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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 DUKE Vice President Catawba Nuclear Station
- ENERGY, Duke Energy CNO1VP 1 4800 Concord Road York, SC 29745 o: 803.701.4251 f: 803.701.3221 CNS-1 4-133 December 17, 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, Unit 1 Docket Number 50-413 Relief Request Serial Number 14-CN-003, Relief Request to Use Alternative Depth Sizing Criteria Pursuant to 10 CFR 50.55a(g)(5)(iii), Duke Energy hereby submits Relief Request 14-CN-003 requesting approval to use an alternative depth sizing qualification for Catawba Unit 1 reactor vessel hot leg and cold leg nozzle-to-safe end welds. The basis for the proposed relief request is provided in the enclosure to this letter.
Duke Energy requests NRC approval of this relief request at your earliest possible convenience.
There are no regulatory commitments contained in this relief request submittal.
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 www.duke-energy.com
U.S. Nuclear Regulatory Commission December 17, 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 Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 Relief Request Serial No. 14-CN-003 Relief Request for Alternative Depth Sizing Criteria, Submitted Pursuant to 10 CFR 50.55a(g)(5)(iii)
Relief Request 14-CN-003 Page 2 of 5
1.0 ASME Code Components Affected
Class 1 Reactor Coolant System (NC) Reactor Vessel Hot Leg Nozzle-to-Safe End and Cold Leg Nozzle-to-Safe End Dissimilar Metal Welds Listed in Table 1 Below.
Table 1 Inspection Plan Nozzle-to-Safe Summary ASME Section XI Description Size End Weld No. Number Item No.
Hot Leg Nozzle 1A to Safe End Weld 29.0" ID (Nom.) 1RPV-W1 5-SE C1.B5.10.0005 B5.10 Hot Leg Nozzle 1B to Safe End Weld 29.0" ID (Nom.) 1RPV-W16-SE C1..B5.10.0006 B5.10 Hot Leg Nozzle 1C to Safe End Weld 29.0" ID (Nom.) 1RPV-W17-SE C1..B5.10.0007 B5.10 Hot Leg Nozzle 1D to Safe End Weld 29.0" ID (Nom.) 1RPV-W18-SE C1.B5.10.0008 B5.10 Cold Leg Nozzle 1A to Safe End Weld 27.5" ID (Nom.) 1RPV-W1l-SE C1.B5.10.0001 B5.10 Cold Leg Nozzle 1B to Safe End Weld 27.5" ID (Nom.) 1RPV-W12-SE C1..B5.10.0002 B5.10 Cold Leg Nozzle 1C to Safe End Weld 27.5" ID (Nom.) 1RPV-W1 3-SE C1..B5.10.0003 B5.10 Cold Leg Nozzle 1D to Safe End Weld 27.5" ID (Nom.) 1RPV-W14-SE C1..B5.10.0004 B5.10 Component materials and nozzle weld configurations are shown in Figure 1.
F- Nozzle Safe End (SS)
N/ozzle (SA-508, Type Class 2)
/ SA-351, CF8A Pipe Figure 1 L Nozzle Cladding (SS)
Hot Leg and Cold Leg Nozzle-to-Safe End Welds (Not to Scale)
I I .
Relief Request 14-CN-003 Page 3 of 5
2.0 Applicable Code Edition and Addenda
2.1 ASME Boiler and Pressure Vessel Code,Section XI, 1998 Edition through the 2000 Addenda.
2.2 The 3rd Inservice Inspection Interval Program for Unit 1 includes ASME Code Case N-695, Qualification Requirements for Dissimilar Metal Piping Welds, Section Xl, Division 1, which has been approved for use in Regulatory Guide 1.147, Rev.
17, Table 1- "Acceptable Section XI Code Cases".
3.0 Applicable Code Requirements 3.1 IWA-2232 requires that ultrasonic examinations be conducted in accordance with Mandatory Appendix I. Appendix 1,1-2220 requires that ultrasonic examinations be qualified by performance demonstration in accordance with Mandatory Appendix VIII. Appendix VIII, Supplement 10, "Qualification Requirements For Dissimilar Metal Piping Welds", Paragraph 3.2(b) requires that "Examination procedures, equipment, and personnel are qualified for depth sizing when the RMS error of the flaw depth measurements, as compared to the true flaw depths, is less than or equal to 0.125 in. (3.2 mm)."
Note that volumetric examinations of the Reactor Vessel nozzle-to-safe end dissimilar metal welds are also required to be performed in accordance with Section XI, Appendix VIII, as required by 10 CFR 50.55a(b)(2)(xv) and 10 CFR 50.55a(b)(2)(xvi).
3.2 Code Case N-695 provides alternatives to the requirements of Appendix VIII, Supplement 10, but paragraph 3.3(c) of this case requires that "Examination procedures, equipment, and personnel are qualified for depth-sizing when the RMS error of the flaw depth measurements, as compared to the true flaw depths, do not exceed 0.125 in. (3 mm)." Code Case N-695 has been accepted by the NRC without condition and is listed in Table 1 of Regulatory Guide 1.147, Rev. 17.
4.0 Impracticality of Compliance 4.1 Since 2002, the nuclear power industry has attempted to qualify personnel and procedures for depth-sizing examinations performed from the inside surface of dissimilar metal and austenitic stainless steel butt welds in PWR piping. As of October 07, 2014, no domestic or international vendor has met the applicable root mean square (RMS) error requirement of ASME Section XI Appendix VIII, Supplement 10, or the alternative qualification requirements of ASME Code Case N-695, as applicable.
4.2 Vendors that Duke Energy is using for performing these examinations have demonstrated an RMS of no less than 0.189 inch.
5.0 Proposed Alternative and Basis for Use Duke Energy proposes to use the following alternative for flaw depth sizing when dissimilar metal welds are examined from the inside surface:
- 1. Examinations shall be performed using ultrasonic (UT) techniques that are qualified for flaw detection and sizing using procedures, personnel and equipment qualified by demonstration in all aspects except depth sizing.
Relief Request 14-CN-003 Page 4 of 5
- 2. A correction factor of the RMS Error - 0.125 inches shall be added to the depths of any measured flaws. The correction factor shall be applied to the most critical location on the flaw in relation to surface proximity.
- 3. Eddy Current (ET) examinations shall be used to confirm whether any detected flaws are surface-breaking.
- 4. If any inner diameter (ID) surface-breaking flaws are detected and measured as 50%
through-wall depth or greater, Duke Energy shall repair the indications or shall perform flaw evaluations and shall submit the evaluations to the NRC for review and approval prior to reactor startup.
These flaw evaluations shall include the following:
- a. Information concerning the mechanism which caused the flaw.
- b. Information concerning the surface roughness/profile in the area of the pipe/weld required to perform the examination, and an estimate of the percentage of potential surface areas with UT probe "lift-off".
All other ASME Code,Section XI requirements for which relief was not specifically requested apply, including the third party review by the Authorized Nuclear Inservice Inspector.
Because compliance with the applicable requirements is impractical, this request is submitted pursuant to 10 CFR 50.55a(g)(5)(iii). Duke Energy believes that the proposed alternative provides reasonable assurance that flaws detected during examination will be sufficiently sized to disposition in accordance with acceptance standards of the ASME Code,Section XI.
6.0 Duration of Proposed Alternative The proposed alternative to the ASME Code is applicable for the third 10-year Inservice Inspection (ISI) Interval at Catawba Nuclear Station, Unit 1, which began on June 29, 2005 and is currently scheduled to end on June 29, 2016.
7.0 Related Industry Relief Requests 7.1 NRC approval of Catawba Nuclear Station, Unit 2 Relief Request 13-CN-001 (ADAMS Accession No. ML13176A400) dated July 8, 2013.
7.2 NRC approval of McGuire Nuclear Station, Unit 2 Relief Request 12-MN-003 (ADAMS Accession No. ML12258A363) dated September 24, 2012.
7.3 NRC approval of McGuire Nuclear Station, Unit 1 Relief Request 13-MN-001 (ADAMS Accession No. ML13086A508) dated March 28, 2013.
8.0 References 8.1 1998 Edition through 2000 Addenda, ASME Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components."
8.2 1998 Edition through 2000 Addenda, ASME Code,Section XI, Appendix VIII, Supplement 10.
8.3 ASME Code Case N-695, Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, Division 1.
Relief Request 14-CN-003 Page 5 of 5 8.4 EPRI Materials Reliability Program: Technical Basis for Change to American Society of Mechanical Engineers (ASME)Section XI Appendix VIII Root- Mean-Square Error Requirement for Qualification of Depth-Sizing for Ultrasonic Testing (UT) Performed from the Inner Diameter (ID) of Large-Diameter Thick-Wall Supplement 2, 10, and 14 Piping Welds (MRP-373).
8.5 EPRI Materials Reliability Program Letter MRP 2012-046, dated November 26, 2012,
Subject:
Assessment of Effect of the Depth-Sizing Uncertainty for Ultrasonic Examinations from ID Surface of Large-Bore Alloy 82/182 and Austenitic Stainless Steel Butt Welds in PWR Primary System Piping, Revision 1.