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MONTHYEARML1130814412011-11-0303 November 2011 License Amendment Request - Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Request ML1134003382011-12-0606 December 2011 Supplemental Information Required for Peach Bottom November 3, 2011, Submittal (TAC Nos. ME7538 & ME7539) Project stage: Other ML1132602952011-12-14014 December 2011 Supplemental Information Needed for Acceptance of Requested Licensing Action Use of Neutron Absorbing Inserts in Units 2 and 3 Spent Fuel Pool Storage Racks Project stage: Acceptance Review ML1135702082011-12-22022 December 2011 Response to License Amendment Request - Use of Neutron Absorbing Inserts in Units 2 & 3 Spent Fuel Pool Storage Racks Project stage: Request ML12096A0522012-04-0404 April 2012 Response to Request for Additional Information - License Amendment Request for Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Response to RAI ML1208702032012-04-18018 April 2012 Request for Additional Information Regarding License Amendment Request for Use of Neutron Absorbing Inserts in Units 2 and 3 Spent Fuel Pool Storage Racks Project stage: RAI ML1212202712012-05-16016 May 2012 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML1212202552012-05-16016 May 2012 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML12139A4042012-05-17017 May 2012 Response to Request for Additional Information - License Amendment Request for Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Response to RAI ML1212505692012-05-22022 May 2012 Request for Additional Information Regarding License Amendment Request for Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: RAI ML12188A0942012-06-21021 June 2012 Response to Request for Additional Information - License Amendment Request for Use of Neutron Absorbing Inserts in Units 2 and 3 Spent Fuel Pool Storage Racks Project stage: Response to RAI ML12194A6082012-07-12012 July 2012 Draft Request for Additional Information Project stage: Draft RAI ML12192A3532012-07-19019 July 2012 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Units 2 and 3 Project stage: Withholding Request Acceptance ML12228A4742012-08-15015 August 2012 Response to Request for Additional Information - License Amendment Request for Use of Neutron Absorbing Inserts in Units 2 and 3 Spent Fuel Pool Storage Racks Project stage: Response to RAI ML12319A2302012-11-13013 November 2012 Response to Request for Additional Information - License Amendment Request for Use of Neutron Absorbing Inserts in Units 2 and 3 Spent Fuel Pool Storage Racks Project stage: Response to RAI ML13063A3372013-03-0404 March 2013 Draft Request for Additional Information Project stage: Draft RAI ML13112A8572013-05-0202 May 2013 Request for Withholding Information from Public Disclosure for Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 Project stage: Withholding Request Acceptance ML13121A2882013-05-13013 May 2013 Transmittal of Draft Safety Evaluation for Proposed Amendment Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Draft Approval ML13114A9292013-05-21021 May 2013 Issuance of Amendments Use of Neutron Absorbing Inserts in Spent Fuel Pool Storage Racks Project stage: Approval 2012-05-17
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Category:Letter
MONTHYEARML24022A2262024-01-22022 January 2024 (PBAPS) Unit 3 - Submittal of the Inservice Inspection (ISI) Owner'S Activity Report (OAR) for the 24th Refueling Outage for Unit 3 ML23346A2412024-01-17017 January 2024 Staff Assessment of Updated Seismic Hazards Following the NRC Process for the Ongoing Assessment of Natural Hazards Information (EPID L-2019-PMP-0061) - Letter IR 05000277/20234022024-01-11011 January 2024 Security Baseline Inspection Report 05000277/2023402 and 05000278/2023402 and Independent Spent Fuel Storage Installation Security Inspection 07200029/2023401 ML23354A1922024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23355A0622023-12-18018 December 2023 Independent Spent Fuel Storage Installation (Isfsi), Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) IR 05000277/20230032023-10-30030 October 2023 Integrated Inspection Report 05000277/2023003 and 05000278/2023003 and Exercise of Enforcement Discretion ML23286A0012023-10-13013 October 2023 Reply to a Notice of Violation (NOV) - NOV 05000277, 05000278/2023010-01 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23271A1342023-10-11011 October 2023 Dtf Analysis Letter IR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23265A1502023-09-22022 September 2023 License Amendment Request Revise a License Condition and Certain Technical Specifications to Remove Restrictions in Support of Decommissioning Activities ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L IR 05000277/20230102023-09-15015 September 2023 Biennial Problem Identification and Resolution Inspection Report 05000277/2023010 and 05000278/2023010 and Notice of Violation ML23251A2022023-09-11011 September 2023 Cover Letter W/Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement IR 05000277/20230052023-08-31031 August 2023 Updated Inspection Plan for Peach Bottom Atomic Power Station, Units 2 and 3 (Report 05000277/2023005 and 05000278/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 IR 05000277/20230112023-08-15015 August 2023 Comprehensive Engineering Team Inspection Report 05000277/2023011 and 05000278/2023011 ML23226A1112023-08-14014 August 2023 10 CFR 50.46 Annual Report IR 05000277/20230022023-08-0808 August 2023 Integrated Inspection Report 05000277/2023002 and 05000278/2023002 RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000277/20230402023-07-17017 July 2023 95001 Inspection Supplemental Report 05000277/2023040 and Follow-Up Assessment Letter ML23188A0532023-07-0707 July 2023 Registration of Use of Independent Spent Fuel Storage Installation (ISFSI) Casks ML23186A1272023-07-0606 July 2023 Response to Disputed Non-Cited Violation Documented in Peach Bottom Atomic Power Station, Units 2 and 3, Inspection Report 05000277/2022004 and 05000278/2022004 ML23178A0352023-06-27027 June 2023 Senior Reactor and Reactor Operator Initial License Examinations RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ML23150A2052023-05-30030 May 2023 Independent Spent Fuel Storage Installation (Isfsi), Annual Radiological Environmental Operating Report 80 January 1, 2022 Through December 31, 2022 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23142A1602023-05-23023 May 2023 Summary of April 11, 2023, Public Observation Meeting with Constellation Energy Generation, LLC Re Proposed Exemption Request from Work Hour Requirements ML23132A1582023-05-18018 May 2023 Correction to Technical Specification 3.4.7 (Page 3.4-16) Issued in Amendment No. 337 ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) IR 05000277/20230012023-05-0808 May 2023 Integrated Inspection Report 05000277/2023001 and 05000278/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI 2024-01-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARIR 05000277/20244012023-10-0505 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000277/2024401 and 05000278/2024401 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML22118A3312022-04-28028 April 2022 NRR E-mail Capture - Peach Bottom - Formal RAI for Proposed Alternative I5R-14, Revision 1 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22021A5692022-01-21021 January 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000277/2022403 and 05000278/2022403 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21035A2222021-02-0404 February 2021 Notification of Conduct of a Fire Protection Team Inspection ML21091A1782021-02-0202 February 2021 Ti 2515/194 Inspection Documentation Request ML21012A1302021-01-12012 January 2021 Request for Additional Information - TSTF-505 ML20357A0972020-12-21021 December 2020 Request for Additional Information - TSTF-505 ML20296A3342020-10-21021 October 2020 ISI Remote Inspection - Supplemental Request for Information ML20239A7982020-08-25025 August 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2 ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20135H1972020-05-14014 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval ML20070R2282020-03-10010 March 2020 Request for Additional Information - RR ML19303D1662019-10-31031 October 2019 Requests for Additional Information for the Environmental Review of the Peach Bottom Subsequent License Renewal Application - Set 2 (EPID No. L-2018-RNW-0013)- RAIs ML19232A1752019-08-20020 August 2019 Request for Additional Information - TSTF-500 Implementation LAR ML19140A2832019-05-15015 May 2019 Email - Peach Bottom Atomic Power Station, Units 2 and 3 Second Round RAI Request - Set 1 ML19140A2822019-05-15015 May 2019 027 Pb FU RAI Subsequent to Clarification Call - Cu Greater than 15 Zn Holston (Jg) ML19253D2932019-05-0707 May 2019 002 Attachment 4D Confirmation Water Chemistry Chereskin Revised (002) ML19249C7252019-05-0303 May 2019 SLRA Requests for Additional Information - Set 2 May 3, 2019 ML19108A4282019-04-10010 April 2019 RAIs SLRA Set 1_ERO(Rev 1) ML19079A0232019-03-19019 March 2019 Licensed Operator Positive Fitness-For-Duty Test ML19058A2902019-02-27027 February 2019 Request for Additional Information - High Pressure Service Water One Time TS Change ML19037A4832019-02-0606 February 2019 NRR E-mail Capture - Clarification Questions Associated with Staff Assessment of Peach Bottom Seismic Probabilistic Risk Assessment Report Dated August 28, 2018 ML19028A0062019-01-25025 January 2019 Secondary Containment LAR Requests for Additional Information ML19017A0472019-01-16016 January 2019 Request for Additional Information - High Pressure Service Water One Time TS Change ML18348B0292018-12-13013 December 2018 Subsequent License Renewal Severe Accident Mitigation Alternatives Requests for Additional Information ML19010A3832018-12-0707 December 2018 Additional Documents Needed for Peach Bottom SLR Environmental Review ML18324A6742018-11-15015 November 2018 Request for Additional Information (FINAL)- LAR to Allow 2SRV/SVs OOS at High Pressure ML18312A4072018-11-0808 November 2018 Request for Additional Information (Public) - LAR to Allow 2SRV/SVs OOS at High Pressure ML18276A0202018-10-0202 October 2018 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan for Limerick and Peach Bottom ML18240A1742018-08-28028 August 2018 Request for Additional Information (Final) - Adopt TSTF-500 Battery TS Changes LAR ML18239A1322018-08-27027 August 2018 Request for Additional Information Final - Relief Request I5R-04 ML18228A6762018-08-14014 August 2018 Request for Additional Information - Adopt TSTF-500 Battery TS Changes LAR ML18226A2012018-08-14014 August 2018 Request for Additional Information - Relief Request I5R-05 ML18214A2812018-08-0202 August 2018 Request for Additional Information Draft - Relief Request I5R-02 ML18200A2742018-07-17017 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment ML18192A1192018-07-10010 July 2018 Request for Additional Information 2nd Round (Final) - Adopt 50.69 License Amendment ML18178A4772018-06-27027 June 2018 Request for Additional Information 2nd Round - Adopt 50.69 License Amendment ML18096B5062018-04-0606 April 2018 Request for Additional Information Exelon Generation Company, LLC Requested Amendment to Adopt 10 CFR 50.69 for Risk-informed Categorization and Treatment of Structures, Systems and Components ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17317B5502017-11-0909 November 2017 Licensed Operator Positive Fitness-For-Duty Test ML17240A0062017-08-24024 August 2017 Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML17222A0962017-08-10010 August 2017 Request for Additional Information - Amendment Request Regarding Safety Relief Valve and Safety Valce Operability for Cycle 22 2023-09-21
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 May 22, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR USE OF NEUTRON ABSORBING INSERTS IN SPENT FUEL POOL STORAGE RACKS (TAC NOS. ME7538 AND ME7539) Dear Mr. Pacilio: By letter to the Nuclear Regulatory Commission (NRC) dated November 3, 2011, as supplemented on December 22, 2011, and April 4, 2012, Exelon Generation Company, LLC (Exelon), submitted a license amendment request for Peach Bottom Atomic Power Station, Units 2 and 3. The proposed amendment would modify the Technical Specifications to include the use of neutron absorbing spent fuel pool rack inserts for the purpose of criticality control in the spent fuel pools. The NRC staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The RAI questions were provided in draft form to Mr. Thomas Loomis of your staff via e-mail on April 10, 2012. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. A conference call between the NRC staff and the Exelon staff was held on April 23, 2012, to discuss the questions. During this call, it was agreed that several of the questions needed to be revised for clarification of the information to be submitted. The revised set of draft questions were sent to Mr. Loomis via e-mail on May4,2012. Foliowingthecall,Mr. Loomis stated that Exelon would provide a response to the RAI by June 29,2012. Please note that if you do not respond to this letter by the agreed-upon date or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108.
M. Pacilio -If you have any questions, please contact me at (301) 415-1420. Sincerely, Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278 Request for Additional cc w/encl: Distribution via ListServ REQUEST FOR ADDITIONAL REGARDING PROPOSED LICENSE USE OF NEUTRON ABSORBING SPENT FUEL POOL RACK PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND DOCKET NOS. 50-277 AND By letter to the Nuclear Regulatory Commission (NRC) dated November 3, 2011, as supplemented on December 22, 2011, and April 4, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 113081441, ML 113570208, and ML 12096A052, respectively), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment would modify the Technical Specifications (TSs) to include the use of neutron absorbing spent fuel pool (SFP) rack inserts for the purpose of criticality control in the SFPs at PBAPS, Units 2 and 3. The NRC staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific information requested is addressed below. Criticality Analysis RAI-19: Section 4.2, "Fuel Model Description" in Attachments 7 and 8 to the letter dated November 3, 2011, indicates that the lattice design and corresponding operating characteristics that produce the worst (Le., highest) rack efficiency are selected as the design basis lattice. However, this does not appear to be the case as provided in Table 7 of Attachments 4 and 6. Explain how "rack efficiency" is used in your methodology to show that the regulatory requirements are met. RAI-20: The results in Table 7 of Attachments 4 and 6 to the letter dated November 3, 2011, indicate that the highest in-core k-infinity case does not necessarily produce the limiting in-rack k-effective. Explain why in-core k-infinity remains the appropriate parameter to control in the TSs. RAI-21: Regarding criticality code validation, the NRC's Interim Staff Guidance (ISG) DSS-ISG-2010-1, "Staff Guidance Regarding the Nuclear Criticality Analysis for Spent Fuel Pools" (ADAMS Accession No. ML 110620086), states: "An acceptable means of including isotopes that are not explicitly represented in the critical experiments used in the validation would be to increase the bias and bias uncertainty by an amount proportional to the reactivity worth of the isotopes not explicitly validated." Justify the impact of actinides and fission products on the code validation bias. RAI-22: Evaluate and apply any trends in the k-effective bias per ISG DSS-ISG-2010-1. Enclosure
-2 Section 3.2.3, "Gap Size and Panel Length Analyses," of Electronic Power Research Institute (EPRI) Topical Report (TR) 1073351 reported a gap size of 3.4 inches for the 1133 south panel in 1996. Attachment 1 to the letter dated November 3, 2011, states that, "[a]s an additional conservatism, and to bound future gap size growth, the gap size modeled in the analysis is 3.0 inches." Justify the assumed gap size. Discuss whether the "Boraflex Panel Shrinkage and Edge Dissolution" bias accounts for reductions in both the length and the width of the Boraflex panel. Considering the rack, the pOison panel and the wrapper plate design at PBAPS, what is the limiting structural configuration of the Boraflex panels under the design basis seismic event from a criticality standpoint? Show that this condition is bounded by the criticality analysis. BADGER and RACKLIFE Quantify and justify the PBAPS-specific combined uncertainty in BADGER at a 95 percent probability, 95 percent confidence level. Quantify and justify the PBAPS-specific combined uncertainty in RACKLIFE at a 95 percent probability, 95 percent confidence level. Section 3.2.2 of Attachment 1 to the letter dated November 3, 2011, states that a "detailed calculation of the bias and bias uncertainty of the BADGER testing measurements and RACKLIFE analysis projections has been performed." Provide this calculation, including the input prediction and measurement data used in the calculation. Describe the normality of the data and any trending analysis performed. Provide the RACKLIFE predicted panel average loss and dose values, and corresponding coordinates (i.e., location) for all panels in the PBAPS SFPs. Provide the two-dimensional areal density measurements from all BADGER scans to evaluate the gradient within a given panel. Provide the corresponding count rates that were measured in these panels for each detector. Provide a detailed description of the calibration process used at PBAPS to support the BADGER campaigns. Provide the calibration curves used to support the PBAPS BADGER campaigns. Describe how BADGER accounts for the effect of degradation levels on the calibration curves. Provide a description, including a drawing, of the calibration cell used at PBAPS. Discuss the applicability of the calibration cell to the PBAPS BADGER campaigns from geometry and material composition considerations. Identify and evaluate their effects on uncertainties in determining the areal densities and the gap sizes. 1 EPRI TR-1 07335, "BADGER, a Probe for Nondestructive Testing of Residual Boron-1 0 Absorber Density in Fuel Storage Racks: Development and Demonstration," Dated October 1997
-Describe how the calibration cell is stored and maintained between BADGER campaigns. Provide the areal densities of the calibration panels in the calibration cell along with their uncertainties. Characterize the gaps in the calibration panels in terms of their sizes and distribution along the panel. Provide the areal densities of the zero-dose panels that were used for each BADGER campaign. Evaluate the uncertainties associated with knowing the zero-dose areal densities. Provide the count rates that were measured in the zero-dose panels for each detector. Describe the potential degradation mechanisms of the zero-dose panels due to heat and water chemistry and how they are accounted for. Provide the panel data that was supplied to the RACKLIFE model that characterized the panels when they were first installed in the SFPs. Discuss how the BADGER data is used to verify RACKLIFE. In addition, discuss how the BADGER measurement sample size is chosen and whether the sample size provides a statistically representative sample of the entire population of panels which bounds the worst-case degradation. What version of RACKLIFE is currently being used at PBAPS? How does RACKUFE account for the temperature variations along the length of the Boraflex panel? In Section 3.8 of NET-332-01 (Attachment 2 to the letter dated April 4, 2012), it states that the "corrosion rates of coupons 23 and 24 were calculated based on 72 ... " Please describe how this ASTM standard is applicable to the IN Rack Inserts, since the rack inserts are made of AA1100 aluminum alloy. Also, please explain and justify how it was determined that exfoliation corrosion was the appropriate corrosion mechanism.
M. Pacilio -If you have any questions, please contact me at (301) Docket Nos. 50-277 and Request for Additional cc w/encl: Distribution via LPL 1-2 RidsNrrDorlLpl1-2 RidsNrrDorlDpr RidsNrrPMPeachBottom RidsNrrLAABaxter RidsOgcRp RidsAcrsAcnw_MailCTR RidsRgn1 MailCenter Sincerely, Ira/ Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDeEmcb Resource WJessup, NRR/DE/EMCB KWood, NRRIDSS/SRXB TNakanisihi, NRR/DSS/SRXB EWong, NRRIDE/ESGB RidsNrrDeEsbg Resource RidsNrrDssSrxb Resource ADAMS Accession No.: ML121250569 *via email OFFICE NAME DATE LPL 1-2/PM REnnis 5/7/12 LPL1-2/LA ABaxter* 5/7/12 ESGB/BC GKutesa 5/16/12 SRXB/BC AUlses 5/21/12 LPL1-2/BC MKhanna 5/22/12 OFFICIAL RECORD COpy