issue date = 09/03/2009 | | | issue date = 09/03/2009 |
| | title = Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System | | | title = Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System |
| | author name = Morris J R | | | author name = Morris J |
| | author affiliation = Duke Energy Carolinas, LLC | | | author affiliation = Duke Energy Carolinas, LLC |
| | addressee name = | | | addressee name = |
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| Duke Energy Carolinas, LLC (Duke)Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414"Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System" In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations, Duke Energy Carolinas, LLC is submitting a request for changes to Catawba Nuclear Station (CNS), Units 1 and 2 Facility Operating Licenses, NPF-35 and NPF-52. The proposed changes would revise the Technical Specification (TS) Section 3.7.10, "Control Room Area Ventilation System (CRAVS)," to allow movement of irradiated fuel with only one CRAVS train OPERABLE. | | Duke Energy Carolinas, LLC (Duke)Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414"Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System" In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations, Duke Energy Carolinas, LLC is submitting a request for changes to Catawba Nuclear Station (CNS), Units 1 and 2 Facility Operating Licenses, NPF-35 and NPF-52. The proposed changes would revise the Technical Specification (TS) Section 3.7.10, "Control Room Area Ventilation System (CRAVS)," to allow movement of irradiated fuel with only one CRAVS train OPERABLE. |
| The requested amendment would revise CNS TS 3.7.10 to be consistent with the NRC approved Standard Technical Specifications (STS).Enclosure 1 provides a description and assessment of the proposed changes.Additional contents of the proposal in,,-e 1,-e 1,following: | | The requested amendment would revise CNS TS 3.7.10 to be consistent with the NRC approved Standard Technical Specifications (STS).Enclosure 1 provides a description and assessment of the proposed changes.Additional contents of the proposal in,,-e 1,-e 1,following: |
| Attachment 1: CNS TS Changes (Mark-Up)Attachment 2: CNS TS Bases Changes (Mark Up)Supporting changes will be made to the TS Bases in accordance with TS 5.5.14, "Technical Specifications Bases Control Program." The affected TS Bases mark up is included in Attachment | | Attachment 1: CNS TS Changes (Mark-Up)Attachment 2: CNS TS Bases Changes (Mark Up)Supporting changes will be made to the TS Bases in accordance with TS 5.5.14, "Technical Specifications Bases Control Program." The affected TS Bases mark up is included in Attachment |
| : 2. These pages are being submitted for information only.Duke Energy requests approval of the proposed license amendment within one calendar year of the License Amendment Request (LAR) submittal date. Duke Energy is requesting a standard 30-day implementation grace period for this license amendment. | | : 2. These pages are being submitted for information only.Duke Energy requests approval of the proposed license amendment within one calendar year of the License Amendment Request (LAR) submittal date. Duke Energy is requesting a standard 30-day implementation grace period for this license amendment. |
| Aioa www. duke-energy, com U.S. Nuclear Regulatory Commission September 3, 2009 Page 2 Implementation of this proposed amendment to the CNS TS will not impact the CNS Updated Final Safety Analysis Report (UFSAR).This LAR has been reviewed and approved by the CNS Plant Operations Review Committee, and the Duke Energy Corporate Nuclear Safety Review Board.In accordance with 10 CFR 50.91 a copy of this application with the enclosure and attachments is being provided to the designated South Carolina state official.There are no new regulatory commitments contained in this submittal. | | Aioa www. duke-energy, com U.S. Nuclear Regulatory Commission September 3, 2009 Page 2 Implementation of this proposed amendment to the CNS TS will not impact the CNS Updated Final Safety Analysis Report (UFSAR).This LAR has been reviewed and approved by the CNS Plant Operations Review Committee, and the Duke Energy Corporate Nuclear Safety Review Board.In accordance with 10 CFR 50.91 a copy of this application with the enclosure and attachments is being provided to the designated South Carolina state official.There are no new regulatory commitments contained in this submittal. |
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| The current requirement of TS 3.7.10 to suspend movement of irradiated fuel should one train of CRAVS become inoperable as implemented with AST approval is more restrictive than TS 3.7.10 of the STS (Reference 1). The additional conservatism of TS 3.7.10 that was implemented with the AST submittal has resulted in unnecessary constraints on plant operation. | | The current requirement of TS 3.7.10 to suspend movement of irradiated fuel should one train of CRAVS become inoperable as implemented with AST approval is more restrictive than TS 3.7.10 of the STS (Reference 1). The additional conservatism of TS 3.7.10 that was implemented with the AST submittal has resulted in unnecessary constraints on plant operation. |
| The changes being proposed within this license amendment request would revise TS 3.7.10 to be consistent with the STS and improve operational flexibility while still ensuring sufficient protection of the health and safety of the public.E1-2 Catawba Nuclear Station I Enclosure 1 Basis for Proposed Changes 4.0 TECHNICAL EVALUTION 4.1 SYSTEM DESCRIPTION Control Room Area Ventilation System (CRAVS) and the Control Room Area Chill Water System (CRAWS) are shared systems at CNS. These two systems provide the normal and emergency ventilation requirements to the Control Room and Control Room Area. The Control Room is maintained at a positive pressure with respect to all adjacent areas. Outside air for pressurization and a portion of the return air from the Control Room pass through a carbon filter train to limit operator radiation exposure during all plant modes. The CRAVS is required to be OPERABLE during all plant modes and during movement of irradiated fuel assemblies. | | The changes being proposed within this license amendment request would revise TS 3.7.10 to be consistent with the STS and improve operational flexibility while still ensuring sufficient protection of the health and safety of the public.E1-2 Catawba Nuclear Station I Enclosure 1 Basis for Proposed Changes 4.0 TECHNICAL EVALUTION 4.1 SYSTEM DESCRIPTION Control Room Area Ventilation System (CRAVS) and the Control Room Area Chill Water System (CRAWS) are shared systems at CNS. These two systems provide the normal and emergency ventilation requirements to the Control Room and Control Room Area. The Control Room is maintained at a positive pressure with respect to all adjacent areas. Outside air for pressurization and a portion of the return air from the Control Room pass through a carbon filter train to limit operator radiation exposure during all plant modes. The CRAVS is required to be OPERABLE during all plant modes and during movement of irradiated fuel assemblies. |
| | | 4.2 JUSTIFICATION As part of the issued license amendment for partial scope implementation of AST, TS 3.7.10 was revised to require during movement of irradiated fuel assemblies two CRAVS trains be required OPERABLE. |
| ===4.2 JUSTIFICATION===
| |
| As part of the issued license amendment for partial scope implementation of AST, TS 3.7.10 was revised to require during movement of irradiated fuel assemblies two CRAVS trains be required OPERABLE. | |
| In the submittal dated March 26, 2002, Attachment 3 Duke Energy states"For Condition A of this LCO, one CRA VS train inoperable, the required action is to restore the CRA VS train to operable status with a Completion Time of seven days. This Allowed Outage Time appears to be inappropriate for the case of movement of irradiated fuel assemblies. | | In the submittal dated March 26, 2002, Attachment 3 Duke Energy states"For Condition A of this LCO, one CRA VS train inoperable, the required action is to restore the CRA VS train to operable status with a Completion Time of seven days. This Allowed Outage Time appears to be inappropriate for the case of movement of irradiated fuel assemblies. |
| During the refueling outages, reactor core unloading and reloading typically require two to three days each. The current TS LCO would permit one train of CRA VS to be inoperable during these fuel handling operations. | | During the refueling outages, reactor core unloading and reloading typically require two to three days each. The current TS LCO would permit one train of CRA VS to be inoperable during these fuel handling operations. |
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Category:Letter
MONTHYEARIR 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 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 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 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 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 IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 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 ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23188A0732023-07-0707 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 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-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 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 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 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 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 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 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 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 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 ML12153A3282012-05-31031 May 2012 Proposed Technical Specifications Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (COLR) License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement Method ML12038A1732012-02-0101 February 2012 Proposed Tech Specs Amendment TS 3.4.13, TS 5.5.9, TS 5.6.8, License Amendment Request to Revise TS for Permanent Alternate Repair Criteria 2023-07-07
[Table view] Category:Technical Specification
MONTHYEARRA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change 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 ML22186A0082022-06-21021 June 2022 SLC Revision to 16.9-22, TS Bases 3.7.7 RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 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-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation 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-18-0219, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-12-0404 December 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System.2018-11-15015 November 2018 Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System. 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-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes 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 RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes 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 RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process CNS-16-046, Technical Specification Bases Changes, B 3.7 Plant Systems2016-06-14014 June 2016 Technical Specification Bases Changes, B 3.7 Plant Systems CNS-16-031, Technical Specification Bases Changes2016-04-26026 April 2016 Technical Specification Bases Changes CNS-16-015, Technical Specification Bases Changes2016-02-18018 February 2016 Technical Specification Bases Changes CNS-15-098, Technical Specification Bases Changes2015-12-14014 December 2015 Technical Specification Bases Changes 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 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 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 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 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 MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements2015-06-23023 June 2015 Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements CNS-15-054, Submittal of Technical Specification Bases Changes 5.5.142015-06-0202 June 2015 Submittal of Technical Specification Bases Changes 5.5.14 CNS-15-021, Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.2015-03-0909 March 2015 Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program. 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-14-079, Technical Specification Bases Changes2014-06-18018 June 2014 Technical Specification Bases Changes CNS-14-055, Technical Specification Bases Changes2014-05-0505 May 2014 Technical Specification Bases Changes CNS-14-032, Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications2014-03-10010 March 2014 Request for Notice of Enforcement Discretion (NOED) Regarding Technical Specifications 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. ML13269A0772013-09-23023 September 2013 Submittal of Technical Specification Bases Changes ML13263A3732013-09-18018 September 2013 Technical Specification Bases Changes ML13109A0802013-04-17017 April 2013 Technical Specification Bases Changes ML12314A0152012-11-0606 November 2012 Technical Specification Bases Changes ML12153A3282012-05-31031 May 2012 Proposed Technical Specifications Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (COLR) License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement Method ML11335A1482011-11-29029 November 2011 Technical Specification Bases Changes ML11327A1492011-11-22022 November 2011 Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML11171A0422011-06-15015 June 2011 Changes to Technical Specification Bases Pursuant to 10CFR 50.4 ML11138A3042011-05-10010 May 2011 Technical Specification Bases Changes, Pursuant to 1OCFR 50.4 ML1108907012011-03-24024 March 2011 Duke Energy Carolinas - Technical Specification Bases Changes ML1026500392010-09-16016 September 2010 License Amendment Request to Revise Technical Specification 5.3, Unit Staff Qualifications 2023-04-24
[Table view] Category:Amendment
MONTHYEARRA-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-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 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-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation 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-18-000, 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 RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - 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 ML12153A3282012-05-31031 May 2012 Proposed Technical Specifications Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (COLR) License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement Method ML11327A1492011-11-22022 November 2011 Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML1026500392010-09-16016 September 2010 License Amendment Request to Revise Technical Specification 5.3, Unit Staff Qualifications ML1019002672010-06-29029 June 2010 License Amendment Request to Revise Reactor Trip System and Engineered Safety Feature Actuation System Technical Specifications ML0928600672009-09-30030 September 2009 Units 1 & 2 and Oconee, Units 1, 2, & 3 - License Amendment Request (LAR) Catawba and McGuire Containment Spray Nozzle and Oconee Reactor Building Spray and Cooling Systems Technical Specification Surveillance Requirement ML0925302402009-09-0303 September 2009 Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System ML0911202002009-02-27027 February 2009 Duke Energy Carolinas, LLC - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0829005322008-10-0202 October 2008 Units 1 and 2 - Amendment to Technical Specification 3.6.13, Ice Condenser Doors, Revised Surveillance Requirements ML0823106722008-09-0808 September 2008 Issuance of Amendments Regarding (TAC MD6961 and MD6962) ML0824900942008-09-0202 September 2008 Technical Specifications (TS) And/Or Bases Sections: 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation 3.3.3, Post Accident Monitoring (PAM) Instrumentation 3.5.4, Refueling Water Storage. ML0819807732008-07-30030 July 2008 Tech Spec Pages for Amendments 243 and 237 Regarding Single Supply Header Operation of the Buried Nuclear Service Water System ML0819801982008-07-14014 July 2008 Proposed Technical Specification Amendment, Technical Specification 3.6.6, Containment Spray System; 3.7.5, Auxiliary Feedwater System ML0813000352008-05-28028 May 2008 Tech Spec Pages for Amendments 241 and 236 Regarding Changes to the Update Final Safety Analysis Report ML0800100042008-01-0202 January 2008 Technical Specifications Related to Amendment No. 239 One-Time Extension of the 1B Emergency Core Cooling System & the Auxiliary Building Filtered Ventilation Exhaust System Allowed Outage Time ML0734804452007-12-11011 December 2007 Units 1 & 2 - Proposed Technical Specification (TS) Amendment to Relax Completion Times and Surveillance Intervals for the Reactor Trip System (RTS) Instrumentation TS 3.3.1, Engineered Safety Feature ML0727601252007-09-27027 September 2007 Application for Technical Specification Change TSTF-491, Removal of the Main Steam (TS 3.7.2) and Main Feedwater (TS 3.7.3) Valve Isolation Times from Technical Specifications, Using the Consolidated Line Item Improvement Process ML0527002472005-09-19019 September 2005 Proposed Technical Specifications and Bases Amendment ML0525902452005-09-13013 September 2005 Proposed Technical Specifications 3.5.2, Emergency Core Cooling System; 3.6.6, Containment Spray System; 3.6.17, Containment Valve Injection Water System; 3.7.5, Auxiliary Feedwater System & 3.7.7, Component Cooling Water System ML0525902472005-09-13013 September 2005 Proposed Technical Specifications 3.7.16, Spent Fuel Assembly Storage, and 4.3, Fuel Storage ML0520202062005-07-0707 July 2005 Units 1 & 2 - License Amendment Request Applicable to Technical Specification 3.9.1, Boron Concentration. ML0516705512005-06-10010 June 2005 Tech Spec Pages for Amendments 225 and 220 Regarding Extending the Interval Between Local Leakage Rate Tests of the Containment Purge and Vent Valves with Resilient Seals ML0501901302005-01-13013 January 2005 Enclosure, Amendment, TS for SG Tube Integrity (Tac No. MB7842, MB7843) ML0426602802004-09-13013 September 2004 Proposed Technical Specifications (TS) Amendments Revision to Steam Generator TS ML0412502172004-04-29029 April 2004 Amendment Nos. 213 and 207, Increasing Flexibility in Mode Restraints ML0409101232004-03-23023 March 2004 Duke Energy Corp License Amendment Request Applicable to Technical Specifications 5.5.7, Reactor Coolant Pump Flywheel Inspection Program, Using the Consolidated Line Item Improvement Process (CLIIP) ML0406500112004-03-0404 March 2004 Amd Nos. 212/206, Re. Heatup, Cooldown, Criticality, and Inservice Test Pressure and Temperature Limits, and LTOP System Pressure-Temperature Limits ML0403002752004-01-15015 January 2004 Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Proposed Technical Specification Amendment TS 3.4.3 - Reactor Coolant System (RCS) Pressure and Temperature (P/T) Limits, TS 3.4.6, RCS Loops - Mode 4, TS 3.4.7, RCS Loops - Mod ML0335803932003-12-19019 December 2003 Technical Specification Pages for Amendments 210 and 204 ML0321304972003-06-25025 June 2003 Proposed Technical Specifications and Bases Amendment 2.0, Safety Limits; 3.3, Instrumentation; 3.4, Reactor Coolant System; 5.6, Reporting Requirements ML0316904972003-06-12012 June 2003 Amendment to Technical Specification 3.6.12 - Ice Bed Revise Ice Mass Surveillance Requirements Supplement and Response to Request for Additional Information ML0309000372003-03-20020 March 2003 Proposed TS Amendment TS 3.4.3 - Reactor Coolant System Pressure & Temperature Limits ML0306900292003-02-25025 February 2003 Application for Amendment to Licenses NPF-35 & NPF-52, to Change & Add Technical Specifications ML0302104322003-01-0808 January 2003 Proposed Technical Specifications (TS) Amendments, Technical Specification 5.5.2 One-Time Extension of ILRT Interval ML0211401132002-04-22022 April 2002 Technical Specifications for Amendments 197 and 190 Eliminating Response Time Testing Requirements for Selected Sensors and Specified Instrumentation to Loops for the Engineered Safety Features and the Reactor Trip System ML0208104712002-03-20020 March 2002 Technical Specifications for Amendments 196 & 189, Revising TS 3.3.2 & TS 3.3.6 ML0206402842002-02-26026 February 2002 Technical Specifications Pages for Amendments 195 & 188 2023-02-16
[Table view] |
Text
Duke JAMES R. MORRIS, VICE PRESIDENT Energy Duke Energy Carolinas, LLC Carolinas Catawba Nuclear Station 4800 Concord Road! CN01 VP York, SC 29745 803-701-4251 803-701-3221 fax September 3, 2009 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke)Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414"Request to Amend Technical Specification (TS) 3.7.10: Control Room Area Ventilation System" In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations, Duke Energy Carolinas, LLC is submitting a request for changes to Catawba Nuclear Station (CNS), Units 1 and 2 Facility Operating Licenses, NPF-35 and NPF-52. The proposed changes would revise the Technical Specification (TS) Section 3.7.10, "Control Room Area Ventilation System (CRAVS)," to allow movement of irradiated fuel with only one CRAVS train OPERABLE.
The requested amendment would revise CNS TS 3.7.10 to be consistent with the NRC approved Standard Technical Specifications (STS).Enclosure 1 provides a description and assessment of the proposed changes.Additional contents of the proposal in,,-e 1,-e 1,following:
Attachment 1: CNS TS Changes (Mark-Up)Attachment 2: CNS TS Bases Changes (Mark Up)Supporting changes will be made to the TS Bases in accordance with TS 5.5.14, "Technical Specifications Bases Control Program." The affected TS Bases mark up is included in Attachment
- 2. These pages are being submitted for information only.Duke Energy requests approval of the proposed license amendment within one calendar year of the License Amendment Request (LAR) submittal date. Duke Energy is requesting a standard 30-day implementation grace period for this license amendment.
Aioa www. duke-energy, com U.S. Nuclear Regulatory Commission September 3, 2009 Page 2 Implementation of this proposed amendment to the CNS TS will not impact the CNS Updated Final Safety Analysis Report (UFSAR).This LAR has been reviewed and approved by the CNS Plant Operations Review Committee, and the Duke Energy Corporate Nuclear Safety Review Board.In accordance with 10 CFR 50.91 a copy of this application with the enclosure and attachments is being provided to the designated South Carolina state official.There are no new regulatory commitments contained in this submittal.
Inquiries regarding this submittal should be directed to Adrienne F. Driver, Catawba Regulatory Compliance at 803-701-3445.
Sincerely, Ja es R. Morris Site Vice President, Catawba Nuclear Station Enclosure with Attachments U.S. Nuclear Regulatory Commission September 3, 2009 Page 3 Mr. 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.
James " orris, CNS Site Vice President Subscribed and sworn to me Date Notary Public Notary Public, South Carolina, State at Large My Commission Expires: My Commission Expires March 6,2018 Date SEAL " o- If -..
U.S. Nuclear Regulatory Commission September 3, 2009 Page 4 xc w/Enclosures and Attachments:
U.S. Nuclear Regulatory Commission Mr. Luis A. Reyes, NRC Region II Administrator U.S. Nuclear Regulatory Commission
-Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. Jon Thompson, NRC Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Mail Stop 0-8 G9A Washington, D.C. 20555 Mr. A. Hutto, NRC Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station State of South Carolina Official S.E. Jenkins, Section Manager Division of Waste Management S.C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 U.S. Nuclear Regulatory Commission September 3, 2009 Page 5 bxc w/Enclosures and Attachments:
Lisa F. Vaughn A. Driver, CNS RGC R.D. Hart, CNS RGC Manager Geoff G. Pihl, NGO/REN K.L. Ashe (MG01RC)Robert Meixell (ON03RC)NCMPA-1, CNS Owner NCEMC, CNS Owner PMPA, CNS Owner R.L. Gill, NRI&IA Manager (EC05P)ELL-ECO50 RGC Date File Document Control File 801.01 I e Duke Energy The proposed change would revise Technical Specification (TS)3.7.10, "Control Room Area Ventilation System (CRAVS)" along with the corresponding Bases section of TS 3.7.10. This amendment requests that only one train of CRAVS be required OPERABLE during movement of irradiated fuel assemblies.
Catawba Nuclear Station, Regulatory Compliance Catawba Nuclear Station Enclosure 1 Basis for Proposed Changes
1.0 DESCRIPTION
This is a request to amend Operating License NPF-35 and NPF-52 for Catawba Nuclear Station Units 1 and 2. The proposed changes would revise Technical Specification (TS) 3.7.10,."Control Room Area Ventilation System (CRAVS)" along with the corresponding Bases section of TS 3.7.10. This amendment requests that only one train of CRAVS be required OPERABLE during movement of irradiated fuel assemblies.
The proposed changes to TS 3.7.10 would conform to the Industry Standard Technical Specification (STS) and achieve a higher degree of standardization and consistency with Duke's other nuclear sites and the industry (Reference 1).
2.0 PROPOSED CHANGE
S The following changes are proposed: TS 3.7.10 Control Room Area Ventilation System (CRAVS)* Condition D is revised by adding "or during movement of irradiated fuel assemblies" to the end of the Condition D.* The required action of Condition D is revised by adding "OR" after Required Action D.1 and adding a new Required Action D.2 which states "Suspend movement of irradiated fuel assemblies."* Condition E is revised from "Two CRAVS trains inoperable in MODE 5 or 6, or one or more CRAVS trains inoperable during movement of irradiated fuel assemblies" to "Two CRAVS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies."
3.0 BACKGROUND
On April 23, 2002 the Nuclear Regulatory Commission amended the Facility Operating Licenses at CNS for partial scope implementation of the alternative source term (AST) (Reference 4). As part of the license amendment for partial scope implementation of AST, TS 3.7.10 was revised to require suspension of movement of irradiated fuel should one train of CRAVS become inoperable.
As stated in the submittal dated March 26, 2002, the allowed outage time for Condition A of TS 3.7.10 of the STS "appears to be inappropriate for the case of movement of irradiated fuel assemblies-(Reference 2)." After further assessment, the LCO conditions, required.actions and completion times of TS 3.7.10 of the STS are appropriate.
The current requirement of TS 3.7.10 to suspend movement of irradiated fuel should one train of CRAVS become inoperable as implemented with AST approval is more restrictive than TS 3.7.10 of the STS (Reference 1). The additional conservatism of TS 3.7.10 that was implemented with the AST submittal has resulted in unnecessary constraints on plant operation.
The changes being proposed within this license amendment request would revise TS 3.7.10 to be consistent with the STS and improve operational flexibility while still ensuring sufficient protection of the health and safety of the public.E1-2 Catawba Nuclear Station I Enclosure 1 Basis for Proposed Changes 4.0 TECHNICAL EVALUTION 4.1 SYSTEM DESCRIPTION Control Room Area Ventilation System (CRAVS) and the Control Room Area Chill Water System (CRAWS) are shared systems at CNS. These two systems provide the normal and emergency ventilation requirements to the Control Room and Control Room Area. The Control Room is maintained at a positive pressure with respect to all adjacent areas. Outside air for pressurization and a portion of the return air from the Control Room pass through a carbon filter train to limit operator radiation exposure during all plant modes. The CRAVS is required to be OPERABLE during all plant modes and during movement of irradiated fuel assemblies.
4.2 JUSTIFICATION As part of the issued license amendment for partial scope implementation of AST, TS 3.7.10 was revised to require during movement of irradiated fuel assemblies two CRAVS trains be required OPERABLE.
In the submittal dated March 26, 2002, Attachment 3 Duke Energy states"For Condition A of this LCO, one CRA VS train inoperable, the required action is to restore the CRA VS train to operable status with a Completion Time of seven days. This Allowed Outage Time appears to be inappropriate for the case of movement of irradiated fuel assemblies.
During the refueling outages, reactor core unloading and reloading typically require two to three days each. The current TS LCO would permit one train of CRA VS to be inoperable during these fuel handling operations.
Consequently, changes to the Conditions and Required Actions associated with this LCO are being proposed." Upon further review of plant operation and system design, it has been concluded that the requirement for both CRAVS trains to be OPERABLE during movement of irradiated fuel assemblies is not necessary.
Requiring two CRAVS trains OPERABLE added unnecessary' conservatism and more restrictive operational practices with respect to movement of irradiated fuel during refueling outages and dry cask storage. In addition, the credited single failure of one CRAVS train is acceptable and meets the requirements for GDC 22. There are no fuel types, operational practices, or unique design features that should require Catawba to have more restrictive TS for the Control Room Ventilation System than the industry standard.
This amendment requests that during movement of irradiated fuel assemblies, only one train of CRAVS be required OPERABLE and in operation.
Current standard operational practices require one filter train in operation during movement of irradiated fuel assemblies.
If the online filter train fails to run, the redundant filter train is available.
Equipment such as the CRAVS that is credited with post accident functions'is Class 1 E and capable of performing these functions with a single active failure.Currently Condition D of TS 3.7.10 requires both CRAVS trains OPERABLE during movement of irradiated fuel assemblies.
This License Amendment Request (LAR) proposes changing Condition D to add the statement "or during movement of irradiated fuel assemblies" to the end of Condition D. This change is coupled with an additional change to Condition D to add an "OR" after Required Action D.1 and a new Required Action D.2 which states "Suspend movement of irradiated fuel assemblies." As a result, the requirement to suspend movement of irradiated fuel if one CRAVS train is inoperable will be removed from Condition E. The proposed revision of E1-3 Catawba Nuclear Station Enclosure 1 Basis for Proposed Changes Condition D provides an option in TS 3.7.10 to immediately place the operable CRAVS train in operation or suspend movement of irradiated fuel should the other CRAVS train be inoperable.
This proposed revision will change Condition D to be consistent with the STS.Condition E is revised to state "Two CRAVS trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies." This change will effectively move the Required Action of suspending fuel movement from Condition E to Condition D.4.3 TECHNICAL EVALUATION CONCLUSION Movement of irradiated fuel assemblies with one train of CRAVS OPERABLE does not invalidate nor change the current analysis of radiological consequences for the fuel handling accident (Reference 2, 3, and 4). In review of the single failure criteria for the postulated fuel handling accident, industry plant operation, site system.design and current radiological analysis, the proposed changes to TS 3.7.10 continue to ensure the protection of the health and safety of the public.It has been determined for Condition D of TS 3.7.10 for the allowed outage time associated with movement of irradiated fuel assemblies, the STS LCO, the Required Action and Completion Times are appropriate and applicable to CNS.5.0 REGULATORY ANALYSIS 5.1 APPLICABLE REGULATORY REQUIREMENTS 10 CFR 50, Appendix A, Criterion 16 "Containment Design," in part states that Reactor containment and associated systems shall be provided to establish an essential leak-tight barrier against the uncontrolled release of radioactivity to the environment, and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require.10 CFR 50, Appendix A, Criterion 19, "Control Room," in part states that a control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents.
10 CFR 50, Appendix A, Criterion 22," in part states that the protection system shall be designed to assure that the effects of natural phenomena, and of normal operating, maintenance, testing and postulated accident conditions on redundant channels do not result in. loss of protection function, or shall be demonstrated to be acceptable on some other defined basis.10 CFR 50, Appendix A, Criterion 41, "Containment Atmosphere Cleanup," in part states that..."Systems to control fission products, hydrogen, oxygen, and other substances which may be released into the reactor containment shall be provided as necessary to reduce, consistent with the functioning of other associated systems, the concentration and quality of fission products released to the environment following postulated accidents, and to control the concentration of hydrogen or oxygen and other substances in the containment atmosphere following postulated accidents to assure that Containment integrity is maintained." In review of the GDCs the proposed amendment to TS 3.7.10 does not impact the conformance to the above applicable design criteria.EI-4 Catawba Nuclear Station Enclosure 1 6 Basis for Proposed Changes 5.2 SIGNIFICANT HAZARDS CONSIDERATION Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed changes do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configurations of the facility.
The proposed changes do not alter or prevent the ability of structure, systems and components (SSCS) to perform their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. This is a revision to the TS for the control room ventilation system which is a mitigation system designed to minimize unfiltered air inleakage into the control room and to filter the Control Room atmosphere to protect occupants following an accident previously analyzed.
The Control Room ventilation system is not an initiator or precursor to any accident previously evaluated.
Therefore, the probability or consequences of any accident previously evaluated are not increased.
Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
This revision will not impact the accident analysis.
The change will not alter the requirements of the Control Room ventilation system or its function during accident conditions.
No new or different accidents result from the changes proposed.
The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or significant changes in methods governing normal plant operation.
The changes do not alter assumptions made in the safety analysis.
The proposed changes are consistent with the safety analyses assumptions.
Therefore, it is concluded that these changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.
Does the proposed change involve a significant reduction in margin of safety?The proposed changes do not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operations are determined.
The safety analysis acceptance criteria are not affected by these changes. The proposed changes will not result in plant operation in a configuration outside the design basis for an acceptable period of time without compensatory measures.
The proposed changes do not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
It is therefore concluded that the proposed changes do not involve a significant reduction in the margin of safety.5.3 REGULATORY ANALYSIS CONCLUSION In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2)such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.E1-5 Catawba Nuclear Station Enclosure 1 Basis for Proposed Changes 6.0 ENVIRONMENTAL EVALUATION The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c) (9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be'prepared in connection with the proposed amendment.
E1-6 Catawba Nuclear Station Enclosure 1 Basis for Proposed Changes
7.0 REFERENCES
- 1. U.S. Nuclear Regulatory Commission, NUREG-1431, "Standard Technical Specifications Westinghouse Plants," Volumes 1 and 3, Revision 3, March 2004.2. Gary R. Peterson (CNS) to U.S. Nuclear Regulatory Commission, "Duke Energy Corporation, Catawba Nuclear Station Units 1 and 2, Docket Numbers 50-416 and 50-414, Proposed Amendment to Technical Specifications (TS) 3.7.10, Control Room Area Ventilation System, TS 3.7.11, Control Room Area Chilled Water System, TS 3.7.13, Fuel Handling Ventilation Exhaust System, and TS 3.9.3, Containment Penetrations," December 20, 2001.3. Gary R. Peterson (CNS) to U.S. Nuclear Regulatory Commission, "Duke Energy Corporation, Catawba Nuclear Station Units 1 and 2, Docket Numbers 50-416 and 50-414, Proposed Amendment to Technical Specifications (TS) 3.7.10, Control Room Area Ventilation System, TS 3.7.11, Control Room Area Chilled Water System, TS 3.7.13, Fuel Handling Ventilation Exhaust System, and TS 3.9.3, Containment Penetrations," March 26, 2002.4. Chandu P. Patel (U.S. Nuclear Regulatory Commission) to G.R. Peterson (CNS), "Catawba Nuclear Station, Units 1 and 2 Re: Issuance of Amendments (TAC Nos. MB3758 and MB3759)," April 23, 2002.E 1-7 Attachment 1 Technical Specification (Mark Up)
Attachment 2: Technical Specification Bases (Mark Up)
S CRAVS 3.7.10 REQUIRED ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C. 1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1,2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Required Action and D.1 Place OPERABLE CRAVS Immediately associated Completion train in operation.
Time of Condition A not met in MODE 5 or 6, or OR during movement of irradiated fuel D.2 Suspend movement of assemblies.
irradiated fuel assemblies.
E. Two CRAVS trains E.1 Suspend movement of Immediately inoperable in MODE 5 irradiated fuel assemblies.
or 6, or one or more CRAVS trains i*neperable-during movement of irradiated fuel assemblies.
OR One or more CRAVS trains inoperable due to an inoperable CRE boundary in MODE 5 or.6, or during movement of irradiated fuel assemblies.
F. Two CRAVS trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.(continued)
Catawba Units 1 and 2 3.7.10-2 Amendment Nos. 250/245 low CRAVS B 3.7.10 BASES ACTIONS (continued)
D.1 In MODE 5 or 6, if the inoperable CRAVS train cannot be restored to OPERABLE status within the required Completion Time, or during movement of irradiated fuel assemblies, action must be taken to immediately place the OPERABLE CRAVS train in operation.
This action ensures that the operating (or running) train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure would be readily detected.An alternative to Required Action D.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of the CRE. This places the unit in a condition that minimizes risk. This does not preclude the movement of fuel to a safe position.E. 1 In MODE 5 or 6, or during movement of irradiated fuel assemblies, with two CRAVS trains inoperable, or during movement of irradiated fuel assemblies with one or more CRAVS trains inoperable due to an inoperable CRE boundary, action must be taken immediately to suspend activities that could result in a release of radioactivity that might require isolation of the 1 CRE. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel to a safe position.F. 1 If both CRAVS trains are inoperable in MODE 1, 2, 3, or 4, for reasons other than Condition B, the CRAVS may not be capable of performing the intended function and the unit is in a condition outside the accident analyses.
Therefore, LCO 3.0.3 must be entered immediately.
G.1 and G.2 With one or more CRAVS heaters inoperable, the heater must be restored to OPERABLE status within 7 days. Alternatively, a report must be initiated per Specification 5.6.6, which details the reason for the heater's inoperability and the corrective action required to return the heater to OPERABLE status.The heaters do not affect OPERABILITY of the CRAVS filter trains because carbon adsorber efficiency testing is performed at 300C and 95%Catawba Units 1 and 2 B 3.7.10-8 Revision No. 5