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Category:Letter type:NLS
MONTHYEARNLS2024053, Licensee Guarantees of Payment of Deferred Premiums2024-07-30030 July 2024 Licensee Guarantees of Payment of Deferred Premiums NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024 Data from Metamic Coupon Sampling Program NLS2024052, Supplement to the Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow2024-07-24024 July 2024 Supplement to the Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow NLS2024051, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program2024-07-0303 July 2024 Supplement to the Application to Revise Technical Specifications to Adopt TSTF-374, Revision to Diesel Fuel Oil Testing Program NLS2024025, License Amendment Request to Revise Technical Specifications 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the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation2024-04-0303 April 2024 Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) 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 NLS2024018, Property Insurance Coverage2024-03-20020 March 2024 Property Insurance Coverage NLS2024017, Response to an Apparent Violation in NRC Inspection Report 05000298/2023012; EA-24-0012024-03-0808 March 2024 Response to an Apparent Violation in NRC Inspection Report 05000298/2023012; EA-24-001 NLS2024009, Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Support Inspection of2024-03-0808 March 2024 Response to Nuclear Regulatory Commission Request for Additional Information Regarding Application to Revise Technical Specifications to Support Inspection of 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 NLS2024006, Response to Nuclear Regulatory Commissions Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commissions Request for Additional Information for Relief Request RC3-02 NLS2024006, 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 2024-07-30
[Table view] Category:Technical Specifications
MONTHYEARNLS2024025, 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 ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) NLS2024027, Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) Instrumentation2024-04-0303 April 2024 Response to NRC Request for Additional Information Regarding Application for the Emergency License Amendment Request to Revise Technical Specifications 3 .3 .1.1, Reactor Protection (RPS) 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 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 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 NLS2021041, Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program2021-07-20020 July 2021 Request for Exception from Leak Testing Requirement of the Primary Containment Leakage Rate Testing Program ML20314A2352020-12-0202 December 2020 Issuance of Amendment No. 268 Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, Using the Consolidated Line Item Improvement Process ML19238A0072019-10-30030 October 2019 Issuance of Amendment No. 263 Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation ML18218A4832018-09-0606 September 2018 Issuance of Amendment No. 261 Safety Limit Minimum Critical Power Ratio ML18137A2102018-05-10010 May 2018 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 ML15343A3012016-01-22022 January 2016 Issuance of Amendment No. 253 to Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML16021A3222016-01-12012 January 2016 Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function ML15216A2592015-08-27027 August 2015 Issuance of Amendment No. 252, Revise Technical Specification 3.5.2, ECCS - Shutdown, to Delete Condensate Storage Tank as Alternate Source of Makeup Water ML15168A1712015-07-14014 July 2015 Issuance of Amendment No. 251, Request to Move Linear Heat Generation Rate (LHGR) and Single Loop Operation LHGR Limit from Technical Requirements Manual to Technical Specifications ML15135A0052015-05-29029 May 2015 Issuance of Amendment No. 250, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-413, Elimination of Requirements for a Post Accident Sampling System (PASS) 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 ML14055A0232014-04-29029 April 2014 Issuance of Amendment No. 248, Adopt National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for LWR Electric Generating Plants ML13191A1052013-09-12012 September 2013 Issuance of Amendment No. 247, Revise License Condition 2.E to Require All License Renewal Commitments Will Be Incorporated Into the Updated Safety Analysis Report ML13085A0962013-03-29029 March 2013 Corrected Technical Specification (TS) and Safety Evaluation Pages for Amendment No. 245, Revise TS 3.4.9, RCS Pressure and Temperature (P/T) Limits, to Revise Limit Curves and Surveillance Requirements ML12157A2062012-05-30030 May 2012 License Amendment Request to Revise Technical Specifications - Safety Limit Minimum Critical Power Ratio ML1136302582012-01-31031 January 2012 Issuance of Amendment No. 240, Revise Technical Specification 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection NLS2011086, Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves2011-10-0606 October 2011 Supplement to License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves 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 ML1101002912011-01-0505 January 2011 Cooper - License Amendment Request for Reducing the Number of Technical Specification 3.4.3 Required Safety Relief Valves 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 ML0906207232009-02-26026 February 2009 Corrected Technical Specification Pages Regarding Reactor Equipment Cooling System Margin Amendment ML0815402852008-06-30030 June 2008 Technical Specifications, Measurement Uncertainty Recapture Power Uprate ML0812202892008-05-12012 May 2008 Technical Specification Pages for Issuance of Amendment No. 230 Control Room Habitability, TSTF-448 NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-05-0909 May 2008 Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate NLS2007079, Corrected Technical Specification Pages2007-11-0505 November 2007 Corrected Technical Specification Pages NLS2007048, License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve2007-08-16016 August 2007 License Amendment Request for a One-Time Exception to the Five-Year Test Frequency for a Single Safety Valve ML0630405382006-10-31031 October 2006 Tech Spec Pages for Amendment 226 Regarding MSIV Leakage Exemption from 10 CFR Part 50, Appendix J ML0629602942006-10-23023 October 2006 Technical Specification, Revised Limiting Condition for Operation (LCO) 3.10.1, Scram Time Testing Activities ML0627700902006-10-0303 October 2006 Technical Specification Pgs Amd #224 - Issuance of Amendment Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0625003012006-09-0606 September 2006 Technical Specifications, Technical Specification (TS) Changes Associated with Inservice Testing Program, Section 5.5.6, Under TS Programs and Manuals, MD0335 ML0624900372006-09-0505 September 2006 Technical Specifications, Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences and Related Technical Specification Changes, MC8566 NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation2006-06-16016 June 2006 License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation ML0612403772006-05-0303 May 2006 Correction to Amendment No. 218, Technical Specification Page 3.1-12 ML0612304692006-05-0202 May 2006 Technical Specifications, Changes to TS Leakage Limit for the Main Stream Isolation Valves ML0611802442006-04-27027 April 2006 Technical Specifications, Revised Pressure Vessel Fluence and Pressure Temp Curve Applicability to 30 Effective Full-Power Years of Operation ML0611001622006-04-18018 April 2006 Corrected Technical Specification Page 3.9-1 Re Refueling Operations NLS2006039, Corrected Technical Specification Page from Amendment No. 2182006-04-17017 April 2006 Corrected Technical Specification Page from Amendment No. 218 ML0609004412006-03-30030 March 2006 Technical Specification Pages, Change Request for Various Sections ML0628404572006-03-10010 March 2006 Tech Spec Pages for Amendment 217 Regarding Revise Technical Specifications Instrumentation Definitions NLS2006013, License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program2006-03-0707 March 2006 License Amendment Request to Update the American Society of Mechanical Engineers Code Referenced in TS Section 5.5.6, Inservice Testing Program NLS2006002, License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval2006-01-30030 January 2006 License Amendment Request for a One-Time Extension of Containment Integrated Leakage Rate Test Interval NLS2006001, Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2006-01-30030 January 2006 Application for TS Change to Add LCO 3.0.8 on Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0602002922006-01-16016 January 2006 Cooper Nuclear Station - Revised and Supplemental Pages to License Amendment Request for Application of the Alternative Source Term for Reevaluation of the Fuel Handling Accident Dose Consequences 2024-05-09
[Table view] |
Text
N Nebraska Public Power District Always there when you need us NLS2008046 May 9, 2008 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K. Measurement Uncertainty Recapture Power Uprate Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
- 1) Letter from Carl F. Lyon, U.S. Nuclear Regulatory Commission, to Stewart B. Minahan, Nebraska Public Power District, dated May 2, 2008, "Cooper Nuclear Station - Request for Additional Information RE:
Measurement Uncertainty Recapture Power Uprate (TAC No. MD7385)"
- 2) Letter from Stewart B. Minahan, Nebraska Public Power District, to the U.S. Nuclear Regulatory Commission, dated April 4, 2008, "Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate"
- 3) Letter from Stewart B. Minahan, Nebraska Public Power District, to the U.S. Nuclear Regulatory Commission, dated November 19, 2007, "License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate"
Dear Sir or Madam:
The purpose of this letter is for the Nebraska Public Power District (NPPD) to submit its response to the Nuclear Regulatory Commission (NRC) Request for Additional Information (RAI) from the Instrumentation and Controls Branch (EICB), sent on May 2, 2008 (Reference 1). This RAI is related to the license amendment request (LAR) that would revise the Cooper Nuclear Station (CNS) Technical Specifications (TS) for Measurement Uncertainty Recapture power uprate. This LAR was submitted by NPPD letter dated November 19, 2007 (Reference 3),
as updated by NPPD letter dated April 4, 2008 (Reference 2).
In response to Question 1 of the RAI (Reference 1), NPPD is withdrawing the revised TS pages submitted in its April 4, 2008 letter (Reference 2), thus reverting to the specific pages provided in the November 19, 2007 submittal (Reference 3).
COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402) 825-5211 wvww.nppd.com"
NLS2008046 Page 2 of 3 In response to Question 2 of the RAI (Reference 1), NPPD is resubmitting TS Page 3.3-6 for NRC consideration. The TS pages submitted November 19, 2007 (Reference 3) along with the resubmitted TS page included with this submittal incorporate all changes through Amendment 229. contains the response to the NRC EICB RAI questions from Reference 1. contains the markup and clean TS page in response to the RAI Question 2. contains a copy of the TS Bases pages that explain how setpoints are selected for information. These TS Bases pages are unaffected by the proposed changes to TS Page 3.3-6.
NPPD has determined that the specific TS page changes are editorial in nature in that the changes provide clarification and do not impose new requirements nor delete any requirements contained in the preceding submittals. NPPD has determined that the changes do not impact the Technical or Regulatory Safety Analysis, nor do they change the conclusion of the No Significant Hazards Consideration evaluation submitted in Reference 3.
Should you have any questions regarding this submittal, please contact David Van Der Kamp, Licensing Manager, at (402) 825-2904.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on #] Y20 Sincerely, Stewart B. Minahan Vice President - Nuclear and Chief Nuclear Officer
/dm Attachments (3)
NLS2008046 Page 3 of 3 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
NLS2008046 Page 1 of 2 Attachment 1 Response to Instrumentation and Controls Branch Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Measurement Uncertainty Recapture Power Uprate Cooper Nuclear Station, Docket No. 50-298, DPR-46 The Nuclear Regulatory Commission (NRC) Request for Additional Information questions from the Instrumentation and Controls Branch are shown in italics. The Nebraska Public Power District (NPPD) responses are shown in block font.
I1. NRC Request Page 1 ofAttachment 6 stated that the originallyproposed 9.85% is incorrect, and you will revise the value to 9.84%. It seems that you calculated 1001/61.016 = 9.8425%, and rounded off the value to 9.84%. Since the Rod Worth Minimizer (R WM) blocks erroneous operationof a control rod at low power, should the permissive setpoint be 9.85% instead of 9.84%o, to be more conservative?
NPPD Response The change to 9.84% was to be consistent with setpoint calculation NEDC 92-050R, Section 3.15. This conversion to the post-uprated power level value was only calculated to the second digit since the converted value is not what NPPD uses to calculate the permissive setpoint for the Rod Block Monitor (RBM). NPPD uses 10% of rated Feedwater and Main Steam flow at the originally licensed power level (2381 MWth) as the analytical limits for calculating the permissive setpoints (see NEDC 92-050R, Section 2.2) that ensure the RBM is not bypassed below 10% of originally Rated Thermal Power (RTP).
Since NPPD establishes the permissive setpoints based on 10% of originally licensed Feedwater and Main Steam flow, not the converted RTP value of 9.84%, rounding up to 9.85% has no affect on the setpoints. Per this letter, NPPD is withdrawing the proposed change contained in Attachment 7 of Reference 2, and reverting to using 9.85% in Technical Specifications (TS). This change back to the previously submitted value does not impact the Technical or Regulatory evaluation, nor does it impact the No Significant Hazards determination provided in the November 19, 2007 submittal.
NLS2008046 Page 2 of 2
- 2. NRC Request In Attachment 1, you stated that the APRM Neutron Flux-High (Flow Biased) is a safety-limit-related limitingsafety system setting, but that you would not use the guidance provided in the NRC to NEI letter dated September 7, 2005. The letterprovided an acceptable means to the NRC staff of meeting the requirements of 10 CFR 50.36. If you will not use the guidance of the letter,you should provide another means acceptable to the staff or the staff will be unable to determine thatyour proposed change meets the regulatory requirements.
NPPD Response In NPPD's April 4, 2008 response, NPPD stated that the Technical Specification Task Force (TSTF) had proposed an approach, reflected in TSTF Traveler 493, Revision 3, that has generically addressed the issues related to setpoint allowable values discussed in the NRC letter to Nuclear Energy Institute (NEI) dated September 7, 2005. While this TSTF has not yet been approved by the NRC, NPPD is proposing the addition of two notes to Table 3.3.1.1-1, applicable to the Neutron Flux-High (Flow Biased) function of the Average Power Range Monitors, consistent with this TSTF. The addition of these notes represents an acceptable means of ensuring regulatory requirements are met.
TS Amendment 178 described the Cooper Nuclear Station setpoint methodology and the approach to implementing that methodology. This methodology and approach is conservative with respect to the approach described in TSTF 493, Revision 3. The Safety Evaluation Report for TS Amendment 178, received on July 31, 1998, in Section III.G.2 accepted that methodology and approach for implementation. Therefore, the footnote changes proposed only represent clarification. This clarification makes explicit how NPPD will manage the setpoints to ensure compliance with 10 CFR 50.36.
Attachment 2 contains both the markup and clean copy of the affected TS page (Page 3.3-6). NPPD has determined that the recommended TS Bases language provided in the NRC letter to NEI dated September 7, 2005 and TSTF Traveler 493, Revision 3 generally exists in the current TS Bases Pages B 3.3-3 and 3.3-4. These pages explain how setpoints are selected for the instrument channel Functions specified in TS Table 3.3.1.1-1. These pages have been provided for information in Attachment 3.
The subject changes are considered editorial in nature, and do not impact the Technical or Regulatory evaluation, nor do they impact the No Significant Hazards determination provided in the November 19, 2007 submittal.
NLS2008046 Attachment 2 Technical Specification Pages - Markup and Clean Format Regarding License Amendment Request to Revise Technical Specifications for Measurement Uncertainty Recapture Power Uprate Cooper Nuclear Station, Docket No. 50-298, DPR-46 Technical Specification Page 3.3-6
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1. Intermediate Range Monitors
- a. Neutron 2 3 G SR 3.3.1.1.1 < 121/125 Flux - High SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 5 (a) 3 H SR 3.3.1.1.1 < 121/125 SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15
- b. Inop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13 5(a) 3 H SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13
- 2. Average Power Range Monitors
- a. Neutron 2 2 G SR 3.3.1.1.1 : 14.5% RTP Flux - High SR 3.3.1.1.3 (Startup) SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3..1.1.13 SR 3.3.1.1.15
- b. Neutron 2 F SR 3.3.1.1.1 Flux-High SR 3.3.1.1.2 ,.--..*O%
SR 3.3.1.1.4 RTpfbl" (Flow Biased)
SR 3.3.1.1.7 SR 3.3.1.1.8 ",,.. ,
S R 3.3.1.1.15 (continued) 0 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) [8.,66',' . 7.% - 0.00 A'] RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
f4A vuir4 0p1V,.10.
~KI4Z~
3.3-6
Table 3.3. 1.1-1 (page 1 of 3)
Footnote Insert Wording The following footnotes are to be inserted at the bottom of Technical Specification Page 3.3-6.
(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures to confirm the channel performance. The NTSP and the methodologies used to determine
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1. Intermediate Ranae Monitors
- a. Neutron 2 3 G SR 3.3.1.1.1 < 121/125 Flux - High SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 5 (a) 3 H SR 3.3.1.1.1 < 121/125 SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15
- b. Inop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13 5(a) 3 H SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13
- 2. Average Power Range Monitors
- a. Neutron 2 2 G SR 3.3.1.1.1
- b. Neutron 2 F SR 3.3.1.1.1 < 0.75 W Flux-High SR 3.3.1.1.2 + 62.0%
(Flow Biased) SR 3.3.1.1.4 RTP(b)
SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3 .3.1.1. 1 0 (c,d)
SR 3 .3.1.1. 1 2 (c,d)
SR 3.3.1.1.13 SR 3.3.1.1.15 (continued)
(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b) [0.75 W + 62.0% - 0.75 AW] RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
(c) If the as-found setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(d) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures to confirm the channel performance. The NTSP and the methodologies used to determine the as-found and as-left tolerances are specified in station procedures implementing the GE Setpoint Methodology per NEDC-31336P-A approved in TS Amendment 178 SER,Section III.G.2.
Cooper 3.3-6 Amendment No.
NLS2008046 Attachment 3 Technical Specification Bases Pages- For Information Regarding License Amendment Request to Revise Technical Specifications for Measurement Uncertainty Recapture Power Uprate Cooper Nuclear Station, Docket No. 50-298, DPR-46 Bases Pages B 3.3-3 B 3.3-4
RPS Instrumentation B 3.3.1.1 BASES (continued)
APPLICABLE The actions of the RPS are assumed in the safety analyses of SAFETY ANALYSES, References 1, 2, 3, and 4. The RPS is required to initiate LCO, and a reactor scram when monitored parameter values exceed the APPLICABILITY Allowable Values, specified by the setpoint methodology and listed in Table 3.3.1.1-1 to preserve the integrity of the fuel cladding, the reactor coolant pressure boundary (RCPB),
and the containment by minimizing the energy that must be absorbed following a LOCA.
RPS instrumentation satisfies Criterion 3 of 10 CFR 50.36 (c)(2)(ii) (Ref. 5). Functions not specifically credited in the accident analysis are retained for the overall redundancy and diversity of the RPS as required by the NRC approved licensing basis.
The OPERABILITY of the RPS is dependent on the OPERABILITY of the individual instrumentation channel Functions specified in Table 3.3.1.1-1. Each Function must have a required number of OPERABLE channels per RPS trip system, with their setpoints within the specified Allowable Value, where appropriate. The actual setpoint is calibrated consistent with applicable setpoint methodology assumptions.
Each channel must also respond within its assumed response time, where appropriate.
Allowable Values are specified, as appropriate, for RPS Functions specified in the Table. Nominal trip setpoints are specified in the setpoint calculations. The setpoint calculations are performed using methodology described in NEDC-31336P-A, "General Electric Instrument Setpoint Methodology," dated September 1996. The nominal setpoints are selected to ensure that the actual setpoints do not exceed the Allowable Value between successive CHANNEL CALIBRATIONS. Operation with a trip setpoint less conservative than the nominal trip setpoint, but within its Allowable Value, is acceptable. A channel is inoperable if its actual trip setpoint is not within its required Allowable Value.
Trip setpoints are those predetermined values of output at which an action should take place. The setpoints are compared to the actual process parameter (e.g., reactor vessel water level), and when the measured output value of the process parameter exceeds the setpoint, the associated device changes state. The analytic limits are derived from (continued)
Cooper B 3.3-3 Revision 0
RPS Instrumentation B 3.3.1.1 BASES APPLICABLE the limiting values of the process parameters obtained from SAFETY ANALYSES, the safety analysis or other appropriate documents.
LCO, and The Allowable Values are derived from the analytic limits, APPLICABILITY corrected for calibration, process, and some of the (continued) instrument errors. The trip setpoints are then determined accounting for the remaining instrument errors (e.g.,
drift). The trip setpoints derived in this manner provide adequate protection because instrumentation uncertainties, process effects, calibration tolerances, instrument drift, and severe environment errors (for channels that must function in harsh environments as defined by 10CFR 50.49) are accounted for.
The OPERABILITY of scram pilot valves andtassociated solenoids, backup scram valves, and SDV valves, described in the Background section, are not addressed by this LCO.
The individual Functions are required to be OPERABLE in the MODES or other Conditions specified in the table, which may require an RPS trip to mitigate the consequences of a design basis accident or transient. To ensure a reliable scram function, a combination of Functions are required in each MODE to provide primary and diverse initiationsignals.
The only MODES specified in Table 3.3.1.1-1 are MODES I and 2 and MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies. No RPS Function is required in MODES 3 and 4 since, all control rods are fully inserted and the Reactor Mode Switch Shutdown Position control rod withdrawal block (LCO 3.3.2.1) does not allow any control rod to be withdrawn. In MODE 5, control rods withdrawn from a core cell containing no fuel assemblies do not affect the reactivity of the core and, therefore., are not required to have the capability to scram. Provided all other control rods remain inserted, no RPS Function is required. In this condition, the required SDM:(LCO 3.1.1) and refuel position one-rod-out interlock (LCO 3.9.2) ensure that no event requiring RPS will occur.
The trip that results from the removal of a circuit card is a basic design feature of selected circuits. This feature is excluded from periodic testing in order to minimize component wear and damage.
(continued)
Cooper B 3.3-4 Revision 1
SATTACHMENT 3 LIST OF REGULATORY COMMITMENTS ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS@
Correspondence Number: NLS2008046 The following table identifies those actions committed to by Nebraska Public Power District (NPPD) in this document. Any other actions discussed in the submittal represent intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITMENT COMMITTED DATE COMMITMENT NUMBER OR OUTAGE None N/A N/A 4 4
+ 4
+ 4 1* 4 PROCEDURE 0.42 REVISION 22 PAGE 18 OF 25