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| | issue date = 06/13/2016 | | | issue date = 06/13/2016 |
| | title = Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications | | | title = Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications |
| | author name = Limpias O A | | | author name = Limpias O |
| | author affiliation = Nebraska Public Power District (NPPD) | | | author affiliation = Nebraska Public Power District (NPPD) |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:NLS2016038 June 13, 2016 Nebraska Public Power District Always there when you need us U.S. Nuclear Regulatory Commission Attention: | | {{#Wiki_filter:Nebraska Public Power District Always there when you need us 50.90 NLS2016038 June 13, 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk |
| Document Control Desk | | * Washington, D.C. 20555-0001 |
| * Washington, D.C. 20555-0001 | |
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| ==Subject:== | | ==Subject:== |
| Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications Cooper Nuclear Station, Docket No. 50-298, DPR-46 50.90 | | Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications Cooper Nuclear Station, Docket No. 50-298, DPR-46 |
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| ==Reference:== | | ==Reference:== |
| | Letter from Oscar A. Limpias, Nebraska Public Power District, to the U.S. |
| | Nuclear Regulatory Commission, dated September 8, 2015, "License Amendment Request to Replace Figure with Text in Technical Specifications" |
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| Letter from Oscar A. Limpias, Nebraska Public Power District, to the U.S. Nuclear Regulatory Commission, dated September 8, 2015, "License Amendment Request to Replace Figure with Text in Technical Specifications"
| | ==Dear Sir or Madam:== |
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| ==Dear Sir or Madam:==
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| The purpose of this letter is for the Nebraska Public Power District to correct a typographical error identified during the review of the referenced submittal. | | The purpose of this letter is for the Nebraska Public Power District to correct a typographical error identified during the review of the referenced submittal. |
| The proposed licensed amendment request contains a typographical error in Technical Specifications (TS) Section 1.1, Definitions. | | The proposed licensed amendment request contains a typographical error in Technical Specifications (TS) Section 1.1, Definitions. Specifically, DOSE EQUIVALENT 1-131 should be DOSE EQUIVALENT I-131. |
| Specifically, DOSE EQUIVALENT 1-131 should be DOSE EQUIVALENT I-131. Attachment 1 provides the marked up TS page. Attachment 2 provides the final typed format TS page to be issued with the amendment. | | Attachment 1 provides the marked up TS page. Attachment 2 provides the final typed format TS page to be issued with the amendment. |
| The editorial change submitted in this letter does not affect the technical or regulatory analysis included in .the referenced submittal. | | The editorial change submitted in this letter does not affect the technical or regulatory analysis included in .the referenced submittal. |
| This letter contains no regulatory commitments. | | This letter contains no regulatory commitments. |
| Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788. | | Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788. |
| * I declare under penalty of perjury that the foregoing is true and correct. Executed on: O((:J 3 / I (,p r 1 (Date) COOPER NUCLEAR STATION P.O .. Box 98 /Brownville, NE 68321-0098 Telephone: | | * I declare under penalty of perjury that the foregoing is true and correct. |
| (402) 825-3811 /Fax: (402) 825-5211 www.nppd.com NLS2016038 Page 2 of2 /jo Attachments: | | Executed on: O((:J r |
| : 1. Proposed Technical Specifications Revision (Markup) 2. Proposed Technical Specifications Revision (Final Typed Format) cc: Regional Administrator w/ attachments USNRC -Region IV Cooper Project Manager w/ attachments USNRC -NRR Project Directorate IV-1 Senior Resident Inspector w/ attachments USNRC-CNS Nebraska Health and Human Services w/ attachments Department of Regulation and Licensure NPG Distribution w/o attachments CNS Records w/ attachments NLS2016038 Attachment 1 Page 1 of2 Attachment 1 Proposed Technical Specifications Revision (Markup) Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3 | | ~3 / |
| : 1. 1 Definitions rl-131, Definitions 1.1 DOSE EQUIVALENT-4-4-a+ | | 1 I (,p (Date) |
| {continued)
| | COOPER NUCLEAR STATION P.O .. Box 98 /Brownville, NE 68321-0098 Telephone: (402) 825-3811 /Fax: (402) 825-5211 www.nppd.com |
| LEAKAGE LINEAR HEAT GENERATION. 1-133, I* 134, and 1-135 actually present. The DOSE EQUIVALENT 1-131 concentration is calculated as follows: DOSE EQUIVALENT 1-131 = (1-131) + 0.0060 (1-132) + 0.17 (1-133) + 0.0010 (1-134) + 0.029 {1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989. LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or 2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE; c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE; d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall. or vessel wall. The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, {continued).
| | |
| Cooper 1.1-3 Amendment No. 251-NLS2016038 Attachment 2 Page 1 of2 Attachment 2 Proposed Technical Specifications Revision (Final Typed Format) Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3 1.1 Definitions DOSE EQUIVALENT 1-131 (continued) | | NLS2016038 Page 2 of2 |
| LEAKAGE LINEAR HEAT GENERATION RATE (LHGR) Definitions 1.1 1-133, 1-134, and 1-135 actually present. The DOSE EQUIVALENT 1-131 concentration is calculated as follows: DOSE EQUIVALENT 1-131=(1-131)+0.0060 (1-132) + 0.17 (l-133) + 0.0010 (1-134) + 0.029 (1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989. LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE into the drywall, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or 2. LEAKAGE into the drywall atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; b. Unidentified LEAKAGE All LEAKAGE into the drywall that is not identified LEAKAGE; c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE; d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall. The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, (continued)
| | /jo Attachments: 1. Proposed Technical Specifications Revision (Markup) |
| Cooper 1.1-3 Amendment No.}} | | : 2. Proposed Technical Specifications Revision (Final Typed Format) cc: Regional Administrator w/ attachments USNRC - Region IV Cooper Project Manager w/ attachments USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/ attachments USNRC-CNS Nebraska Health and Human Services w/ attachments Department of Regulation and Licensure NPG Distribution w/o attachments CNS Records w/ attachments |
| | |
| | NLS2016038 Page 1 of2 Attachment 1 Proposed Technical Specifications Revision (Markup) |
| | Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3 |
| | |
| | Definitions |
| | : 1. 1 Definitions rl-131, 1.1 |
| | \/;~ |
| | DOSE EQUIVALENT-4-4-a+ 1-133, I* 134, and 1-135 actually present. The DOSE |
| | {continued) EQUIVALENT 1-131 concentration is calculated as follows: |
| | = |
| | DOSE EQUIVALENT 1-131 (1-131) + 0.0060 (1-132) + 0.17 (1-133) + 0.0010 (1-134) + 0.029 {1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989. |
| | LEAKAGE LEAKAGE shall be: |
| | : a. Identified LEAKAGE |
| | : 1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or |
| | : 2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; |
| | : b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE; |
| | : c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE; |
| | : d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall. or vessel wall. |
| | LINEAR HEAT GENERATION. The LHGR shall be the heat generation rate per unit length of RATE(~) fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. |
| | ~ |
| | LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, |
| | {continued). |
| | Cooper 1.1-3 Amendment No. 251- |
| | |
| | NLS2016038 Page 1 of2 Attachment 2 Proposed Technical Specifications Revision (Final Typed Format) |
| | Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3 |
| | |
| | Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 1-133, 1-134, and 1-135 actually present. The DOSE (continued) EQUIVALENT 1-131 concentration is calculated as follows: |
| | DOSE EQUIVALENT 1-131=(1-131)+0.0060 (1-132) + 0.17 (l-133) + 0.0010 (1-134) + 0.029 (1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989. |
| | LEAKAGE LEAKAGE shall be: |
| | : a. Identified LEAKAGE |
| | : 1. LEAKAGE into the drywall, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or |
| | : 2. LEAKAGE into the drywall atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; |
| | : b. Unidentified LEAKAGE All LEAKAGE into the drywall that is not identified LEAKAGE; |
| | : c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE; |
| | : d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall. |
| | LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per unit length of RATE (LHGR) fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. |
| | LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, (continued) |
| | Cooper 1.1-3 Amendment No.}} |
Letter Sequence Supplement |
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Category:Letter type:NLS
MONTHYEARNLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 NLS2024007, Emergency Plan Implementing Procedure 5.7.1, Revision 732024-01-16016 January 2024 Emergency Plan Implementing Procedure 5.7.1, Revision 73 NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector2024-01-15015 January 2024 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector NLS2024004, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20232024-01-10010 January 2024 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2023 NLS2023053, ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-30030 November 2023 ISFSI, Supplement to Exemption Request from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023050, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation NLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023051, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-10-10010 October 2023 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023049, 10 CFR Part 21 Report Regarding HGA Relays2023-09-0606 September 2023 10 CFR Part 21 Report Regarding HGA Relays NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023047, Licensee Guarantees of Payment of Deferred Premiums2023-07-26026 July 2023 Licensee Guarantees of Payment of Deferred Premiums NLS2023033, 10 CFR 50.55a Relief Request RC3-022023-06-27027 June 2023 10 CFR 50.55a Relief Request RC3-02 NLS2023039, Preparation and Scheduling of Operator Licensing Examinations2023-06-0101 June 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2023038, Nebraska Public Power District 2022 Financial Report2023-05-22022 May 2023 Nebraska Public Power District 2022 Financial Report NLS2023031, Annual Radiological Environmental Report2023-05-11011 May 2023 Annual Radiological Environmental Report NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023018, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling NLS2023030, Annual Radioactive Effluent Release Report2023-04-27027 April 2023 Annual Radioactive Effluent Release Report NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes NLS2023027, Annual Report of Individual Exposure Monitoring2023-04-13013 April 2023 Annual Report of Individual Exposure Monitoring NLS2023021, Quality Assurance Program Changes2023-04-10010 April 2023 Quality Assurance Program Changes NLS2023020, Decommissioning Funding2023-03-29029 March 2023 Decommissioning Funding NLS2023019, Property Insurance Coverage2023-03-23023 March 2023 Property Insurance Coverage NLS2023010, Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owner'S Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022054, Preparation and Scheduling of Operator Licensing Examinations2023-01-0505 January 2023 Preparation and Scheduling of Operator Licensing Examinations NLS2022055, Emergency Plan, Revision 812023-01-0404 January 2023 Emergency Plan, Revision 81 NLS2022053, CNS-2022-11 Post Exam Submittal2022-11-22022 November 2022 CNS-2022-11 Post Exam Submittal NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022048, Management Change and Correspondence Update2022-11-0101 November 2022 Management Change and Correspondence Update NLS2022047, Core Operating Limits Report, Cycle 33, Revision 02022-10-14014 October 2022 Core Operating Limits Report, Cycle 33, Revision 0 NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022037, Emergency Plan, Revision 80, Summary of 50.54(q) Analyses2022-08-18018 August 2022 Emergency Plan, Revision 80, Summary of 50.54(q) Analyses NLS2022035, Evacuation Time Estimate Report for Cooper Nuclear Station2022-08-16016 August 2022 Evacuation Time Estimate Report for Cooper Nuclear Station NLS2022031, Licensee Guarantees of Payment of Deferred Premiums2022-07-19019 July 2022 Licensee Guarantees of Payment of Deferred Premiums NLS2022005, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-06-16016 June 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements NLS2022025, Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring2022-06-0606 June 2022 Nebraska Public Power District Letter (NLS2022010) to U.S. Nuclear Regulatory Commission Dated April 5, 2022, Annual Report of Individual Exposure Monitoring NLS2022016, Annual Radiological Environmental Report2022-05-10010 May 2022 Annual Radiological Environmental Report NLS2022020, Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report2022-05-0202 May 2022 Nebraska Public Power District, Cooper Nuclear Station, 2021 Financial Report NLS2022014, Annual Radioactive Effluent Release Report2022-04-27027 April 2022 Annual Radioactive Effluent Release Report NLS2022010, Annual Report of Individual Exposure Monitoring2022-04-0505 April 2022 Annual Report of Individual Exposure Monitoring NLS2022009, Property Insurance Coverage2022-03-23023 March 2022 Property Insurance Coverage NLS2022011, Preparation and Scheduling of Operator Licensing Examinations2022-03-18018 March 2022 Preparation and Scheduling of Operator Licensing Examinations NLS2022004, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 12022-02-0707 February 2022 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Relief Request RR5-01, Revision 1 NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 NLS2021067, ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan2021-12-16016 December 2021 ISFSI - Independent Spent Fuel Storage Installation Decommissioning Funding Plan NLS2021069, Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-12-15015 December 2021 Withdrawal of Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021066, Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 32021-12-10010 December 2021 Response to Nuclear Regulatory Commission'S Request for Additional Information Regarding Alternative Request RI5-02, Revision 3 NLS2021065, Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-012021-12-0606 December 2021 Clarification of Response to Nuclear Regulatory Commission'S Request for Additional Information for Alternative Request RS-01 NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements 2024-01-25
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARNLS2023045, Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2023-11-15015 November 2023 Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2023029, License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks2023-09-0606 September 2023 License Amendment Request to Revise Technical Specifications to Support Inspection of Diesel Fuel Oil Storage Tanks NLS2023017, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2023-05-0303 May 2023 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2023007, Technical Specification Bases Changes2023-04-17017 April 2023 Technical Specification Bases Changes ML21350A0582021-12-21021 December 2021 Withdrawal of an Amendment Request ML21340A2362021-12-20020 December 2021 Issuance of Amendment No. 270 Adoption of Technical Specifications Task Force Traveler TSTF-582, Revision 0, RPV WIC Enhancements NLS2021056, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2021-11-16016 November 2021 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements NLS2021018, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-05-11011 May 2021 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NLS2021015, (CNS) - Technical Specification Bases Changes2021-04-16016 April 2021 (CNS) - Technical Specification Bases Changes NLS2020007, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process NLS2020004, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2020-04-0101 April 2020 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules NLS2019022, Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1)2019-05-23023 May 2019 Application for Technical Specifications Improvement to Eliminate Requirements for Hydrogen/Oxygen Monitors (TSTF-447, Rev. 1) NLS2019020, Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr.2019-05-23023 May 2019 Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit Mcpr. NLS2019011, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2019-02-28028 February 2019 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. NLS2018010, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.2018-06-11011 June 2018 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control. ML18137A2102018-05-10010 May 2018 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016046, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing.2016-08-26026 August 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal and Clarify Surveillance Requirement Usage Rule Application to Section 5.5 Testing. NLS2016038, Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications2016-06-13013 June 2016 Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications ML16120A3702016-04-21021 April 2016 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2016010, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2016-03-22022 March 2016 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program NLS2016002, Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2016-03-11011 March 2016 Application to Revise Technical Specifications to Adopt TSTF 535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. NLS2015103, License Amendment Request to Replace Figure with Text in Technical Specifications2015-09-0808 September 2015 License Amendment Request to Replace Figure with Text in Technical Specifications NLS2014087, License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function2015-01-15015 January 2015 License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function NLS2014030, License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water2014-08-26026 August 2014 License Amendment Request to Delete Condensate Storage Tank as an Alternate Source of Makeup Water NLS2014028, License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications2014-07-17017 July 2014 License Amendment Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications NLS2014035, License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 License Amendment Request to Eliminate Requirements for Post Accident Sampling System for Boiling Water Reactors Using the Consolidated Line Item Improvement Process NLS2014022, License Amendment Request - Revision of Cyber Security Plan Implementation Schedule2014-03-14014 March 2014 License Amendment Request - Revision of Cyber Security Plan Implementation Schedule NLS2013014, License Amendment Request to Revise License Renewal License Condition 2.E2013-02-12012 February 2013 License Amendment Request to Revise License Renewal License Condition 2.E NLS2012042, Nebraska Public Power District (NPPD) - License Amendment Request for DPR- 46 for Cooper Nuclear Station to Revise the Physical Protection Protection License Condition Related to the Cyber Security Plan2012-06-14014 June 2012 Nebraska Public Power District (NPPD) - License Amendment Request for DPR- 46 for Cooper Nuclear Station to Revise the Physical Protection Protection License Condition Related to the Cyber Security Plan ML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio NLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012 Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c) NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a2011-09-16016 September 2011 License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a NLS2011026, License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2011-03-26026 March 2011 License Amendment Request for Administrative Revisions to Technical Specifications and to Remove an Expired One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve ML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves NLS2010043, License Amendment Request on Non-Conservative Battery Terminal Voltage and Specific Gravity in Technical Specification Surveillance Requirements2010-10-29029 October 2010 License Amendment Request on Non-Conservative Battery Terminal Voltage and Specific Gravity in Technical Specification Surveillance Requirements NLS2010006, License Amendment Request to Correct Power Factor Limit and to Incorporate a Generic Revision in Technical Specification Surveillance Requirement 3.8.1.92010-02-25025 February 2010 License Amendment Request to Correct Power Factor Limit and to Incorporate a Generic Revision in Technical Specification Surveillance Requirement 3.8.1.9 ML1001900422010-02-0303 February 2010 Summary of Telephone Conference Call Held on 1/8/2010, Between the U.S. NRC and Nebraska Public Power District Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station ML0934309332009-12-0707 December 2009 SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application Cooper Nuclear Station, Docket No. 50-298, DPR-46 NLS2009084, License Amendment Request for Approval of the Cyber Security Plan2009-11-19019 November 2009 License Amendment Request for Approval of the Cyber Security Plan NLS2009034, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2009-06-0202 June 2009 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process NLS2009010, License Amendment Request to Revise Nonconservative Battery Resistance Technical Specification Surveillance Requirements2009-03-11011 March 2009 License Amendment Request to Revise Nonconservative Battery Resistance Technical Specification Surveillance Requirements ML0829107682008-10-13013 October 2008 Cooper Nuclear Station - License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML0830302502008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Environmental Report, Figure 2.1-1 - Figure 2.3.3 ML0830302462008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix E, Environmental Report ML0830302512008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Environmental Report, Figure 2.4-1 - Figure 2.12-2 ML0830302442008-09-24024 September 2008 Copper Nuclear Station, License Renewal Application, Appendix D, Technical Specification Changes ML0830302362008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Cover Page ML0830302412008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Appendix a, Updated Safety Analysis Report Supplement ML0830302422008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Appendix B, Aging Management Programs and Activities ML0830302432008-09-24024 September 2008 Cooper Nuclear Station, License Renewal Application, Appendix C, Response to BWRVIP Applicant Action Items 2023-09-06
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Nebraska Public Power District Always there when you need us 50.90 NLS2016038 June 13, 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk
Subject:
Supplement to License Amendment Request to Replace Figure with Text in Technical Specifications Cooper Nuclear Station, Docket No. 50-298, DPR-46
Reference:
Letter from Oscar A. Limpias, Nebraska Public Power District, to the U.S.
Nuclear Regulatory Commission, dated September 8, 2015, "License Amendment Request to Replace Figure with Text in Technical Specifications"
Dear Sir or Madam:
The purpose of this letter is for the Nebraska Public Power District to correct a typographical error identified during the review of the referenced submittal.
The proposed licensed amendment request contains a typographical error in Technical Specifications (TS) Section 1.1, Definitions. Specifically, DOSE EQUIVALENT 1-131 should be DOSE EQUIVALENT I-131.
Attachment 1 provides the marked up TS page. Attachment 2 provides the final typed format TS page to be issued with the amendment.
The editorial change submitted in this letter does not affect the technical or regulatory analysis included in .the referenced submittal.
This letter contains no regulatory commitments.
Should you have any questions concerning this matter, please contact Jim Shaw, Licensing Manager, at (402) 825-2788.
- I declare under penalty of perjury that the foregoing is true and correct.
Executed on: O((:J r
~3 /
1 I (,p (Date)
COOPER NUCLEAR STATION P.O .. Box 98 /Brownville, NE 68321-0098 Telephone: (402) 825-3811 /Fax: (402) 825-5211 www.nppd.com
NLS2016038 Page 2 of2
/jo Attachments: 1. Proposed Technical Specifications Revision (Markup)
- 2. Proposed Technical Specifications Revision (Final Typed Format) cc: Regional Administrator w/ attachments USNRC - Region IV Cooper Project Manager w/ attachments USNRC - NRR Project Directorate IV-1 Senior Resident Inspector w/ attachments USNRC-CNS Nebraska Health and Human Services w/ attachments Department of Regulation and Licensure NPG Distribution w/o attachments CNS Records w/ attachments
NLS2016038 Page 1 of2 Attachment 1 Proposed Technical Specifications Revision (Markup)
Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3
Definitions
- 1. 1 Definitions rl-131, 1.1
\/;~
DOSE EQUIVALENT-4-4-a+ 1-133, I* 134, and 1-135 actually present. The DOSE
{continued) EQUIVALENT 1-131 concentration is calculated as follows:
=
DOSE EQUIVALENT 1-131 (1-131) + 0.0060 (1-132) + 0.17 (1-133) + 0.0010 (1-134) + 0.029 {1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989.
LEAKAGE LEAKAGE shall be:
- a. Identified LEAKAGE
- 1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
- 2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;
- b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;
- c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
- d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall. or vessel wall.
LINEAR HEAT GENERATION. The LHGR shall be the heat generation rate per unit length of RATE(~) fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
~
LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit,
{continued).
Cooper 1.1-3 Amendment No. 251-
NLS2016038 Page 1 of2 Attachment 2 Proposed Technical Specifications Revision (Final Typed Format)
Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46 Revised Pages 1.1-3
Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 1-133, 1-134, and 1-135 actually present. The DOSE (continued) EQUIVALENT 1-131 concentration is calculated as follows:
DOSE EQUIVALENT 1-131=(1-131)+0.0060 (1-132) + 0.17 (l-133) + 0.0010 (1-134) + 0.029 (1-135). The dose conversion factors used for this calculation are those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989.
LEAKAGE LEAKAGE shall be:
- a. Identified LEAKAGE
- 1. LEAKAGE into the drywall, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or
- 2. LEAKAGE into the drywall atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;
- b. Unidentified LEAKAGE All LEAKAGE into the drywall that is not identified LEAKAGE;
- c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;
- d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per unit length of RATE (LHGR) fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all TEST logic components required for OPERABILITY of a logic circuit, (continued)
Cooper 1.1-3 Amendment No.