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Category:Graphics incl Charts and Tables
MONTHYEARRA-20-0263, Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-09-16016 September 2020 Duke Energy Corp. - Request to Use Provision of Later Edition and Addenda of ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)(iv) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15352A1922015-12-21021 December 2015 Revised Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation ML15268A2982015-10-0505 October 2015 Interim Staff Response Enclosuflooding Tables 1 and 2 ML15226A5252015-09-0303 September 2015 HAhn_8-13-2015 ML15230A0702015-09-0303 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10CFR50.54 Information Request - Flood Causing Mechanism Reevaluation ML15141A0542015-05-0707 May 2015 Enclosure 6, MNS EAL Wallcharts ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T CNS-14-100, Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds2014-09-11011 September 2014 Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds ML12312A0692012-10-17017 October 2012 Table 16.8-1-2 Unit 2 Cpcopds ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML11207A4572011-07-21021 July 2011 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML1103500032011-02-0909 February 2011 Correction Letter for License Amendment Nos. 262 and 258, Regarding Technical Specification 3.8.4 DC (Direct Current) Sources - Operating. ML1025600662010-09-0808 September 2010 Response to Request for Additional Information Related to the License Amendment Request Applicable to Technical Specification (TS) 3.8.4 DC Sources-Operating ML0828300142008-10-0606 October 2008 Response to Request for Additional Information License Amendment Request for Implementation of Alternative Source Term ML0823302222008-08-20020 August 2008 Choice Letter Attachment Q - Pump Strainer Dp Data Analysis ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0715002972007-05-22022 May 2007 Units 1 & 2 - Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0529902932005-10-19019 October 2005 FAQ Log 10/19/2005 ML0506100192005-02-17017 February 2005 Request for Relief Number 05-CN-001 Limited Weld Examinations During End-of-Cycle 14 Refueling Outage ML0403602192004-01-22022 January 2004 /22/2004 Meeting Handouts by the Licensee - Enclosure 3 ML0307904262003-03-20020 March 2003 Attachment - Table 1 Summary of Relief Requests 2020-09-16
[Table view] Category:Letter
MONTHYEARIR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf IR 05000369/20244032024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, “Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20240102024-03-13013 March 2024 Comprehensive Engineering Team Inspection Report 05000369/2024010 and 05000370/2024010 IR 05000413/20243012024-03-12012 March 2024 – Notification of Licensed Operator Initial Examination 05000413/2024301 and 05000414/2024301 IR 05000413/20230062024-02-28028 February 2024 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - (NRC Inspection Report 05000413/2023006 and 05000414/2023006) IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000413/20230042024-02-0202 February 2024 – Integrated Inspection Report 05000413-2023004 and 05000414-2023004 IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary 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 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 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 IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) 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 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 2024-08-08
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THOMAS C. GEER Dkery Vice President Nuclear Engineering Duke Energy Corporation 526 South Church St.
Charlotte, NC 28202 May 22, 2007 Mailing Address:
EC08H / PO Box 1006 U. S. Nuclear Regulatory Commission Charlotte, NC 28201-1006 Washington, D. C. 20555-0001 704 382 4712 Attention: Document Control Desk 704 382 7852 fax tcgeer@duke-energy.corn
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)
McGuire Nuclear Station, Units 1 and 2 Docket Numbers 50-369 and 50-370 Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model
Reference:
Letter from Thomas C. Geer (Duke) to USNRC, "Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model,"
March 13, 2007 10 CFR 50.46 (a)(3)(ii) requires the reporting of changes to or errors in the Emergency Core Cooling System (ECCS) evaluation models. This report covers the small break loss of coolant accident (SBLOCA) re-analyses recently performed by Westinghouse (at the request of Duke) to support decreased intermediate head safety injection and centrifugal charging pump (IHSI/CCP) flows at all McGuire/Catawba units. The reduced flows were used in the SBLOCA analyses to (1) account for the technical specification surveillance limits of +/-2% on the frequency of the emergency diesel generators (EDGs), and (2) obtain additional test acceptance criteria (TAC) margin for the IHSI and CCP pumps. At the time the potential EDG frequency reduction was discovered, an estimated impact on SBLOCA peak clad temperature (PCT) was not necessary due to sufficient ECCS injected flow margin.
Large break loss of coolant accident (LBLOCA) analyses were not re-analyzed as sufficient low head safety injection (LHSI) flow margin exists in the current analyses to offset the reduced flow due to the frequency reduction of the EDGs.
Implementation of these analyses represents a new SBLOCA analysis of record, and includes the impacts of the NOTRUMP mixing level tracking/region depletion and bubble rise/drift flux model errors. Although implementation of these analyses are voluntary, this report is being issued due to calculated PCT increases of 108 0 F for McGuire Unit 1, 98 0 F for both McGuire Unit 2 and Catawba Unit 1, and 132°F for Catawba Unit 2 versus the final PCT values reported in the above reference.
www. duke-energy. com AoD(
U.S. Nuclear Regulatory Commission May 22, 2007 Page 2 The McGuire and Catawba Updated Final Safety Analysis Reports (UFSARs) will be revised as required by 10 CFR 50.71(e) to reflect these SBLOCA re-analyses following the issuance of this report.
McGuire Units 1 and 2 and Catawba Unit 1 were analyzed separately from Catawba Unit 2 due to steam generator differences. All four plants were analyzed with a break spectrum of 1.5, 2.0, 3.0, and 4.0 inch breaks. A review of the McGuire Units 1 and 2 and Catawba Unit 1 evaluation results shows a limiting PCT of 1323 0 F and maximum transient oxidation of 0.24% for the 2.0 inch break. A review of the Catawba Unit 2 evaluation results shows a limiting PCT of 1243 0 F for the 4.0 inch break and maximum transient oxidation of 0.10% for the 3.0 inch break.
A summary of the SBLOCA PCTs for McGuire Units 1 & 2 and Catawba Unit 1 is provided in Table 1. Table 2 provides a summary of the SBLOCA PCTs for Catawba Unit 2.
Please address any comments or questions regarding this matter to L. B. Jones at (704) 382-4753.
Sincerely, Thomas C. Geer Attachments Table 1 - SBLOCA Peak Cladding Temperature Summary - McGuire Units 1 & 2 and Catawba Unit 1 Table 2 - SBLOCA Peak Cladding Temperature Summary - Catawba Unit 2
U.S. Nuclear Regulatory Commission May 22, 2007 Page 3 xc: (with attachments)
W. D. Travers, Region II Administrator U.S. Nuclear Regulatory Commission Sam Nunn Atlanta Federal Center, 23 T85 61 Forsyth St., SW Atlanta, GA 30303-8931 J. F. Stang, Senior Project Manager (CNS & MNS)
U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 J. B. Brady, NRC Senior Resident Inspector McGuire Nuclear Station A. T. Sabisch, NRC Senior Resident Inspector Catawba Nuclear Station
U.S. Nuclear Regulatory Commission May 22, 2007 Page 4 bxc (with attachments)
R. L. Gill - EC05P K. L. Ashe - MG01 RC R. D. Hart - CN01 RC R. A. Hight - EC08H S. B. Thomas - EC08H H. D. Brewer- EC081 K. L. Crane - MG01 RC K. E. Nicholson - CN01 RC Date File - CN01VP NCMPA-1 SREC PMPA NCEMC NRIA File - ELL MNS Master File 801.01- MG01DM CNS Master File 801.01 - CN04DM NED File - E-NRC-LOCA - EC08H
U.S. Nuclear Regulatory Commission May 22, 2007 ATTACHMENTS Table 1 - SBLOCA Peak Cladding Temperature Summary - McGuire Units I & 2 and Catawba Unit I Table 2 - SBLOCA Peak Cladding Temperature Summary - Catawba Unit 2
U.S. Nuclear Regulatory Commission May 22, 2007 Table I SBLOCA Peak Cladding Temperature Summary - McGuire Units 1 & 2 and Catawba Unit I SBLOCA PCT (-F) Comments Evaluation model: NOTRUMP Analysis of record PCT 1323 References A & B Prior errors (APCT)
- 1. None 0 Prior evaluation model changes (APCT)
- 1. None 0 Errors (APCT)
- 1. None 0 Evaluation model changes (APCT)
- 1. None 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1323
References:
A) Westinghouse Report DPC-06-101, "Small Break LOCA Evaluation of Reduced ECCS Flows for McGuire Units 1 & 2 and Catawba Units 1 & 2", December 14, 2006.
B) Westinghouse Letter LTR-LIS-06-453, "10 CFR 50.46 Report for the McGuire Units 1 and 2 and Catawba Units 1 and 2 Reduced ECCS Flow SBLOCA Evaluation", December 19, 2006.
Table 2 SBLOCA Peak Cladding Temperature Summary - Catawba Unit 2 SBLOCA PCT (°F) Comments Evaluation model: NOTRUMP Analysis of record PCT 1243 References A & B Prior errors (APCT)
- 1. None 0 Prior evaluation model changes (APCT)
- 1. None 0 Errors (APCT)
- 1. None 0 Evaluation model changes (APCT)
- 1. None 0 Absolute value of errors/changes for this report (APCT) 0 Net change in PCT for this report 0 Final PCT 1243
References:
A) Westinghouse Report DPC-06-101, "Small Break LOCA Evaluation of Reduced ECCS Flows for McGuire Units 1 & 2 and Catawba Units 1 & 2", December 14, 2006.
B) Westinghouse Letter LTR-LIS-06-453, "10 CFR 50.46 Report for the McGuire Units 1 and 2 and Catawba Units 1 and 2 Reduced ECCS Flow SBLOCA Evaluation", December 19, 2006.