Letter Sequence RAI |
---|
|
|
MONTHYEARML12115A0042012-04-23023 April 2012 Email to Convey RAI Thermal Conductivity Degradation Project stage: RAI ML12122A0052012-04-30030 April 2012 Email Conveys Revised RAI Re. Thermal Conductivity Degradation Effects on 10 CFR 50.46 Compliance Project stage: RAI ML12129A5012012-05-14014 May 2012 RAI the Effect of Thermal Conductivity Degradation on Peak Cladding Temperature Analysis Project stage: RAI 2012-04-30
[Table View] |
Similar Documents at Cook |
---|
Category:Letter
MONTHYEARIR 05000315/20240032024-10-31031 October 2024 Integrated Inspection Report 05000315/2024003 05000316/2024003 07200072/2024001 and Exercise of Enforcement Discretion AEP-NRC-2024-77, U2C28 Steam Generator Tube Inspection Report2024-10-21021 October 2024 U2C28 Steam Generator Tube Inspection Report AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 ML24159A2522024-05-30030 May 2024 10 CFR 50.71(e) Update and Related Site Change Reports AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report 05000316/LER-2024-001, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24256A1472024-05-0606 May 2024 DC Cook 2024 NRC Examination Submittal Letter: Submittal ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24178A0432024-06-26026 June 2024 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - License Amendment Request Regarding Neutron Flux Instrumentation ML24156A0072024-05-30030 May 2024 NRR E-mail Capture - Final RAI - D.C. Cook Nuclear Plant, Unit Nos. 1 and 2 - License Amendment Request Regarding Reserve Feed Enclosure ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 ML22264A1112022-09-21021 September 2022 Notification of Post-Approval Site Inspection for License Renewal - Phase IV; IR 05000315/2023010; 05000316/2023010 and RFI ML22230A4362022-08-19019 August 2022 Licensed Operator Positive Fitness-For-Duty Test ML22049B4532022-02-22022 February 2022 Notification of NRC Baseline Inspection and Request for Information Report 05000315/2022002 ML21307A3352021-11-0303 November 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Final RAI - License Amendment Request Regarding Containment Water Level Instrumentation ML21215A1242021-08-0303 August 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2021013; 05000316/2021013 ML21140A3052021-05-20020 May 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request ISIR-4-11, Impractical Examinations for the Fourth 10-Year ISI Interval ML21049A2682021-02-16016 February 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Final RAI - License Amendment Request for One-Time Extension Containment Type a ILRT ML21026A3472021-01-26026 January 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval IR 05000315/20200112020-09-17017 September 2020 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2020011; 05000316/2020011 ML20181A4122020-06-29029 June 2020 NRR E-mail Capture - Final RAI - D.C. Cook 1 - One-Time Extension, Containment Type a ILRT Frequency ML20232B4562020-04-27027 April 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Fragility Questions IR 05000315/20200202020-04-10010 April 2020 Units 1 and 2 - Information Request for NRC Triennial Evaluation of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000315/2020020 and 05000316/2020020 ML20232B4432020-03-25025 March 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Plant Response Model Questions ML19267A1362019-09-24024 September 2019 NRC Information Request (September 23, 2019) - IP 71111.08 - DC Cook U2 - Documents Selected for Onsite Review (DRS-M.Holmberg) ML19204A0962019-07-23023 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Request for Additional Information Related to Unit 2 Leak Before Break Analysis and Deletion of Containment Humidity Monitors for Unit Nos. 1 and 2 ML19211C3032019-07-0303 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 & 2 - Request for Additional Information Related to LAR to Address NSAL-15-1 ML19084A0002019-03-20020 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19072A1432019-03-12012 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19011A3512019-01-11011 January 2019 NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment ML18313A0802018-11-0808 November 2018 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative ML18263A1542018-09-14014 September 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18204A3722018-07-19019 July 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18143B6292018-05-29029 May 2018 Dtf. RAI ML18142B5312018-05-29029 May 2018 Request for Additional Information Concerning 2017 Decommissioning Funding Status Report ML18060A0212018-02-28028 February 2018 Enclosurequest for Additional Information (Request for Additional Information Regarding Indiana Michigan Power Company'S Decommissioning Funding Update for Donald C Cook Nuclear Plant Units 1 and 2 ISFSI) ML18043A0092018-02-0909 February 2018 NRR E-mail Capture - DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program ML17304A0102017-11-0101 November 2017 Unit Nos.1 and 2 - Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9444 and MF9445; EPID L-2016-LRC-0001) ML17249A7492017-08-28028 August 2017 E-Mail Sent August 28, 2017, Request for Information for Donald C. Cook Nuclear Power Plant, Unit 1 (Part B); Inspection Report 05000315/2017004 (Msh) ML17108A7772017-04-18018 April 2017 17 Donald C. Cook Nuclear Power Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information (05000315/2017003; 05000316/2017003) (Msh) ML17068A0652017-03-0808 March 2017 Ltr 03/08/17 Donald C. Cook Nuclear Power Plant, Unit 2 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000316/2017009 (Bxj) ML17027A0192017-01-26026 January 2017 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI Regarding LAR to Revise TS 5.5.14 (MF8483 and MF8484) ML16211A0152016-08-0101 August 2016 Follow-Up Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control IR 05000315/20160042016-07-11011 July 2016 Donald C. Cook Nuclear Power Plant, Unit 2 - Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16193A6542016-07-11011 July 2016 Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16154A1822016-06-0909 June 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control (CAC Nos. MF7114 and MF7115) ML16127A0792016-05-11011 May 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control ML16025A0552016-01-22022 January 2016 Ltr. 01/22/16 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Pilot Design Bases Inspection on the Implementation of the Environmental Qualification Program Inspection Report 05000315/2016008; 05000316 ML15267A6832015-10-0505 October 2015 Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15231A5542015-08-18018 August 2015 Ltr. 08/18/15 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Triennial Pilot Baseline Component Design Bases Inspection (Inspection Report 05000315/2015008; 05000316/2015008) (Axd) ML15225A5772015-08-13013 August 2015 Information Request to Support Upcoming Problem Identification and Resolution Inspection at D.C. Cook, Units 1 and 2 ML15163A1672015-06-15015 June 2015 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15149A3832015-05-28028 May 2015 Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15119A3392015-05-0505 May 2015 Follow-up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal ML15055A5702015-02-24024 February 2015 Cyber Security RFI Temporary Instruction 2201/004 ML15022A1532015-01-21021 January 2015 Dccook ISI Request for Information 2024-06-26
[Table view] |
Text
May 14, 2012
Mr. Lawrence Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106
SUBJECT: DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION ON THE ISSUE OF PEAK CLADDING TEMPERATURE AFFECTED BY THERMAL CONDUCTIVITY DEGRADATION (TAC NOS. ME8322 AND ME8323)
Dear Mr. Weber:
By letter dated March 19, 2012 (Accession No. ML 12088A104), Indiana Michigan Power Company submitted its response to a Nuclear Regulatory Commission (NRC) staffs information request pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.54(f) related to the estimated effect on peak cladding temperature resulting from thermal conductivity degradation in the Westinghouse-furnished realistic emergency core cooling system (ECCS) evaluation. The licensee also stated that the March 19, 2012, letter served as a 30-day report of a significant ECCS evaluation model change or error in accordance with requirements of 10 CFR 50.46(a)(3). In the course of its 10 CFR 50.46 report review, the NRC staff determined that additional information is necessary to complete its review. A draft of a request for additional information (RAI, Accession No. ML 12086A002) was provided to facilitate discussion with the licensee; subsequently, the NRC staff conducted an audit at the Westinghouse Electric Company facilities in Cranberry Township, Pennsylvania, to further clarify the request for additional information and the contents required to be responsive to the request. The draft RAI has been revised and sent to the licensee by an e-mail ofApriI23.2012(AccessionNo.ML12115A004). On April 30, 2012, the NRC staff held a conference call with your staff and agreed to revise the RAI further, eliminating Question 4, and revising Question 10. The revised RAI was e-mailed to your staff on April 30, 2012 (Accession No. ML 12122A005).
L. The purpose of this letter is to formally convey the final RAI to you (see Enclosure). The NRC staff requests your response within 30 days of the date of this letter. Feel free to contact me if you need any further clarification of the questions in the enclosed RAI.
Sincerely,P er S. Tam, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
RAI cc w/encl: Distribution via ListServ REQUEST FOR ADDITIONAL INFORMATION D. C. COOK NUCLEAR PLANT THE ISSUE OF PEAK CLADDING TEMPERATURE AFFECTED BY THERMAL CONDUCTIVITY DEGRADATION Provide a table of data that includes the following ASTRUM inputs for AOR and integrated analyses: (1) AOR Run #, (2) TCD Run #, (3) PCT, (4) Time of PCT, (5) Fq, (6) FdH, (7) Cycle Burnup, (8) RCS Tavg, (9) Accumulator Temperature, (10) Safety Temperature, (11) Safety Injection Please highlight the limiting cases in the ASTRUM run matrices and explain how these cases were chosen. Provide details and explain the approach used to estimate (1) the effects of TCD and (2) the compensating model changes. Justify the selection of the number of WCOBRAITRAC cases that were re-executed, as opposed to a larger number of cases. Justify the containment pressure changes made to obtain margin on Unit 1. Provide reference to excerpts from the applicable methodologies to clarify the response. Your submittal referenced a March 7, 2012, letter sent by Westinghouse Electric Company (WEC) to the Nuclear Regulatory Commission (NRC). The final paragraph on Page 2 of 9 refers to small differences in fuel characteristics that were claimed to be compared. The paragraph also discusses confirmatory evaluations concluding that other operating characteristics were acceptable. Provide the results of this comparison for D. C. Cook, including the relevant conclusions and the technical basis supporting those conclusions. For any conclusion regarding differences in void volume are offset by other conservatisms, list those conservatisms and provide a quantitative estimate for each conservatism, as well as a brief description of the rigor associated with that estimate. Please provide the values for the coefficients used in the PAD 4.0 + TCD UOz thermal conductivity equation. Please explain any error corrections, code improvements, and miscellaneous code cleanup between the WCOBRAITRAC and HOTSPOT code versions used in the TCD evaluations and those used in the plant's AOR. What is the thermal conductivity model impact of code version changes in HOTSPOT? Explain the differences between the HOTSPOT and PAD thermal conductivity models and the impact of those differences. Provide graphs or other quantified descriptions that aid in explanation. Enclosure
-Please provide additional detail concerning the steady-state ASTRUM/CQD initialization process. In particular, please explain what fuel characteristics are adjusted within the applicable models to obtain convergence among HOTSPOT, WCOBRAITRAC, and PAD 4.0 + TCD. Please explain how the changed design values will be verified during operation of the plant, i.e., Technical Specification limits, Surveillances, etc. Also, explain what compensatory actions will be taken if a value is found to be outside of the limits assumed in the analysis. Fully explain all peaking factor adjustments and provide the rationale for each adjustment. At the bottom of Page 1 of Enclosure 2 to AEP-NRC-2012-13 it is stated that "I&M and WEC utilized processes which ensure that the LBLOCA [large-break loss-of-coolant accident] analysis input values conservatively bound the as-operated plant values for those parameters." Please explain these processes. Please explain the process for determining the establishment of a trend in the context of the following statement: "For the margin PCT calculation, WCOBRAITRAC cases were executed until an estimated trend could be established." Based on the NRC's review of the March 19,2012, submittal it appears that the licensee has revised inputs to a method of evaluation as described in the Final Safety Analysis Report (as updated) used in establishing the design bases or in the safety analyses. Revision 1 to NEI 96-07, "Guidelines for 10 CFR 50.59 Implementation," Section 3.8, "Input Parameters," (Accession No. ML003771157) provides clarifying information concerning whether an input parameter is considered to be an element of a methodology for the purposes of addressing the applicable requirements found at Title 10 of the Code of Federal Regulations (10 CFR) 50.59, "Changes, Tests, and Experiments." Address whether the methodology permits the licensee to establish how to select the value of an input parameter to yield adequately conservative results and whether the revised value is more conservative than that required by the selection method. Address whether any of the changes (i.e., to the U02 thermal conductivity equation) constitutes a change in the calculational framework used for evaluating behavior or response of a system, structure or component. Explain whether and how 10 CFR 50.59(c)(4) might apply to such a change.