Letter Sequence RAI |
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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
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[Table view] Category:Request for Additional Information (RAI)
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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. 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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. 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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
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Text
Accession No. ML12122A005 From: Tam, Peter Sent: Monday, April 30, 2012 3:03 PM To: 'hletheridge@aep.com'; mkscarpello@aep.com Cc: Parks, Benjamin; Paige, Jason
Subject:
D.C. Cook - Revised Request for Additional Information Regarding Thermal Conductivity Degradation (TAC ME9322 and ME9323)
Helen:
By letter dated March 19, 2012 (Accession No. ML12041A384), Indiana Michigan Power Company submitted a response to an 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 evaluation. The licensee also stated that this response served as a 30-day report of a significant emergency core cooling system 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 copy of this request for additional information 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 content required to be responsive to the request (Accession No. ML12094A069). The draft request for additional information has been revised and sent to you by my e-mail of 4/23/12 (Accession No. ML12115A004). Today (4/30/12) we held a conference call with you and your staff and agreed to revise the RAI further, eliminating Question 4, and revising Question 10 as shown in red.. The questions after Question 4 are re-numbered to reflect elimination of Question 4.
Please respond to the revised RAI below within 30 days of the date of this e-mail.
- 1. 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 Injection Temperature, (11) Safety Injection Time.
- 2. 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 WCOBRA/TRAC cases that were re-executed, as opposed to a larger number of cases.
- 3. Justify the containment pressure changes made to obtain margin on Unit 1.
Provide reference to excerpts from the applicable methodologies to clarify the response.
- 4. Your submittal referenced a March 7, 2012, letter sent by Westinghouse Electric Company to the NRC.
- a. 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 that differences in void volume are offset by other conservatisms, list those conservatisms and provide a quantitative estimate of each conservatism, as well as a brief description of the rigor associated with that estimate.
- b. Please provide the values for the coefficients A1 and A2 used in the PAD 4.0 +
TCD UO2 thermal conductivity equation.
- c. Please explain any error corrections, code improvements, and miscellaneous code cleanup between the WCOBRA/TRAC and HOTSPOT code versions used in the TCD evaluations and those used in the plants AOR.
- d. What is the thermal conductivity model impact of code version changes in HOTSPOT?
- e. 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.
- f. 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, WCOBRA-TRAC, and PAD4.0TCD.
- 5. Please explain how the changed design values will be verified during operation of the plant, i.e. TS 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.
- 6. Fully explain all peaking factor adjustments and provide the rationale for each adjustment.
- 7. 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 analysis input values conservatively bound the as-operated plant values for those parameters.
Please explain these processes.
- 8. Please explain the process for determining the establishment of a trend in the context of the following statement: For the margin PCT calculation, WCOBRA/TRAC cases were executed until an estimated trend could be established.
- 9. Based on the NRCs review of the March 19. 2012, submittal it appears that the licensee has revised inputs to a method of evaluation as described in the FSAR (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, 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 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 UO2 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.
Peter S. Tam, Senior Project Manager (for D.C. Cook and Monticello)
Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Tel. 301-415-1451