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| {{#Wiki_filter:Exelon Generation September 1, 2016 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Unit 2 Renewed Facility Operating License No. DPR-69 NRC Docket No. 50-318 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp | | {{#Wiki_filter:Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.55a September 1, 2016 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Unit 2 Renewed Facility Operating License No. DPR-69 NRC Docket No. 50-318 |
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| ==Subject:== | | ==Subject:== |
| Relief Request for Dissimilar Metal Butt Weld Examinations | | Relief Request for Dissimilar Metal Butt Weld Examinations |
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| ==References:== | | ==References:== |
| : 1) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated March 5, 2015 2) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated November 24, 2015 3) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated January 28, 2016 4) Email from R. Guzman (U.S. Nuclear Regulatory Commission) to T. Loomis (Exelon Generation Company, LLC), 11 Calvert Cliffs Request for Additional Information | | : 1) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated March 5, 2015 |
| -Relief Request No. RR-ISl-04-11 (CAC No. MF7291 )," dated August 9, 2016 In the Reference 3 letter, Exelon Generation Company, LLC (Exelon), proposed an alternative to the requirements of 10 CFR 50.55a(g)(6)(ii)(F) regarding examination coverage of dissimilar metal butt welds on the basis that complying with the specified requirement would result in hardship or unusual difficulty for Calvert Cliffs Nuclear Power Plant, Unit 2. A similar relief request was submitted for Unit 1 in the Reference 1 letter. In the Reference 2 letter, responses to requests for additional information were supplied for the Unit 1 relief request. In Reference 4, the U.S. Nuclear Regulatory Commission requested additional information. | | : 2) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated November 24, 2015 |
| | : 3) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated January 28, 2016 |
| | : 4) Email from R. Guzman (U.S. Nuclear Regulatory Commission) to 11 T. Loomis (Exelon Generation Company, LLC), Calvert Cliffs Request for Additional Information - Relief Request No. RR-ISl-04-11 (CAC No. |
| | MF7291 )," dated August 9, 2016 In the Reference 3 letter, Exelon Generation Company, LLC (Exelon), proposed an alternative to the requirements of 10 CFR 50.55a(g)(6)(ii)(F) regarding examination coverage of dissimilar metal butt welds on the basis that complying with the specified requirement would result in hardship or unusual difficulty for Calvert Cliffs Nuclear Power Plant, Unit 2. A similar relief request was submitted for Unit 1 in the Reference 1 letter. In the Reference 2 letter, responses to requests for additional information were supplied for the Unit 1 relief request. |
| | In Reference 4, the U.S. Nuclear Regulatory Commission requested additional information. |
| Attached is our response. | | Attached is our response. |
| Relief Request for Dissimilar Metal Butt Weld Examinations September 1, 2016 Page2 There are no regulatory commitments in this letter. If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510. | | |
| Respectfully, David T. Gudger Manager -Licensing | | Relief Request for Dissimilar Metal Butt Weld Examinations September 1, 2016 Page2 There are no regulatory commitments in this letter. |
| & Regulatory Affairs Exelon Generation Company, LLC | | If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510. |
| | Respectfully, David T. Gudger Manager - Licensing & Regulatory Affairs Exelon Generation Company, LLC |
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| ==Attachment:== | | ==Attachment:== |
| | Response to Request for Additional Information - Relief Request RR-ISl-04-11 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, CCNPP USNRC Project Manager [CCNPP] |
| | S. T. Gray, State of Maryland |
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| | Attachment Response to Request for Additional Information - Relief Request RR-ISl-04-11 |
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| | Relief Request for Dissimilar Metal Butt Weld Examinations Relief Request RR-ISl-04-11 Response to Request for Additional Information Page 1 Question: |
| | Recent operational experience with the ISi of dissimilar metal butt welds in nuclear power plants include several instances of human errors in the application of qualified nondestructive examination procedures. Licensee Event Report No. 2016-002 dated April 14, 2016 (ADAMS Accession No. ML16106A304) describes an event at Calvert Cliffs Nuclear Power Plant, Unit 1 (CCNPP1) on February 20, 2016, which identified an 81.8 percent through-wall flaw. This flaw had been previously examined in 2010, with techniques which appear to be similar to those used on CCNPP2 in 2011 as described in the January 28, 2016 submittal, without identifying the true extent of the through-wall flaw. Please describe lessons learned from the February 2016 CCNPP1 event which will be applied to the 2017 CCNPP2 examinations to insure the quality and effectiveness of the ultrasonic examinations. |
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| Response to Request for Additional Information | | ===Response=== |
| -Relief Request RR-ISl-04-11 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, CCNPP USNRC Project Manager [CCNPP] S. T. Gray, State of Maryland Attachment Response to Request for Additional Information
| | The Nondestructive Evaluation (NOE) Improvement Focus Group (NIFG) was formed to address NOE reliability and extent of condition actions in response to North Anna dissimilar metal weld operating experience. The operating experience occurred early in 2012 and involved the missed detection of flaws during ultrasonic examinations performed according to the ASME Boiler and Pressure Vessel Code, Section XI, Appendix VIII, Supplement 10. Exelon 11 has implemented the needed 11 requirements of NFIG according to the Nuclear Energy Institute (NEI) Guideline for the Management of Materials Issues (NEI 03-08). |
| -Relief Request RR-ISl-04-11 Question:
| | During the 2016 examination, an improved scanner was used that increased the data quality. The ASME Section XI, Appendix VIII qualified technique also included a larger aperture search unit, additional examination angles, lower frequency, beam skewing, and enhanced focusing. This improved data enhanced the image of the previously reported axial flaw. After reviewing the data, it was determined that this optimized technique provided sufficient data to detect the connection of the previously reported shallow axial flaw and the embedded indication that was also present in previous examination data. |
| Relief Request for Dissimilar Metal Butt Weld Examinations Relief Request RR-ISl-04-11 Response to Request for Additional Information Page 1 Recent operational experience with the ISi of dissimilar metal butt welds in nuclear power plants include several instances of human errors in the application of qualified nondestructive examination procedures.
| | Exelon will use the current qualified examination techniques and the NEI 03-08 "needed" elements for effective and reliable examination of the dissimilar metal welds in 2017.}} |
| Licensee Event Report No. 2016-002 dated April 14, 2016 (ADAMS Accession No. ML16106A304) describes an event at Calvert Cliffs Nuclear Power Plant, Unit 1 (CCNPP1) on February 20, 2016, which identified an 81.8 percent through-wall flaw. This flaw had been previously examined in 2010, with techniques which appear to be similar to those used on CCNPP2 in 2011 as described in the January 28, 2016 submittal, without identifying the true extent of the through-wall flaw. Please describe lessons learned from the February 2016 CCNPP1 event which will be applied to the 2017 CCNPP2 examinations to insure the quality and effectiveness of the ultrasonic examinations.
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| Response:
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| The Nondestructive Evaluation (NOE) Improvement Focus Group (NIFG) was formed to address NOE reliability and extent of condition actions in response to North Anna dissimilar metal weld operating experience. | |
| The operating experience occurred early in 2012 and involved the missed detection of flaws during ultrasonic examinations performed according to the ASME Boiler and Pressure Vessel Code, Section XI, Appendix VIII, Supplement | |
| : 10. Exelon has implemented the 11 needed 11 requirements of NFIG according to the Nuclear Energy Institute (NEI) Guideline for the Management of Materials Issues (NEI 03-08). During the 2016 examination, an improved scanner was used that increased the data quality. The ASME Section XI, Appendix VIII qualified technique also included a larger aperture search unit, additional examination angles, lower frequency, beam skewing, and enhanced focusing.
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| This improved data enhanced the image of the previously reported axial flaw. After reviewing the data, it was determined that this optimized technique provided sufficient data to detect the connection of the previously reported shallow axial flaw and the embedded indication that was also present in previous examination data. Exelon will use the current qualified examination techniques and the NEI 03-08 "needed" elements for effective and reliable examination of the dissimilar metal welds in 2017.}} | |
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MONTHYEARML16028A1562016-01-28028 January 2016 Relief Request for Dissimilar Metal Butt Weld Examinations Project stage: Request 05000317/LER-2016-0022016-04-14014 April 2016 Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit, LER 16-002-00 for Calvert Cliffs, Unit 1, Regarding Pressurizer Safety Relief Nozzle Dissimilar Metal Weld Flaw Exceeded American Society of Mechanical Engineers Code Allowable Limit Project stage: Request ML16222A1252016-08-0909 August 2016 Request for Additional Information - Relief Request No. RR-ISI-04-11, 2016/08/08 E-mail from R.Guzman to T.Loomis Project stage: RAI ML16246A2022016-09-0101 September 2016 Response to Request for Additional Information Regarding Relief Request for Dissimilar Metal Butt Weld Examinations Project stage: Response to RAI ML16337A1902016-12-19019 December 2016 Relief Request RR-ISI-4-11 for Dissimilar Metal Butt Weld Examinations Project stage: Other 2016-04-14
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Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 IR 05000318/20240072024-11-0606 November 2024 Assessment Follow-Up Letter for Calvert Cliffs Nuclear Power Plant, Unit 2 (Report 05000318/2024007) ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000317/20240032024-10-22022 October 2024 Integrated Inspection Report 05000317/2024003, 05000318/2024003, and Independent Spent Fuel Storage Installation Report 07200008/2024001 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24283A0012024-10-0909 October 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000317/20245012024-10-0707 October 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000317/2024501 and 05000318/2024501 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000317/20240052024-08-29029 August 2024 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2024005 and 05000318/2024005) ML24240A1112024-08-27027 August 2024 Registration of Use of Casks to Store Spent Fuel ML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000317/20240022024-08-0606 August 2024 Integrated Inspection Report 05000317/2024002 and 05000318/2024002 IR 05000317/20240102024-07-31031 July 2024 Age-Related Degradation Inspection Report 05000317/2024010 and 05000318/2024010 ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24198A0442024-07-16016 July 2024 Inservice Inspection Report IR 05000317/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000317/2024401 and 05000318/2024401 ML24177A1832024-06-25025 June 2024 Inservice Inspection Report RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24161A0012024-06-0909 June 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML24150A0522024-05-29029 May 2024 Operator Licensing Examination Approval ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24136A1962024-05-15015 May 2024 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report IR 05000317/20240012024-05-0707 May 2024 Integrated Inspection Report 05000317/2024001 and 05000318/2024001 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests 05000317/LER-2024-002, Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus2024-04-29029 April 2024 Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus 05000318/LER-2024-001, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip2024-04-24024 April 2024 Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip ML24101A1942024-04-22022 April 2024 Closeout Letter for GL 2004-02 ML24114A0182024-04-18018 April 2024 Electronic Reporting of Occupational Exposure Reporting 05000318/LER-2023-004-01, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-04-12012 April 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000317/20240402024-04-11011 April 2024 95001 Supplemental Inspection Report 05000317/2024040 and Follow-Up Assessment Letter RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24082A0082024-03-22022 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24078A1152024-03-18018 March 2024 10 CFR 50.46 Annual Report ML24059A0632024-03-15015 March 2024 Authorization and Safety Evaluation for Alternative Request ISI-05-021 (EPID L-2023-LLR-0006) - Non-Proprietary IR 05000317/20230062024-02-28028 February 2024 Annual Assessment Letter for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, (Reports 05000317/2023006 and 05000318/2023006 ML24052A0072024-02-14014 February 2024 Core Operating Limits Report for Unit 1, Cycle 27, Revision 0 ML24040A0962024-02-0909 February 2024 Notification of Readiness for NRC 95001 Inspection ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 IR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank 2024-09-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23241A8432023-08-29029 August 2023 Enclosure 3 - Response to Request for Additional Information - Non-Proprietary Version ML23166A1052023-06-15015 June 2023 Response to Request for Additional Information Related to the License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML23155A0012023-06-0404 June 2023 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (C RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P ML21334A3422021-11-30030 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21320A2422021-11-16016 November 2021 Stations - Response to Request for Additional Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML21308A5072021-11-0404 November 2021 Supplement to Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request ML21298A0432021-10-25025 October 2021 Response to Request for Additional Information Regarding the Spent Fuel Pool Cooling - Shutdown Cooling Systems Licensing Design Basis License Amendment Request JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments ML21208A0072021-07-26026 July 2021 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-20-017, Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-8852021-02-0101 February 2021 Response to Request for Additional Information - Proposed Alternative to Utilize Code Case N-885 ML20317A1122020-11-12012 November 2020 Final Response and Close-out to Generic Letter 2004-02 ML20280A5132020-10-0606 October 2020 Response to Request for Additional Information - End of Interval Relief Request Associated with the Fourth Ten-Year Inservice Inspection (ISI) Interval ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information ML20182A1102020-06-30030 June 2020 Response to Request for Additional Information to License Amendment Request - Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements Voltage ML20107F7652020-04-16016 April 2020 Response to Request for Additional Information to License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 ML19282B7182019-10-0909 October 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19277D1032019-10-0303 October 2019 Response to Request for Additional Information Revised - Final Response to Generic Letter 2004-02 ML19217A3372019-08-0606 August 2019 Response to RAI #6 Regarding the Application to Adopt 10 CFR 50.69 ML19217A1432019-08-0505 August 2019 Revised Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19200A2162019-07-19019 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19183A0122019-07-0101 July 2019 Response to Request for Additional Information Regarding the Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ... JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18316A0342018-11-12012 November 2018 Response to Request for Additional Information: Proposed Changes to Technical Specification 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to 14 ... ML18283A0342018-10-10010 October 2018 Supplement to Final Response to Generic Letter 2004-02, Dated August 13, 2018 ML18239A2602018-08-27027 August 2018 Supplement to Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk .. ML18201A4062018-06-21021 June 2018 Plants, Units 1 and 2 - Exelon'S Response to NRC Questions ML18172A1452018-06-21021 June 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed ... NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18047A1242018-02-16016 February 2018 Relief Requests Associated with Fifth Ten-Year Lnservice Testing Interval: Supplement 1 - Response to Request for Additional Information ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML18018B3402018-01-18018 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. ML18011A6652018-01-11011 January 2018 Response to Request for Additional Information License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times. RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 ML17081A3032017-03-22022 March 2017 Response to Request for Additional Information to License Amendment Request - Control Room Emergency Ventilation System 2024-08-09
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Exelon Generation 200 Exelon Way Kennett Square. PA 19348 www.exeloncorp.com 10 CFR 50.55a September 1, 2016 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Calvert Cliffs Nuclear Power Plant, Unit 2 Renewed Facility Operating License No. DPR-69 NRC Docket No. 50-318
Subject:
Relief Request for Dissimilar Metal Butt Weld Examinations
References:
- 1) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated March 5, 2015
- 2) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated November 24, 2015
- 3) Letter from D. Gudger (Exelon Generation Company, LLC) to U.S. Nuclear Regulatory Commission, "Relief Request for Dissimilar Metal Butt Weld Examinations," dated January 28, 2016
- 4) Email from R. Guzman (U.S. Nuclear Regulatory Commission) to 11 T. Loomis (Exelon Generation Company, LLC), Calvert Cliffs Request for Additional Information - Relief Request No. RR-ISl-04-11 (CAC No.
MF7291 )," dated August 9, 2016 In the Reference 3 letter, Exelon Generation Company, LLC (Exelon), proposed an alternative to the requirements of 10 CFR 50.55a(g)(6)(ii)(F) regarding examination coverage of dissimilar metal butt welds on the basis that complying with the specified requirement would result in hardship or unusual difficulty for Calvert Cliffs Nuclear Power Plant, Unit 2. A similar relief request was submitted for Unit 1 in the Reference 1 letter. In the Reference 2 letter, responses to requests for additional information were supplied for the Unit 1 relief request.
In Reference 4, the U.S. Nuclear Regulatory Commission requested additional information.
Attached is our response.
Relief Request for Dissimilar Metal Butt Weld Examinations September 1, 2016 Page2 There are no regulatory commitments in this letter.
If you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.
Respectfully, David T. Gudger Manager - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information - Relief Request RR-ISl-04-11 cc: Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, CCNPP USNRC Project Manager [CCNPP]
S. T. Gray, State of Maryland
Attachment Response to Request for Additional Information - Relief Request RR-ISl-04-11
Relief Request for Dissimilar Metal Butt Weld Examinations Relief Request RR-ISl-04-11 Response to Request for Additional Information Page 1 Question:
Recent operational experience with the ISi of dissimilar metal butt welds in nuclear power plants include several instances of human errors in the application of qualified nondestructive examination procedures. Licensee Event Report No. 2016-002 dated April 14, 2016 (ADAMS Accession No. ML16106A304) describes an event at Calvert Cliffs Nuclear Power Plant, Unit 1 (CCNPP1) on February 20, 2016, which identified an 81.8 percent through-wall flaw. This flaw had been previously examined in 2010, with techniques which appear to be similar to those used on CCNPP2 in 2011 as described in the January 28, 2016 submittal, without identifying the true extent of the through-wall flaw. Please describe lessons learned from the February 2016 CCNPP1 event which will be applied to the 2017 CCNPP2 examinations to insure the quality and effectiveness of the ultrasonic examinations.
Response
The Nondestructive Evaluation (NOE) Improvement Focus Group (NIFG) was formed to address NOE reliability and extent of condition actions in response to North Anna dissimilar metal weld operating experience. The operating experience occurred early in 2012 and involved the missed detection of flaws during ultrasonic examinations performed according to the ASME Boiler and Pressure Vessel Code,Section XI, Appendix VIII, Supplement 10. Exelon 11 has implemented the needed 11 requirements of NFIG according to the Nuclear Energy Institute (NEI) Guideline for the Management of Materials Issues (NEI 03-08).
During the 2016 examination, an improved scanner was used that increased the data quality. The ASME Section XI, Appendix VIII qualified technique also included a larger aperture search unit, additional examination angles, lower frequency, beam skewing, and enhanced focusing. This improved data enhanced the image of the previously reported axial flaw. After reviewing the data, it was determined that this optimized technique provided sufficient data to detect the connection of the previously reported shallow axial flaw and the embedded indication that was also present in previous examination data.
Exelon will use the current qualified examination techniques and the NEI 03-08 "needed" elements for effective and reliable examination of the dissimilar metal welds in 2017.