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Results
Other: ML032020526, ML032060316, ML033040017, ML040420040, ML040760831, ML040830646, ML040840483, ML040890917, ML040970488, ML040980602, ML041000245, ML041000258, ML041140337, ML042230368, ML042300171, ML043560170, ML050420463, ML050600059, ML050610153, ML050660027
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MONTHYEARML0319606822003-07-14014 July 2003 Request for Additional Information - Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0320205262003-07-21021 July 2003 Notice of Consideration for Mixed Oxide Fuel Lead Assemblies Project stage: Other ML0320303472003-07-22022 July 2003 Memo - Transmittal of Draft Requests for Information on MOX to Licensee Project stage: Draft Other ML0320603162003-07-25025 July 2003 Ltr, Mixed Oxide Lead Fuel Assemblies Project stage: Other ML0322504222003-08-13013 August 2003 Request for Additional Information Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0327500332003-09-23023 September 2003 Mixed Oxide Fuel Land Assembly License Amendment Request Project stage: Request ML0328904052003-10-0101 October 2003 Response to Request for Additional Information Regarding the Use of Mixed Oxide Fuel Lead Assemblies Project stage: Response to RAI ML0328803702003-10-0101 October 2003 Stations - Response to RAI Regarding Mixed Oxide Fuel Lead Assemblies Project stage: Response to RAI ML0328100902003-10-0303 October 2003 Stations, Partial Response to Request for Additional Information Regarding Use of Mixed Oxide Lead Fuel Assemblies Project stage: Response to RAI ML0329705332003-10-28028 October 2003 Draft Letter to Duke Power Requesting Additional Information on Materials Engineering and Environmental Review for MOX Program Project stage: Draft Other ML0330400172003-10-31031 October 2003 Re. MOX Fuel Assemblies and Associated Amendment Requests Project stage: Other ML0332103452003-11-0404 November 2003 Response to Request for Additional Information Regarding the Use of Mixed Oxide Lead Fuel Assemblies Project stage: Response to RAI ML0332505302003-11-21021 November 2003 Request for Additional Information (RAI) Re.: Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0335105632003-12-10010 December 2003 Response to Request for Additional Information Regarding Mixed Oxide Fuel Lead Assemblies Project stage: Response to RAI ML0334503932003-12-11011 December 2003 Draft Letter Requesting Additional Information on MOX LTA Fuel at Catawba Project stage: Draft Other ML0335004082003-12-16016 December 2003 Request for Additional Information Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0335800082003-12-24024 December 2003 Request for Additional Information Regarding Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0402203962004-01-22022 January 2004 Draft Letter Requesting Additional Information on MOX Radiological Consequences Analyses Project stage: Draft Other ML0404200402004-02-0202 February 2004 Additional Information Regarding Mixed Oxide Fuel Lead Assemblies MOX Fuel Rod Free Volume Project stage: Other ML0405100642004-02-0202 February 2004 Response to Request for Additional Information on the Mixed Oxide Fuel Lead Assemblies (Environmental, Radiological, and Materials) Project stage: Response to RAI ML0403500052004-02-0404 February 2004 Request for Additional Information, Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0404906832004-02-20020 February 2004 RAI, Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0407105072004-03-0101 March 2004 Response to Request for Additional Information, Mixed Oxide Fuel Lead Assemblies (Radiological) Project stage: Response to RAI ML0407104972004-03-0101 March 2004 Response to Request for Additional Information, Mixed Oxide Fuel Lead Assemblies (Security) Project stage: Response to RAI ML0407104922004-03-0101 March 2004 Response to Request for Additional Information Mixied Oxide Fuel Lead Assemblies Project stage: Response to RAI ML0407608312004-03-0909 March 2004 Additional Information Regarding Mixed Oxide Fuel Lead Assemblies Criticality Project stage: Other ML0409704702004-03-0909 March 2004 Response to Request for Additional Information Mixed Oxide Fuel Lead Assemblies (Security) Project stage: Response to RAI ML0409302002004-03-0909 March 2004 Response to Request for Additional Information (RAI) Mixed Oxide Fuel Lead Assemblies (Security) Project stage: Response to RAI ML0404400252004-03-10010 March 2004 MOX and McGuire Nuclear Stations, Units 1 and 2, Framatome Anp, Inc., MB7863 and MB7864, Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0408404832004-03-16016 March 2004 Amended Information Regarding Radiological Consequences for MOX Fuel Lead Assemblies Project stage: Other ML0408306462004-03-16016 March 2004 Additional Information Regarding Mixed Oxide Fuel Lead Assemblies Assembly Bow Project stage: Other ML0408909172004-03-26026 March 2004 Withholding from Public Disclosure, Compact Disc, McGuire and Catawba LOCA Input Decks, Proprietary, Framatome Anp, Dated October 3, 2003 Project stage: Other ML0409704882004-03-26026 March 2004 Additional Information Regarding Mixed Oxide Fuel Lead Assemblies No Significant Hazards Consideration Evaluation & Environmental Review Project stage: Other ML0410002452004-03-30030 March 2004 Catawba FHA for MOX LTA Project stage: Other ML0409806022004-03-31031 March 2004 Fuel Burn-up Limit Commitment Project stage: Other ML0409700462004-04-0505 April 2004 Safety Evaluation for Proposed Amendments to Facility Operating License and Technical Specifications to Allow Insertion of Mixed Oxide Fuel Lead Assemblies Project stage: Approval ML0412701622004-04-13013 April 2004 Response to Request for Additional Information - Mixed Oxide Fuel Lead Assemblies (Security) Project stage: Response to RAI ML0411403372004-04-21021 April 2004 Catawba - 04/21/2004 Letter from Margaret J. Bupp to Mark J. Wetterhahn Informing That, Subject to the Board'S Protective Order, Bredl'S Approved Representatives Possess the Requisite Need to Know Re Duke Energy Corp.'S Response to Request. Project stage: Other ML0412105122004-04-30030 April 2004 Westinghouse, Request for Additional Information, Revising the Technical Specification to Allow the Use of Four Mixed Oxide Lead Test Assemblies Project stage: Request ML0412605442004-05-0505 May 2004 5/5/04, Catawba MOX, Non-Safeguards Version of Supplement 1 to Safety Evaluation Security Plan for MOX Fuel Project stage: Approval ML0414002012004-05-19019 May 2004 RAI, Re, Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0421200182004-07-29029 July 2004 Board Notification 2004-10, Supplement 2 to Safety Evaluation for Proposed Amendments to the Facility Operating License and Technical Specifications to Allow Use of Mixed Oxide Fuel Lead Assemblies Project stage: Approval ML0422303682004-08-10010 August 2004 Environmental Assessment and Finding of No Significant Impact Related to Mixed Oxide Lead Test Assemblies Project stage: Other ML0426601442004-08-31031 August 2004 Duke Energy Corporation Catawba Nuclear Station Units 1 & 2, Proposed Amendments to the Facility Operating License and Technical Specifications to Allow Insertion of Mixed Oxide (MOX) Fuel Lead Assemblies (Dose Inputs) Project stage: Request ML0428903432004-09-20020 September 2004 Proposed Amendments to the Facility Operating License and Technical Specifications to Allow Insertion of Mixed Oxide Fuel Lead Assemblies (Revised Dose Evaluations) Project stage: Request ML0427901242004-09-29029 September 2004 Request for Additional Information Concerning Mixed Oxide Lead Fuel Assemblies Project stage: RAI ML0410002582004-09-30030 September 2004 Catawba MOX for AST Weir Project stage: Other ML0428600502004-10-0707 October 2004 Request for Additional Information, Mixed Oxide Fuel Lead Test Project stage: RAI ML0435601702004-12-10010 December 2004 Proposed Amendments to the Facility Operating License and Technical Specifications to Allow Insertion of Mixed Oxide Fuel Lead Assemblies (Additional Information on Revised Does Evaluations) Project stage: Other ML0504204632005-02-14014 February 2005 EA, No Significant Impact of Using MOX Lead Test Assemblies Project stage: Other 2004-02-20
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Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22102A2962022-04-13013 April 2022 Request for Withholding Information from Public Disclosure Response to Request for Additional Information ML22063B1782022-03-0909 March 2022 Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY ML22024A1122022-01-24024 January 2022 2022 CNS POV Inspection Information Request ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 ML20338A3932020-12-0303 December 2020 Notification of Inspection and Request for Information ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20244A0462020-08-31031 August 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20073F3832020-03-13013 March 2020 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station - SG Report (RA-19-0391) - C2R23 ML20052E4282020-02-21021 February 2020 Notification of NRC Fire Protection Team Inspection (Fpti) (NRC Inspection Report 05000412/2020013 and 05000414/2020013) and Request for Information ML20050D3382020-02-21021 February 2020 Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure ML20003E5372020-01-0303 January 2020 NRR E-mail Capture - Catawba PT Limits LAR - RAIs ML19032A5842019-01-31031 January 2019 Emergency Preparedness Program Inspection Request for Information ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19009A5412019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Esps LAR ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18068A5052018-03-0909 March 2018 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Nsws Return Pond Header LAR (CACs MG0245 and MG0246, EPID L-2017-LLA-0297) ML18058B2062018-02-27027 February 2018 Notification of Inspection and Request for Information ML18057A2182018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17335A0972017-11-29029 November 2017 NRR E-mail Capture - Request for Additional Information - Catawba Nuclear Station, Units 1 and 2 - Relief Request 17-CN-001 (CACs MF9807 and MF9808, EPID L-2017-LLR-0032) ML17135A0302017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - Catawba TSTF-197 ML17115A1422017-04-25025 April 2017 NRR E-mail Capture - Request for Additional Information - Catawba SG Report - RFO 21 ML16337A3322017-01-12012 January 2017 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16355A3922016-12-29029 December 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16292A2252016-10-14014 October 2016 Emergency Preparedness Inspection and Request for Information ML16271A0752016-10-12012 October 2016 Request for Additional Information Regarding License Amendment Request for Electrical Power System Alignments for Shared Systems ML16222A7472016-08-0909 August 2016 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML16205A0022016-07-21021 July 2016 Notification of Inspection and Request for Information ML16187A0662016-07-0707 July 2016 Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2936 and MF2937) ML16111B2472016-04-28028 April 2016 Request for Additional Information Re. License Amendment Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML16120A0872016-04-27027 April 2016 Notification of Inspection and Request for Information ML16113A0732016-04-22022 April 2016 Draft RAIs License Amendment Request to Revise TS Section 5.5.2 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16014A7102016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML16007A1902016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Change the RCS Minimum Required Flow Rates ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15252A4012015-09-17017 September 2015 License Amendment Request Regarding Non-Conservative Technical Specification Allowable Value ML15201A5122015-08-13013 August 2015 Request for Additional Information Regarding License Amendment Request to Support a Measurement Uncertainty Recapture Power Uprate for Catawba, Unit 1 2023-09-28
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DRAFT Mr. H. B. Barron Executive Vice President Nuclear Generation Duke Energy Corporation 526 South Church Street Charlotte, NC 28202
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2- REQUEST FOR ADDITIONAL INFORMATION RE: MIXED OXIDE LEAD FUEL ASSEMBLIES (TAC NOS. MB7863 AND MB7864)
Dear Mr. Barron:
By letter dated February 27, 2003, Duke Energy Corporation submitted an application for amendments to the operating licenses for Catawba Nuclear Station, Units 1 and 2. The proposed amendments would revise the Technical Specifications to allow the use of four mixed oxide fuel assemblies at the Catawba station. The Nuclear Regulatory Commission staff has reviewed the information provided and has determined that additional information is required as identified in the Enclosure.
We discussed these questions with your staff on , 2004. Your staff indicated that a response to these issues could be provided . Please contact me at (301) 415-1493, if you have any other questions on these issues.
Sincerely, Robert E. Martin, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414
Enclosure:
Request for Additional Information cc w/encl: See next page
DRAFT REQUEST FOR ADDITIONAL INFORMATION ON APPLICATION FOR MOX LEAD TEST ASSEMBLIES DUKE POWER COMPANY CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 Radiological Conseauences
- 1. In its submittal, the licensee established an increase of 9 percent in the iodine-131 (1-131) inventory of a mixed oxide (MOX) lead test assembly (LTA) over that in an "equivalent" low enrichment uranium (LEU) assembly. This factor is then applied to previously calculated results for the various design basis accidents to estimate what the dose could be with the MOX LTAs in place. This approach is accurate only if the 1-131 concentration used in establishing the percentage increase is the same as that which was used to determine the previously calculated doses. The Nuclear Regulatory Commission (NRC) staff is concerned that the licensee's use of data for an equivalent LEU assembly in lieu of the current licensing basis data may have underestimated the impact on previously analyzed doses. The following examples are illustrative of the staff's concerns. They are based upon information that the staff has available. The licensee may be aware of other information, not provided to the NRC staff in the submittal or its supplements, that may be relevant to the NRC staff's concerns.
In Table Q3(f)-1, provided in the licensee's letter of November 3, 2003, the 1-131 concentration of a 5% MOX assembly with fuel handling accident (FHA) peaking factors was identified as 8.81 E+05 curies. In Attachment 6 of the licensee's letter dated December 20, 2001, an 1-131 concentration of 7.46E+05 curies for an LEU assembly, including the radial peaking factor, was identified. The NRC staff questions whether the values in Attachment 6 are part of the current licensing basis for a FHA since that amendment request was approved based in part on those results. The increase in the 1-131 concentration associated with the MOX LTA is 18.1 percent, double the value apparently assumed in the licensee's present comparative analysis.
Table 15.12 of the Catawba Updated Final Safety Analysis Report (UFSAR) provides a core inventory 1-131 value of 8.9E+07 curies for a power level of 3636 megawatts thermal (MWt). This power level is 6.5 percent greater than the power level of 3411 MWt identified in Table 1 of the licensee's letter dated December 10, 2003. Since the core inventory is directly proportional to power level, the adjusted 1-131 inventory would be 8.9E+07 / 1.065 = 8.36E+07 curies for the core or 8.36E+07 / 193 = 4.33E+05 curies for an average LEU assembly.
Removing the peaking factor from the Table Q3(f)-1 1-131 value yields 8.81 E+05
DRAFT
/1.65 = 5.34E+05 curies. The resulting increase from a current LEU assembly to the MOX LTA (4.33E+5 to 5.34E+05) is 23 percent rather than 9 percent.
For the accidents identified in Tables Q3(b)-1 through Q3(b)-4, please provide the following information:
(1) The quantity of 1-131, in curies, that was utilized in the current analysis of record that provided the tabulated LEU dose (2) The quantity of 1-131, in curies, in the MOX LTA used for comparison.
(3) The rated power plus uncertainty that the LEU and MOX LTA radionuclide inventories were based upon.
(4) The percent increase in the 1-131 concentrations identified in (1) and (2),
adjusted for differences identified in (3)
If the resulting percent increases differ from those used in the licensee's analyses reported in Tables Q3(b)-1 through Q3(b)-4, please revise the submittal, or provide a justification of why the licensee's approach should be found acceptable.
- 2. In a recent teleconference, the licensee explained the basis for the Table Q3(a)-2 release fraction value of 1.96E-4. The NRC staff has determined that it will be relying on this information in preparing its safety evaluation. As such, this information is requested to be submitted by letter. Please explain the derivation of the release fraction value in the forthcoming submittal, as discussed in the teleconference.
The NRC staff reviewed the NUREG/CR-641 0 method cited by the licensee in the teleconference (i.e., Section 3.3.4.8). This section discusses the crushing of small right cylinders of brittle materials by forces applied over the entire upper surface of the specimen by a component with an area greater in size than that of the impacted surface.
It appears that the experimental data were obtained for individual pellets. Please provide a justification of the applicability of these data to fuel pellets contained within fuel pins that are part of a larger fuel assembly. For example, how is the momentum of the fuel assembly structural components reflected in the energy density calculated from the pellet density? Does friction between the pellet surface and the cladding reduce the compressive force represented by the energy density?