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Category:Letter
MONTHYEARML24227A0822024-09-0303 September 2024 Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value IR 05000298/20240052024-08-22022 August 2024 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005) IR 05000298/20240022024-07-25025 July 2024 Integrated Inspection Report 05000298/2024002 ML24183A1722024-07-17017 July 2024 Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML24197A1462024-07-15015 July 2024 NRC Region IV Ltr to Cooper Nuclear Station Re FEMA Level 1 Finding IR 05000298/20243012024-07-12012 July 2024 NRC Examination Report 05000298/2024301 ML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 ML24197A0682024-06-24024 June 2024 FEMA Ltr to Missouri State Emergency Management Agency - Level 1 Finding, 24 June 2024 ML24192A0112024-06-13013 June 2024 2024-06-Post Exam Comments IR 05000298/20244012024-06-0404 June 2024 Security Baseline Inspection Report 05000298/2024401 ML24151A1082024-05-30030 May 2024 NRC Initial Operator Licensing Examination Approval 05000298/2024301 ML24137A0942024-05-17017 May 2024 Regulatory Audit Plan in Support of License Amendment Request to Modify Allowable Value Regarding Technical Specification for High Pressure Coolant Injection Pump Discharge Low Flow IR 05000298/20240012024-05-0303 May 2024 Integrated Inspection Report 05000298/2024001 ML24129A0952024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000298/20240102024-04-24024 April 2024 Comprehensive Engineering Team Inspection Report 05000298/2024010 ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) ML24093A2282024-04-0202 April 2024 Notice of Enforcement Discretion for Cooper Nuclear Station IR 05000298/20240902024-04-0101 April 2024 – Notice of Violation, NRC Inspection Report 05000298/2024090 IR 05000298/20230062024-02-28028 February 2024 Annual Assessment Letter for Cooper Nuclear Station - Report 05000298/2023006 IR 05000298/20230042024-02-12012 February 2024 Integrated Inspection Report 05000298/2023004 ML24033A3092024-02-12012 February 2024 Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230122024-02-12012 February 2024 NRC Inspection Report 05000298/2023012 ML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23311A1122023-11-0909 November 2023 Project Manager Assignment IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report ML23102A0282023-04-19019 April 2023 U.S. Nuclear Regulatory Commission Presentation at the May 8, 2023, Brownville Village Meeting IR 05000298/20230012023-04-17017 April 2023 Integrated Inspection Report 05000298/2023001 ML23060A1582023-03-0808 March 2023 Design Basis Assurance Inspection (Programs) Inspection Report 05000298/2023001 IR 05000298/20220062023-03-0101 March 2023 Annual Assessment Letter for Cooper Nuclear Station Report 05000298/2022006 ML23041A1622023-02-10010 February 2023 Licensed Operator Positive Fitness-for-Duty Test Request for Additional Information IR 05000298/20220042023-01-30030 January 2023 Integrated Inspection Report 05000298/2022004 IR 05000298/20220112022-12-23023 December 2022 License Renewal Phase 4 Inspection Report 05000298/2022011 ML22286A2072022-11-30030 November 2022 Issuance of Amendment No. 272 Revision to Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements IR 05000298/20220032022-10-27027 October 2022 Integrated Inspection Report 05000298/2022003 ML22304A0052022-10-26026 October 2022 Surveillance Capsule Location (Re-insertion Into the Reactor Vessel) IR 05000298/20223022022-10-20020 October 2022 NRC Initial Operator Licensing Examination Approval 05000298/2022302 ML22276A1562022-10-0505 October 2022 Notification of Commercial Grade Dedication Inspection 05000298/2023011 and Request for Information 2024-09-03
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 NLS2024025, License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation2024-05-0909 May 2024 License Amendment Request to Revise Technical Specifications Table 3.3.2.1-1, Control Rod Block Instrumentation NLS2024024, Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation2024-04-0101 April 2024 Emergency License Amendment Request to Revise Technical Specifications 3.3.1.1, Reactor Protection (RPS) Instrumentation NLS2024001, Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow2024-02-16016 February 2024 Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow 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 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 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 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 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 2024-07-03
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NLS2016038 June 13, 2016 Nebraska Public Power District Always there when you need us 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 50.90
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 3 / I (,p r 1 (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 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
- 1. 1 Definitions rl-131, Definitions 1.1 DOSE EQUIVALENT-4-4-a+
{continued)
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)
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)
Cooper 1.1-3 Amendment No.