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EPID:L-2018-LLR-0391, Submittal of Relief Requests Associated with the Fifth Inservice Inspection (ISI) Interval (Approved, Closed) |
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MONTHYEARML19106A0032019-04-15015 April 2019 Submittal of Relief Requests Associated with the Fifth Inservice Inspection (ISI) Interval Project stage: Request ML19196A1232019-07-19019 July 2019 Issuance of Relief Request 15R-04 Use of Encoded Phased Array Ultrasonic Examination Techniques Project stage: Approval 2019-04-15
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Category:Code Relief or Alternative
MONTHYEARML24344A2742024-12-19019 December 2024 Alternative Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case OMN-32 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) ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping ML22195A0252023-01-0303 January 2023 Authorization and Safety Evaluation for Alternative Request No. ISI-05-016 RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. ML22105A4052022-05-0202 May 2022 Authorization and Safety Evaluation for Proposed Alternative No. ISI-05-019 ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21190A0042021-09-0202 September 2021 Proposed Alternative to the Requirements of the ASME Section XI, Subsection Iwl Concerning Unbound Post-Tensioning Systems ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21130A0382021-05-21021 May 2021 Memo to File - Draft Request for Additional Information Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20275A1022020-11-0404 November 2020 Proposed Alternative I4r-07 to the Requirements of the American Society of Mechanical Engineers Code ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20196L7242020-07-14014 July 2020 Acceptance of Relief Requests Associated with Inservice Inspection Impracticality 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 ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations RS-20-020, Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi)2020-02-28028 February 2020 Relief Request for Alternative Frequency to Supplemental Indication Requirements of 10 CFR 50.55a(b)(3)(xi) ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19168A1172019-07-29029 July 2019 Issuance of Relief Request 15R-03 Use of ASME Code N-513-4 ML19196A1232019-07-19019 July 2019 Issuance of Relief Request 15R-04 Use of Encoded Phased Array Ultrasonic Examination Techniques ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19136A2162019-05-30030 May 2019 Use of a Provision in a Later Edition of the ASME Code ML19106A0032019-04-15015 April 2019 Submittal of Relief Requests Associated with the Fifth Inservice Inspection (ISI) Interval JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 ML17297A5242017-11-0606 November 2017 R. E. Ginna - Request for Use of a Portion of a Later Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (CAC Nos. MG0079-MG0083; EPID L-2017-LLR-0061) ML17228A7082017-08-21021 August 2017 Acceptance of Requested Licensing Action Relief Requests GV-RR-01, RC-RR-01, and SI-RR-01 ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML16337A1902016-12-19019 December 2016 Relief Request RR-ISI-4-11 for Dissimilar Metal Butt Weld Examinations ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML16138A0212016-05-19019 May 2016 Proposed Alternative to Use Code Case N-789 (CAC Nos. MF7018-MF7022) ML16033A4082016-02-11011 February 2016 Relief Request for Dissimilar Metal Butt Weld Examinations ML15327A3672015-12-0707 December 2015 Relief Request for Extension of Volumteric Examination Interval for Reactor Vessel Heads with Alloy 690 Nozzles ML15201A0672015-07-13013 July 2015 Relief Request for Extension of Volumetric Examination Interval for Reactor Vessel Heads with Alloy 690 Nozzles ML14246A0692014-12-19019 December 2014 Relief Request RR-ISI-04-08, Revision 1, Request for Relief Using Alternative Repair for Buried Saltwater Piping (Tac Nos. MF3413 and MF3414) ML14279A5652014-11-0606 November 2014 Relief Request RR-ISI-04-09 Regarding Saltwater System Piping Repair ML14247A5552014-09-24024 September 2014 Relief Request IST-RR-01 Regarding the Frequency of Inservice Testing Requirements of the Pumps and Valves ML13297A2932013-11-13013 November 2013 Relief Request RR-ISI-04-08 Regarding Mitigating of Buried Saltwater Piping Degradation ML13051A7402013-02-18018 February 2013 Response to Request for Additional Information - Relief Request RR-ISI-04-07A, Dissimilar Metal Butt Welds Baseline Examinations ML12345A0552012-12-19019 December 2012 Relief Request RR-ISI-04-06 from ASME Code Case N-770-1 Inspection Coverage Requirement for Volumetric Examination of Reactor System Dissimilar Metal Butt Welds ML12164A3722012-06-0707 June 2012 Relief Request Dissimilar Metal Butt Welds Baseline Examinations (RR-ISI-04-07A) ML12009A0732011-12-29029 December 2011 Relief Requests for Dissimilar Metal Butt Welds Baseline Inspections (RR-ISI-04-06 & ISI-04-07) ML1109104462011-04-26026 April 2011 Third 10-Year Interval Inservice Inspection (ISI) Program Plan Requests for Relief ISI-24, ISI-25, ISI-26, and ISI-27, for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 ML1014100602010-05-18018 May 2010 Request for Approval of Alternate (Relief Request) for Dissimilar Metal Weld Repairs (ISI-04-05) ML0930300522009-11-0909 November 2009 Relief Request ISI-022 & ISI-023 to Extend Reactor Vessel and Reactor Vessel Internal Weld Examinations-Calvert Cliffs Nuclear Power Plant, Unit 1 ML0905401222009-02-24024 February 2009 Acceptance Review of Relief Requests ISI-04-01 Through ISI-04-04-Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 ML0905400622009-02-18018 February 2009 Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld Examinations - Relief Requests (ISI-022 and ISI-023) ML0712300902007-04-27027 April 2007 Part 21 Interim Report, Dresser Investigation File No. 2007-02, Interim Reporting of a Potential Defect Involving Power Actuated Pressure Relief Valves Supplied to Calvert Cliffs, Fort Calhoun and Oconee Plants 2024-07-23
[Table view] Category:Letter
MONTHYEARML25024A0902025-01-24024 January 2025 Automatic Reactor Trip Due to Main Turbine Loss of Load (Cover Letter) ML24353A1372025-01-15015 January 2025 Proprietary Determination Constellation Energy Generation, LLC 2024 Deferred Premiums ML25007A0752025-01-0707 January 2025 Submittal of Initial Operator License Examination Outline ML24344A2742024-12-19019 December 2024 Alternative Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case OMN-32 ML24339B7292024-12-18018 December 2024 Amd - Constellation - Adoption of TSTF-591 IR 05000317/20254032024-12-16016 December 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000317/2025403 and 05000318/2025403 ML24344A1962024-12-0909 December 2024 Automatic Reactor Trip Due to Main Turbine Loss of Load (Letter) RS-24-077, Application to Revise Technical Specifications for Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process2024-12-0909 December 2024 Application to Revise Technical Specifications for Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process ML24331A2592024-11-27027 November 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML24331A2792024-11-26026 November 2024 Supplement to 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 - Revise LaSalle, Units 1 and 2 Technical Specificati IR 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 ML24267A0792024-10-23023 October 2024 Calvert Exemption Issuance Letter 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 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 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 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 2025-01-07
[Table view] Category:Safety Evaluation
MONTHYEARML24344A2742024-12-19019 December 2024 Alternative Request to Use American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case OMN-32 ML24339B7292024-12-18018 December 2024 Amd - Constellation - Adoption of TSTF-591 ML24059A0632024-03-15015 March 2024 Authorization and Safety Evaluation for Alternative Request ISI-05-021 (EPID L-2023-LLR-0006) - Non-Proprietary ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23086C0672023-04-24024 April 2023 Issuance of Amendment Nos. 345 and 323 Deletion of License Conditions Related to Decommissioning Trust ML22195A0252023-01-0303 January 2023 Authorization and Safety Evaluation for Alternative Request No. ISI-05-016 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22202A5142022-07-28028 July 2022 Authorization of Relief Request No. RR-ISI-05-20 Regarding Mitigation of Buried Saltwater System Piping Degradation ML22105A4052022-05-0202 May 2022 Authorization and Safety Evaluation for Proposed Alternative No. ISI-05-019 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21347A8642022-01-13013 January 2022 Issuance of Amendment Nos. 342 and 320 Modifying the Licensing Basis to Allow for Full Core Offload with No Shutdown Cooling Loop Available During Certain Refueling Outages ML21299A0052021-12-14014 December 2021 Issuance of Amendments No. 340 and 318 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21190A0042021-09-0202 September 2021 Proposed Alternative to the Requirements of the ASME Section XI, Subsection Iwl Concerning Unbound Post-Tensioning Systems ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21039A6362021-02-17017 February 2021 R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20363A2422021-01-26026 January 2021 Issuance of Amendment Nos. 339 and 317 Regarding Accident Tolerant Fuel Lead Test Assemblies (EPID L-2019-LLA-0282) - (Non-Proprietary) ML20356A1212021-01-15015 January 2021 Relief from the Requirements of the ASME Code ML20273A0882020-11-0909 November 2020 Issuance of Amendment Nos. 338 and 316 Revise Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20275A1022020-11-0404 November 2020 Proposed Alternative I4r-07 to the Requirements of the American Society of Mechanical Engineers Code ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20010C4162020-08-20020 August 2020 Issuance of Amendments Nos. 214, 214, 218, 218, 337, and 315, Regarding Adoption of TSTF-569, Rev. 2, Revise Response Time Testing Definition ML20182A1942020-08-13013 August 2020 Issuance of Amendment Nos. 336 and 314 Concerning Reactor Coolant Pump Flywheel Inspection Program ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19337D0352020-02-28028 February 2020 Issuance of Amendment Nos. 333 and 311 Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML19330D9092020-02-28028 February 2020 Issuance of Amendment Nos. 332 and 310 Risk-Informed Categorization and Treatment of Systems, Structures, and Components ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19298C9722019-10-31031 October 2019 50.69 Apla SE Input L-2018-LLA-0482 ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19165A2472019-08-26026 August 2019 Issuance of Amendment Nos 330 and 308 Relocation and Consolidation the Emergency Operations Facility and Joint Information Center for the Calvert Cliffs Nuclear Power Plant ML19168A1172019-07-29029 July 2019 Issuance of Relief Request 15R-03 Use of ASME Code N-513-4 ML19196A1232019-07-19019 July 2019 Issuance of Relief Request 15R-04 Use of Encoded Phased Array Ultrasonic Examination Techniques ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19136A2162019-05-30030 May 2019 Use of a Provision in a Later Edition of the ASME Code ML19134A3732019-05-30030 May 2019 Issuance of Relief Request I5R-05 Relief from the Requirements of the ASME Code ML19053A5882019-04-19019 April 2019 Issuance of Amendment Nos. 329 and 307 Removal of an Exception to the Minimum Education Requirements for Shift Technical Advisors ML19046A0432019-02-25025 February 2019 Revision to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule 2024-03-15
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July 19, 2019 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 - ISSUANCE OF RELIEF REQUEST I5R-04 RE: USE OF ENCODED PHASED ARRAY ULTRASONIC EXAMINATION TECHNIQUES (EPID L-2018-LLR-0391)
Dear Mr. Hanson:
By letter dated December 19, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18354A431), as supplemented by letter dated April 15, 2019 (ADAMS Accession No. ML19106A003), Exelon Generation Company, LLC (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of alternatives to certain American Society of Mechanical Engineers Boiler & Pressure Vessel Code (ASME Code)Section XI requirements at Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs). The purpose of this letter is to provide the results of the NRC staffs review of the proposed alternative identified as Relief Request (RR) I5R-04, Revision 0. The NRC staff provided separate correspondence regarding the other two requests (i.e., RRs I5R-03 and I5R-05) in the licensees letter dated December 19, 2018.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative on the basis that the alternative would provide an acceptable level of quality and safety. In RR I5R-04, Revision 0, the licensee proposed to use encoded phased array ultrasonic examination techniques in lieu of the ASME Code-required radiography examinations for inservice inspection Class 1 and 2 ferritic piping repair or replacement welds.
As set forth in the enclosed safety evaluation, the NRC staff concludes that the licensees proposed alternative to use ultrasonic testing in lieu of radiographic testing using encoded phased array examinations provides reasonable assurance of structural integrity and leaktightness of Class 1 and 2 ferritic piping welds. Thus, ultrasonic testing of the subject welds using the procedure described in the licensees letters dated December 19, 2018, and April 15, 2019, would provide an adequate level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes RR I5R-04 for Calvert Cliffs for the remainder of the fifth 10-year inspection interval, which is scheduled to end on June 30, 2029.
All other requirements of the ASME Code for which relief has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
If you have any questions, please contact the Calvert Cliffs Project Manager, Michael L.
Marshall, Jr., at (301) 415-2871 or by e-mail to Michael.Marshall@nrc.gov.
Sincerely,
/RA/
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
Safety Evaluation cc: Listserv
Enclosure SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. I5R-04, REVISION 0 EXELON GENERATION COMPANY, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
By letter dated December 19, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18354A431), as supplemented by letter dated April 15, 2019 (ADAMS) Accession No. ML19106A003), Exelon Generation Company, LLC (the licensee) submitted an alternative to request relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code)Section XI, paragraph IWA-4221 for Calvert Cliffs Nuclear Plant, Units 1 and 2 (Calvert Cliffs). ASME Code Section XI, paragraph IWA-4221, requires the use of the ASME Code Section III, Subarticles NB-5200, NC-5200, and ND-5200, for repaired and replaced components, which in turn specify the use of radiographic examinations. The licensee is proposing to use phased array ultrasonic testing (UT) as an alternative to the required radiographic testing (RT).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative on the basis that the alternative would provide an acceptable level of quality and safety.
2.0 REGULATORY REQUIREMENTS The licensee has proposed an alternative, Relief Request (RR) I5R-04, Revsion 0, to the requirements of ASME Code Section XI, paragraph IWA-4221.Section XI, paragraph IWA-4200, covers repair and replacement activities, and paragraph IWA-4221 requires the use of Section III, paragraphs NB-5200, NC-5200, and ND-5200, which require the use of radiographic examinations on Class 2 piping butt welds.
Section 50.55a(z) of 10 CFR states, in part, that alternatives to the requirements of 10 CFR 50.55a(b)-(h) may be used when authorized by the U.S. Nuclear Regulatory Commission (NRC or the Commission) if (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
3.1 The Licensees Relief Request ASME Code Components Affected All ASME Code Section XI, inservice inspection (ISI) Class 1 and 2 ferritic piping butt welds requiring radiography during repair or replacement activities are affected.
ASME Code of Record The fifth 10-year interval of the Calvert Cliffs, Units 1 and 2, ISI program is based on the ASME Code Section XI, 2013 Edition.
ASME Code Requirement The ASME Code Section XI, IWA-4221, requires that items used for repair or replacement activities meet the applicable owners requirements and construction code requirements when performing repair/replacement activities. IWA-4520 requires that welded joints made for installation of items be examined in accordance with the construction code identified in the repair and replacement plan.
Section 50.55a(b)(2)(xx)(B) of 10 CFR states that:
The NDE [nondestructive examination] provision in IWA-4540(a)(2) of the 2002 Addenda of Section XI must be applied when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary using the 2003 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(l)(ii) of this section.
IWA-4540(a)(2) of the 2002 Addenda of the ASME Code Section XI requires that the NDE and acceptance criteria of the 1992 Edition or later of the ASME Code Section III be met prior to return to service in order to perform a system leakage test in lieu of a system hydrostatic test.
The examination requirements for the ASME Code Section III circumferential butt welds are contained in the ASME Code Section III, Subarticles NB-5200, NC-5200, and ND-5200. The acceptance standards for radiographic examination are specified in the ASME Code Section III, Subarticles NB-5300, NC-5300, and ND-5300.
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Reason for Request===
The licensee requested approval of this proposed alternative to support anticipated piping repair and replacement activities at Calvert Cliffs during the fifth ISI interval. Replacement of piping is periodically performed in support of the flow accelerated corrosion program, as well as other repair and replacement activities. The use of encoded phased array ultrasonic examination techniques (PAUT) in lieu of radiography (RT) to perform the required examinations of the replaced welds would eliminate the safety risk associated with performing RT, which includes the planned exposure and the potential for accidental personnel exposure. PAUT minimizes the
impact on other outage activities normally involved with performing RT such as limited access to work locations and the need to control system fill status because RT would require a line to remain empty of fluid to obtain adequate examination sensitivity and resolution. In addition, encoded PAUT has been demonstrated to be adequate for detecting and sizing critical flaws.
Proposed Alternative The licensee is proposing the use of encoded PAUT in lieu of the ASME Code-required RT examinations for ISI Class 1 and 2 ferritic piping repair and replacement welds at Calvert Cliffs.
Similar techniques are being used throughout the nuclear industry for examination of dissimilar metal welds and overlaid welds, as well as other applications, including ASME B31.1 piping replacements. This proposed alternative request includes requirements that provide an acceptable level of quality and safety that satisfy the requirements of 10 CFR 50.55a(z)(l). The examinations will be performed using personnel and procedures qualified with the requirements listed below.
The electronic data files for the PAUT examinations will be stored as part of the archival quality records. In addition, hard copy prints of the data will also be included as part of the PAUT examination records to allow viewing without the use of hardware or software.
Elements of the proposed alternative examination include:
The welds to be examined shall meet the surface conditioning requirements of the demonstrated ultrasonic procedure.
The welds to be examined shall be conditioned such that transducers properly couple with the scanning surface with no more than a 1/32 inch (0.8 millimeter) gap between the search unit and the scanning surface.
The ultrasonic examination shall be performed with equipment, procedures, and personnel qualified by performance demonstration.
The examination volume shall include 100 percent of the weld volume and the weld-to-base metal interface.
All detected fabrication flaw indications listed below shall be considered planar flaws and compared to the preservice acceptance standards for volumetric examination in accordance with IWB-3000, IWC-3000, or IWD-3000. Preservice acceptance standards shall be applied. Analytical evaluation for acceptance of flaws in accordance with IWB-3600, IWC-3600, or IWD-3600 is permitted for flaws that exceed the applicable acceptance standards and are confirmed by surface or volumetric examination to be non-surface connected.
o Angle beam examination of the complete examination volume for fabrication flaws oriented parallel to the weld joint shall be performed.
o Angle beam examination for fabrication flaws oriented transverse to the weld joint shall be performed to the extent practical. Scan restrictions that limit complete coverage shall be documented.
Flaws exceeding the applicable acceptance standards, and when analytical evaluation has not been performed for acceptance, shall be reduced to an acceptable size or removed and repaired, and the location of the repair shall be reexamined using the same ultrasonic examination procedure that detected the flaw.
The ultrasonic examination shall be performed using encoded UT technology that produces an electronic record of the ultrasonic responses indexed to the probe position, permitting off-line analysis of images built from the combined data.
A written ultrasonic examination procedure qualified by performance demonstration shall be used. The qualification shall be applicable to the scope of the procedure (e.g., flaw detection and/or sizing (length or through-wall height), encoded or non-encoded, single and/or dual side access, etc.).
Performance demonstration specimens shall conform to a list of requirements related to fabrication, geometry, flaw direction, size, and distribution.
Ultrasonic examination procedures shall be qualified by performance demonstration in accordance with the specific requirements.
Ultrasonic examination personnel shall be qualified in accordance with ASME Code Section XI, IWA-2300.
Documentation of the qualifications of procedures and personnel shall be maintained.
Documentation shall include identification of personnel, NDE procedures, equipment, and specimens used during qualification, and results of the performance demonstration.
The preservice examinations will be performed per ASME Section XI.
Basis for Use The licensee is proposing that encoded phased array UT is equivalent to or superior for detecting and sizing critical (planar) flaws, as compared to the required radiographic examination. In this regard, the basis for the proposed alternative was developed from numerous codes, code cases, associated industry experience, articles, and the results of RT and encoded PAUT examinations. It has been shown that PAUT provides an equally effective examination for identifying the presence of fabrication flaws in carbon steel welds compared to RT. The examination procedure and personnel performing examinations are qualified using representative piping conditions and flaws that demonstrate the ability to detect and size flaws that are both acceptable and unacceptable to the defined acceptance standards. The demonstrated ability of the examination procedure and personnel to appropriately detect and size flaws provides an acceptable level of quality and safety alternative as allowed by 10 CFR 50.55a(z)(1).
The requirements in the RR are based upon ASME Section XI, Code Case N-831 (N-831), and will apply to ISI ferritic piping butt welds requiring radiography during repair or replacement activities. N-831 was approved by the ASME Board on Nuclear Codes and Standards on October 20, 2016; however, it has not been incorporated into NRC Regulatory Guide 1.147, Inservice Inspection Code Case Applicability, ASME Section XI, Division 1.
Duration of Proposed Alternative The licensee requested relief for the fifth ISI interval. Additionally, the licensee asked for relief for the remainder of the plant life for Calvert Cliffs, Units 1 and 2 or until the NRC approves ASME Code Case N-831, or a later revision, in Regulatory Guide 1.147 or another document during the interval. The NRC staff evaluation is limited to the fifth ISI interval.
3.2 Staff Evaluation The licensee is proposing to update its use of encoded phased array UT in lieu of RT in RR I5R-04. UT, like RT, is a volumetric inspection technique that is commonly used to inspect welds in nuclear power plants and in other industries. Ultrasonic examinations are not equivalent to radiographic examinations, as they use different physical mechanisms to detect and characterize discontinuities. These differences in physical mechanisms result in several key differences in sensitivity and discrimination capability.
Code Case N-831 discusses ultrasonic examination in lieu of radiography for welds in ferritic piping; however, it has yet to be approved by the NRC and incorporated into the latest revision of Regulatory Guide 1.147. An assessment of the use of UT in lieu of RT by the NRC has been described in NUREG/CR-7204, Applying Ultrasonic Testing In Lieu of Radiography for Volumetric Examination of Carbon Steel Piping (ADAMS Accession No. ML15253A674),
concluding that UT has the potential to replace RT for ferritic welds if done to a sufficient level of rigor. This report included evaluation on the use of UT in lieu of RT for welded pipes and plates with thicknesses ranging from 0.844 inches to 2.2 inches.
One conclusion from NUREG/CR-7204 is:
Considering overall detections/non-detections for the piping specimens, as well as the Navy plates, it appears that PA-UT, based on the techniques applied in this study, provides an equally effective examination for identifying the presence of fabrication flaws in carbon steel welds. The PA-UT parameters applied were shown to be more effective for planar flaws, but slightly less effective for small volumetric flaws, than RT.
Based on this research, the NRC staff finds that there is a sufficient technical basis for the use of UT in lieu of RT for ferritic steel welds. Given that UT in lieu of RT is possible, the NRC staff worked to determine if the proposed alternatives apply UT in a way that provides reasonable assurance of finding structurally-significant flaws.
Some of the primary aspects of this proposed alternative include:
The examination volume shall include 100 percent of the weld volume and the weld to-base metal interface.
The electronic data files for the PAUT examinations will be stored as archival-quality records. In addition, hard copy prints of the data will also be included as part of the PAUT examination records to allow viewing without the use of hardware or software.
Ultrasonic procedures shall be qualified by using either a blind or a non-blind performance demonstration using a minimum of 30 flaws covering a range of sizes, positions,
orientations, and types of fabrication flaws. The demonstration set shall include specimens to represent the minimum and maximum diameter and thickness covered by the procedure.
The flaw through-wall heights shall be based on the applicable acceptance standards for volumetric examination in accordance with the ASME Code Section XI, IWB-3400, IWC-3400, or IWD-3400. At least 30 percent of the flaws shall be classified as acceptable planar flaws, with the smallest flaws being at least 50 percent of the maximum allowable size based on the applicable all aspect ratio for the flaw.
Ultrasonic examination personnel shall demonstrate their capability to detect and size flaws by performance demonstration using the qualified procedure. The demonstration specimen set shall contain at least 10 flaws covering a range of sizes, positions, orientations, and types of fabrication flaws, particularly those covered in Section 9(h) of the licensees submittal dated December 19, 2018.
The remaining aspects of the proposal are listed in Section 5.1, Proposed Alternative, of the licensees submittal dated December 19, 2018.
All flaws detected using angle-beam ultrasonic inspections will be treated as planar, and the flaws will be evaluated against the preservice acceptance standards of the ASME Code Section XI, IWB-3400, IWC-3400, or IWD-3400 for ASME Code Class 1, 2, or 3 welds, respectively, which are based on calculations to determine if the component is acceptable for service, not workmanship standards. The use of the ASME Code Section XI, IWB-3400, IWC-3400, and IWD-3400, has proven effective for piping welds for ISI. The NRC staff finds that the use of these acceptance standards is appropriate for the proposed alternatives, considering they are for repair and replacement activities. Based on the results of NUEG/CR-7204 and the work evaluated in the review of RR I5R-04, there is reasonable assurance that the encoded phased array UT qualified as proposed by the licensee will provide an adequate level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff concludes that the licensees proposed alternative to use UT in lieu of RT using encoded phased array examinations provides reasonable assurance of structural integrity and leaktightness of Class 1 and 2 ferritic piping welds. Thus, UT using the procedure described in the submittals of the subject welds would provide an adequate level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1). Therefore, the NRC staff authorizes RR I5R-04 for Calvert Cliffs, Units 1 and 2 for, the remainder of the fifth 10-year ISI that is scheduled to end on June 30, 2029.
All other requirements of the ASME Code for which relief has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributors: Austin Young Date: July 19, 2019
ML19196A123
- by e-mail OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DMLR/MPHB/BC*
NAME MMarshall LRonewicz ABuford DATE 07/16/2019 07/16/2019 07/02/2019 OFFICE NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME JDanna MMarshall DATE 07/19/2019 07/19/2019