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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 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 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 type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2 CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122 CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017 Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016 Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068 CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
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Kelvin Henderson Vice President ENERGY, Catawba Nuclear Station Duke Energy CN01VP 1 4800 Concord Road York, SC 29745 CNS-1 4-100 o: 803.701.4251 f: 803.701.3221 September 11, 2014 10 CFR 50.55a U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds
References:
- 1. Letter from Duke Energy to NRC, same subject, dated February 20, 2014
- 2. Letter from NRC to Duke Energy, Catawba Nuclear Station, Units 1 and 2 -
Request for Additional Information Regarding Relief Request 14-CN-001 (TAC Nos. MF3527 and MF3528), dated August 15, 2014 The Reference 1 letter submitted Relief Request 14-CN-001 which requested relief from the volumetric examination coverage requirements of the ASME Code, Section Xl. Reference 2 constitutes NRC Requests for Additional Information (RAls) associated with the Reference 1 relief request.
The purpose of this letter is to formally respond to the Reference 2 RAls. The response is included in the enclosure to this letter. The format of the response is to re-state each NRC RAI, followed by its associated response.
There are no regulatory commitments contained in this RAI response.
If you have any questions or require additional information, please contact L.J. Rudy at (803) 701-3084.
Very truly yours, Kelvin Henderson Vice President, Catawba Nuclear Station LJR/s Enclosure Oq-7 www.duke-energy.com
U.S. Nuclear Regulatory Commission September 11, 2014 Page 2 xc (with enclosure):
V.M. McCree Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.A. Hutto, III NRC Senior Resident Inspector Catawba Nuclear Station G.E. Miller (addressee only)
NRC Project Manager (Catawba)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST SERIAL NUMBER 14-CN-001 LIMITED VOLUMETRIC EXAMINATION OF CLASS 1 WELDS DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 By letter dated February 20, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14052A387), Duke Energy Carolinas, LLC (Duke Energy) submitted relief request 14-CN-001. Pursuant to Title 10 of the Code of FederalRegulations Part 50.55a(g)(5)(iii), the request sought relief from the volumetric examination coverage requirements of the ASME Code,Section XI. In order for the NRC staff to complete its review of the relief request, the following additional information is requested.
RAI 1
The NRC reviewed the volumetric examination coverage amounts obtained during the third 10-year inservice inspection (ISI) interval for the nine welds identified in Table 1 in Duke Energy's Relief Request 14-CN-001, and compared them to the coverage amounts obtained during the second 10-year ISI interval examinations. The NRC noted significant differences in the coverage amounts for the Catawba Nuclear Station (CNS), Units 1 and 2, pressurizer surge nozzle to head welds, as summarized in Table 1 below.
- a. Explain the rationale for using the different scan angles to examine the pressurizer surge nozzle to head welds for both CNS units that led to the significantly different amount of coverage observed for these welds.
Duke Energy Response The 2001 examinations were performed using procedure NDE-620 which utilized 600 and 700 refracted longitudinal wave beams. This technique is the same as qualified under ASME Section XI Appendix VIII PDI procedure PDI-UT-6 even though there is no requirement for this procedure to be qualified under Appendix VIII rules. These transducers used were large and the scanning area is obstructed by the Heater Tubes. The 600 dual 24mm X 42mm, and 70' dual 25mm X 15mm transducers are wide and long. The obstruction caused by the Heater Tubes was 64 square inches for the 600 transducer and 46 square inches for the 70' transducer.
During 2005, 2010, and 2011, examinations were performed using procedure NDE-820 which utilized smaller 0.375" X 0.75", 0.5" X 1.0" and 1," diameter transducers along with additional lower 350 and 450 beam angles. The lower beam angles increase coverage in the area close to the search unit when the scanning surface is restricted due to contacting the Heater Tubes with the rear of the transducer. The combination of lower beam angles and smaller transducers allows more coverage of the examination volume to be achieved.
In both cases the procedures are qualified and are acceptable based on ASME requirements. The rationale is that where more coverage can be achieved using qualified techniques, the improvements to coverage should be made with the use of alternate beam angles, as allowed in procedure NDE-820.
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- b. Explain the capability of the 35 degree scan angle to adequately detect flaws in the pressurizer surge nozzle to head welds compared to the standard 45 degree and 60 degree scan angles.
Duke Energy Response Even though ASME Section XI does not require the PDI / ASME Section XI Appendix VIII performance demonstration qualification process for these non-reactor vessel examinations, the Appendix VIII process has qualified procedures with primary detection beam angles of 350 and less. These lower beam angles have been proven to be useful in detecting flaws in vessels and piping including dissimilar metal weld examination procedures.
These lower beam angles have been useful in increasing and improving examination coverage where restrictions to the scanning surface require their application. Many dissimilar metal weld procedures utilize beam angles as low as 300 for shear waves and 250 for longitudinal wave modes.
- c. The figures in 14-CN-001 associated with this component indicate welds that have been ground flush. Clarify the surface condition of the welds and whether credit was taken for scans performed over the welds.
Duke Energy Response As indicated in the figures in the original relief request, the subject welds have been ground flush. Credit was taken for scans performed over the welds as described below.
The ASME Section XI requirements for vessels other than Reactor Vessels greater than 2" thickness are that the procedures are to be demonstrated in accordance with ASME Section V Article 4 as supplemented by Table 1-2000-1, 1998 edition with Addenda through 2000.
There are no restrictions to examination coverage credit specified in ASME Section V Article 4 or Table 1-2000-1, when scanning across the examination surface.
Examination coverage is addressed by ASME Section V Article 4 paragraph T-424.1, requiring that the volume is examined by moving the search unit over the examination area.
T-441.1.4 requires that the examination volume is scanned, wherever feasible, in two directions, approaching the weld from opposite directions, and parallel to the weld from opposite directions.
T-441.1.5 requires the angle beam search units to be aimed at right angles to the weld axis, with the search unit manipulated so that the ultrasonic beams pass through the entire volume of weld metal. The adjacent base metal in the examination volume must be completely scanned by two angle beams, but need not be completely scanned by both angle beams from both directions. Any combination of two angle beams will satisfy this requirement.
T-441.1.6 requires the angle beam search units shall be aimed parallel to the axis of longitudinal and circumferential welds so that the ultrasonic beams pass through all of the examination volume. Areas blocked by geometric conditions shall be examined from at least one direction.
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Table 1. Pressurizer Surge Nozzle to Head Weld Examination Coverage Amounts 3 rdISI I -,2nd ISI Interval, CNSUnit Weld Coverage and.a n Scan: Angle's'(1) AnglES[of Coverage 1-PZR-W1 81.4% 77.2% +4.2%
[2005, September 8, 2005 Relief Request (ML052590564)]
Scan angles used:
350, 450, 600 Scan angles used:
350, 450 2 2-PZR-W1 81.2 % 42.8 % + 38.4 %
[2001, December 20, 2001 Relief Request (ML0203300121)]
Scan angles Scan angles used:
used:
350, 450, 600 600, 700 Note: (1) Source: Relief Request 14-CN-001 (ML14052A387).
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