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MONTHYEARML23361A1022023-12-21021 December 2023 Security Rule Exemption Request - ISFSI Docket No. Reference ML23321A1222023-11-17017 November 2023 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - License Amendment Request Regarding Neutron Flux Instrumentation ML23052A1502023-02-21021 February 2023 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request Regarding Neutron Flux Instrumentation ML22307A2532022-11-0303 November 2022 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Verbal Authorization of Relief Request ISIR-5-06 Regarding Alternative to N-729-6 for RPV Head Visual Examination ML22122A0902022-04-29029 April 2022 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-554, Revision 1 ML22250A6712022-02-16016 February 2022 Outline Submittal Notification Email DC-Cook 2022 ML21341A6252021-12-0707 December 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-577, Revision 1 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 ML21236A0262021-08-23023 August 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance of License Amendment Regarding Changes to Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements 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 ML21113A2812021-04-23023 April 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request Regarding Containment Water Level Instrumentation ML21089A0222021-03-24024 March 2021 DC Cook Power Operated Valves (POV) Preliminary Request for Information ML21082A0262021-03-22022 March 2021 Acceptance of 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 ML21008A4742021-01-0808 January 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance of License Amendment Request for One-Time Extension Containment Type a ILRT ML20366A1012020-12-31031 December 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance of License Amendment Request for One-Time Deferral of Steam Generator Inspection ML20316A0152020-11-0606 November 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval ML20318A0202020-10-16016 October 2020 NRR E-mail Capture - Regarding Public Comment on D.C. Cook, Unit 1 Request for Relief from Nozzle Inspections, Code Case N-729 ML20318A0192020-10-15015 October 2020 NRR E-mail Capture - (External_Sender) Supplemental Public Comment on D.C. Cook, Unit 1 Request for Relief from Nozzle Inspections, Code Case N-729 ML20289A7122020-10-15015 October 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 1 - Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination ML20290A4252020-10-15015 October 2020 Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination ML20318A0182020-10-0909 October 2020 NRR E-mail Capture - (External_Sender) Public Comment on D.C. Cook, Unit 1 Request for Relief from Nozzle Inspections, Code Case N-729 ML20289A1192020-10-0909 October 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of Relief Request for Alternative to N-729-4 for RPV Head Visual Examination ML20181A4122020-06-29029 June 2020 NRR E-mail Capture - Final RAI - D.C. Cook 1 - One-Time Extension, Containment Type a ILRT Frequency ML20149K6272020-05-28028 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment and Exemptions Regarding UFSAR 10 CFR 50.71(e)(4) Update Schedule (Epids: L-2020-LLA-0100, L-2020-LLE-0052, L-2020-LLE-0053) ML20149K4332020-05-26026 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-567, Revision 1 ML20141L8112020-05-20020 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of Relief Request Regarding Impracticality for Inservice Inspection for Certain Welds ML20141L6062020-05-20020 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-541, Revision 2 ML20136A5162020-05-15015 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-412, Revision 3 ML20133J9662020-05-11011 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 1 - Acceptance of License Amendment Regarding Changes to Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements ML20232B4562020-04-27027 April 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Fragility Questions ML20232B4432020-03-25025 March 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Plant Response Model Questions ML19345F9382019-12-0909 December 2019 D.C. Cook 50.54(f) SPRA Submittal - Completeness Review Done and Path Forward ML19333B8042019-11-29029 November 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-569 (L-2019-LLA-0248) ML19309F9212019-11-0505 November 2019 Request for Eportal Access for Audit Review of the DC Cook SPRA Supporting Documents ML19270E7372019-09-26026 September 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-421, Reactor Coolant Pump Flywheel Inspection Program ML19207A4642019-07-26026 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Delete Diesel Generator Load Test Resistor Banks 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 ML19175A3032019-06-24024 June 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS ML19092A4802019-04-0202 April 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-563 ML19092A4792019-04-0202 April 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Address Issues Identified in Westinghouse Document 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 ML19011A1382019-01-11011 January 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Environmental Technical Specifications (L-2018-LLA-0570) ML19011A3512019-01-11011 January 2019 NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment ML19009A5402019-01-0909 January 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS ML18313A0802018-11-0808 November 2018 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative ML18275A0532018-10-0101 October 2018 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS 2023-02-21
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23352A3502023-12-19019 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 ML14363A4912015-01-16016 January 2015 DC Cook Nuclear Plant, Units 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action to Adopt TSTF-490, Rev.0, Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Sp ML14246A4992014-08-26026 August 2014 NRR E-mail Capture - Donald C. Cook Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information (Scvb) Change to TS 5.5.14 by Adopting NEI 94-01, Revision 3-A ML14135A3202014-06-0606 June 2014 Request for Additional Information Concerning the Reactor Vessel Internals Afing Management Program Submittal 2023-12-19
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From: Philpott, Stephen To: David L Williams Cc: Valentin-Olmeda, Milton
Subject:
Second Request for Supporting Information (Fragility Questions) for the D.C. Cook SPRA Audit Review Date: Monday, April 27, 2020 12:57:00 PM Good afternoon Dave, The purpose of this email is to request the following information to support the audit review of the Donald C. Cook Nuclear Plant, Units 1 and 2 (CNP) 50.54(f) seismic probabilistic risk assessment (SPRA) submittal dated November 4, 2019 (ADAMS Accession No. ML19310D805). The NRC staff is using a technical checklist (see ADAMS Accession No. ML18173A017) to guide this review. The following audit questions will support this effort. Please provide your responses to the following questions via your Scientech (OneCWCloud) e-Portal SPRA audit site.
Note that we have continued the question numbering from the first set of clarification questions (Plant-Response Model Questions) sent by my e-mail on March 25, 2020, to avoid any confusion in referencing specific questions and responses.
Donald C. Cook Nuclear Plant, Units 1 and 2 (CNP)
Fragility Clarification Questions Question 6 - Topic # 6 - Use of Seismic Response Scaling (SPID Section 6.3.2)
In Section 4.4.2.2 of the submittal, it is not clear to the NRC staff whether the scaling or screening capacity approach was used to evaluate fragilities of the Nuclear Steam Supply System (NSSS) components. If the scaling approach was used, please clarify, in accordance with SPID Section 6.3.2, whether the scaling of responses were based on the following: (1) previously developed in-structure response spectra (ISRS); (2) shape of the previous uniform hazard spectrum/reviewlevel earthquake (UHS/RLE); (3) shape of new UHS/RLE; and (4) structural natural frequencies, mode shapes, and participation factors.
Please also clarify how non-linear effects were considered if the spectral shape of the new UHS/RLE and the design basis ground motion are non-similar. If the scaling approach was not used, please describe the methodology used to evaluate the fragility of NSSS components.
Question 7 - Topics # 4 - Adequacy of the Structural Model (SPID Section 6.3.1); # 7 -
Use of New Response Analysis for Building Response, ISRS, and Fragilities; # 9 -
Use of the CDFM/Hybrid Methodology for Fragility Analysis (SPID Section 6.4.1); and
- 12 - Selection of Dominant Risk Contributors that Require Fragility Analysis Using the Separation of Variables Methodology (SPID Section 6.4.1)
Sections 3.1.1, 4.3.2, and 4.4 of the submittal states that an earthquake equivalent to 0.8 times the uniform hazard response spectra (UHRS) at 1E-5 mean annual probability of exceedance, designated as the review level earthquake (RLE), was used to evaluate building responses and fragility estimation. The basis for this ground motion for the SPRA is not discussed in the submittal. Please clarify the rationale for the RLE hazard level used in the SPRA.
Question 8 - Topic # 4 - Adequacy of the Structural Model (SPID Section 6.3.1)
The structural response document (Reference #63, CNP document 15C4313-3RPT-003, Summary of Building Response Analysis for Cook Nuclear Plant (CNP) Unit 1 and Unit 2 SPRA) describes the lumped mass stick model (LMSM) of the containment building (CB),
which includes three unique stick models of the containment shell and dome, crane wall, and primary shield wall. In addition, the East Main Steam Stop Enclosure (EMSSE) was added to the CB model. The LMSM was used to develop in-structure response spectra (ISRS) for the fragility assessment of the components and systems housed in EMSEE. To address Checklist Topic #4, the NRC staff is requesting clarifications for the following:
a) The structural response document (15C4313-3RPT-003) stated that the LMSM of the EMSEE reflect the dynamic behavior of the 3D shell model of the structure. Please clarify how the response of EMSEE from the 3D model was verified in the composite CB LMSM.
b) During the staff review of the structural response document (15C4313-3RPT-003), Section 3.0 and Attachment B, the staff noted that although the individual LMSM models do not satisfy all the Criteria 1 through 7 of SPID section 6.3.1 (e.g., models do not include vertical floor response), CNP determined that the overall model of the containment building structure meets the criteria of the SPID. Please provide the basis for the determination that this model meets the SPID criteria.
Question 9 - Topics # 4 - Adequacy of the Structural Model (SPID Section 6.3.1)
The disposition of facts and observations (F&Os) following the close-out peer review is documented in Table A.8-1: Summary of CNP Open F&Os Impact to SPRA Results. There are some F&Os that remain Open and some are Partially Resolved. In all cases CNP concluded that the SPRA results are not expected to be impacted. Although CNP provided paths to closing the F&Os, it is not clear to the NRC staff when CNP plans to close out the F&Os. In some cases, the CNP dispositions are either not sufficiently documented or require further analyses. Please clarify the dispositions for the following two F&Os:
a) In response to F&O 28-2 (Partially Resolved), which required demonstration that by assuming single-point attachment for dynamic coupling, the structural response of the Containment Building (CB) is realistic, the disposition stated that the CB modeling simplifications have no impact on the structural response and detailed studies are not required. However, the disposition did not offer a basis for this conclusion. Please provide a more complete justification for the CNP resolution of F&O 28-2, or identify where this justification is documented in the submittal or supporting documents.
b) In response to F&O 28-11 (Open) regarding the variability of structural properties, the disposition stated the impact of structural variability on the fragility for the risk-significant components will be reviewed. Please provide the basis for the statement that SPRA results are not expected to be impacted without the results from the proposed sensitivity analysis.
Please let me know when the responses are made available so that we can proceed with
the audit review. If a conference call would be helpful to clarify or further explain any of these audit question, please let me know and I will be happy to arrange a call.
Thank you, Steve Steve Philpott Project Manager U.S. Nuclear Regulatory Commission (NRR/DORL/LPMB) phone: 301-415-2365 e-mail: Stephen.Philpott@nrc.gov