Letter Sequence Other |
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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:Code Relief or Alternative
MONTHYEARML23156A6752023-06-20020 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 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 NOC-AE-06002031, Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations2006-06-14014 June 2006 Request for Relief from ASME Boiler and Pressure Vessel Code, Section XI Requirements for Use of Penetrameters in Radiographic Examinations ML0611102322006-05-11011 May 2006 Relief Request, Use Alternative Techniques for Repair of Welded Nozzles ML0602400852006-02-0808 February 2006 Relief Request for Underwater Welding of Heated Junction Thermocouple Holders, Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (TAC Nos. MC8572 and MC8573) 2023-06-20
[Table view] Category:Letter
MONTHYEARIR 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)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 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 IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications 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 ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations 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 ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection 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 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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 2024-02-01
[Table view] Category:Safety Evaluation
MONTHYEARML23304A0642024-01-0202 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 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 ML19330D9092020-02-28028 February 2020 Issuance of Amendment Nos. 332 and 310 Risk-Informed Categorization and Treatment of Systems, Structures, and Components 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 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 ML19134A3732019-05-30030 May 2019 Issuance of Relief Request I5R-05 Relief from the Requirements of the ASME Code ML19136A2162019-05-30030 May 2019 Use of a Provision in a Later Edition of the ASME Code ML19053A5882019-04-19019 April 2019 Plants, Units 1 and 2 - 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 Plants, Units 1 and 2 - Revision to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule ML18365A3732019-01-22022 January 2019 Issuance of Amendment Nos. 328 and 306 to Extend Completion Time of Required Action D.3 of Technical Specification 3.8.1 to 14 Days ML18318A0142018-11-30030 November 2018 Correction to Amendment Nos. 326 and 304 Add Risk-Informed Completion Time Program ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18270A1302018-10-30030 October 2018 Issuance of Amendment Nos. 326 and 304 to Add Risk-Informed Completion Time Program 2024-01-02
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 December 19, 2016
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2-RELIEF REQUEST FOR DISSIMILAR METAL BUTT WELD EXAMINATIONS (CAC NO. MF7291)
Dear Mr. Hanson:
By letter dated January 28, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16028A 156), as supplemented by letter dated September 1, 2016 (Reference 2) (ADAMS Accession No. ML 16246A202), Exelon Generation Company, LLC, the licensee, submitted a request to the U.S. Nuclear Regulatory Commision (NRC) for authorization of a proposed alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-770-1, as conditioned by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(F) for Calvert Cliffs Nuclear Power Plant, Unit No. 2 (CCNPP2). Specifically, the licensee proposed alternative ultrasonic (UT) examination coverage requirements to those of 10 CFR 50.55a(g)(6)(ii)(F) for 16 dissimilar metal butt welds (DMBWs) at CCNPP2. The licensee proposed examination techniques and procedures to be used during the 2017 outage for the identified welds to be similar to those previously used in 2011. Pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use an alternative on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. As set forth in the enclosed Safety Evaluation, the NRC staff has concluded that the proposed alternative in Relief Request RR-ISl-04-11 provides reasonable assurance of structural integrity and leak tightness of the subject dissimilar metal butt welds and that complying with the specified requirement would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the regulatory requirements of 10 CFR 50.55a(z)(2) have been fulfilled and authorizes use of RR-ISl-04-11 at CCNPP2 for the remainder of the fourth 10-year inservice inspection interval. All other ASME Code,Section XI requirements for which relief was not specifically requested and authorized in the subject proposed alternative remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
B. Hanson If you have any questions, please contact the project manager, Richard Guzman, at 301-415-1030 or Richard.Guzman@nrc.gov. Docket Nos. 50-318
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv Sincerely, Stephen S. Koenick, Acting Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST RR-ISl-04-11 REGARDING DISSIMILAR METAL BUTT WELD EXAMINATIONS CALVERT CLIFFS NUCLEAR POWER PLANT. LLC EXELON GENERATION COMPANY. LLC CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 DOCKET NO. 50-318
1.0 INTRODUCTION
By letter dated January 28, 2016 (Reference 1 ), as supplemented by letter dated September 1, 2016 (Reference 2), Exelon Generation Company, LLC, the licensee, submitted a request for authorization of a proposed alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-770-1(Reference 3), as conditioned by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(F) for Calvert Cliffs Nuclear Power Plant, Unit No. 2 (CCNPP2). Specifically, the licensee proposed alternative ultrasonic (UT) examination coverage requirements to those of 10 CFR 50.55a(g)(6)(ii)(F) for 16 dissimilar metal butt welds (DMBWs) at CCNPP2. Pursuant to 10 CFR 50.55a(z)(2), the licensee requested to use an alternative for the identified welds listed in Table 1A of its submittal on the basis that the required examination coverage of "essentially 100 percent" or "100 percent of the susceptible material volume" for cast austenitic stainless steel (CASS) items is unattainable due to physical obstructions and the limitiation imposed by design, geometry, and/or materials of construction.
2.0 REGULATORY EVALUATION
Paragraph 55a(g)(6)(ii)(F) of 1 O CFR 50 requires that licensees of existing operating pressurized water reactors (PWRs) implement the requirements of ASME Code Case N 770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities" (N-770-1 ), subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (g)(6)(ii)(F)(10), by the first refueling outage after August 22, 2011. Paragraph 55a(g)(6)(ii)(F)(4) of 10 CFR 50 states, "The axial examination coverage requirements of Paragraph -2500(c) may not be considered to be satisfied unless essentially 100 percent coverage is achieved." Enclosure Paragraph 10 CFR 50.55a(z) states, in part, that alternatives to the requirements of 1 O CFR 50.55a(g) may be used when authorized by the NRG if the applicant demonstrates that: (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 analysis of the regulatory requirements, the NRG staff concludes that regulatory authority exists to authorize the proposed alternative RR-ISl-04-11 pursuant to 1 O CFR 50.55a(z)(2).
3.0 TECHNICAL EVALUATION
3.1 Components Affected ASME Code Class 1 PWR Pressure Retaining dissimilar metal piping welds containing Alloy 82/182, ASME Code Case N-770-1 Inspection Items as shown below:
- Inspection Item 8, Unmitigated butt weld at cold leg operating temperature: Weld ID NPS 109280 I 30-RC-21 A-7 30" 109310 I 30-RC-21A-10 30" 110280 I 30-RC-218-7 30" 11031OI30-RC-218-10 30" 111280 I 30-RC-22A-7 30" 111310/ 30-RC-22A-10 30" 112280 I 30-RC-228-7 30" 112310 I 30-RC-228-10 30" 115140I12-Sl-2009-15 12" 116190I12-Sl-2010-13 12" 117120I12-Sl-2011-13 12" 118120/ 12-Sl-2012-13 12"
- Inspection Item D, Uncracked butt weld mitigated with stress improvement: Weld ID NPS 113010/12-PSL-1 12" 113130/12-PSL-13 12" 114900 I 12-SC-2004-1 12" 136090 I 4-PS-2003-8 4" 3.2 Code Requirements
- The CCNPP2 code of record for the fourth 10-year inservice inspection interval that started on October 10, 2009 and is scheduled to end on June 30, 2019 is the 2004 Edition, no Addenda, of the ASME Code,Section XI.
- N-770-1, Paragraph -2420 says successive examinations are specified in Table 1. Table 1, Inspection Item B, requires examination every second inspection period not to exceed 7 years. Inspection Items D and E also require successive examinations based on defined criteria.
- N-770-1, Paragraph -2500(c) says in part if 100 percent coverage of the required volume for axial and circumferential flaws cannot be met, but essentially 100 percent coverage for circumferential flaws (100 percent of the susceptible material volume) can be achieved, the examination for axial flaws shall be completed to achieve the maximum coverage practical.
- 10 CFR 55a(g)(6)(ii)(F)(4) says the axial examination coverage requirements of Paragraph -2500(c) may not be considered to be satisfied unless essentially 100 percent coverage is achieved. 3.3 Licensee's Proposed Alternative The licensee is proposing to use the previously obtained ultrasonic examination coverage (as shown in the January 28, 2016 submittal) of the DM butt welds identified above to satisfy the examination requirements of N-770-1 and 10 CFR 55a(g)(6)(ii)(F)(4). 3.4 Licensee's Basis for Requesting Relief The licensee proposes to use coverage achieved during the N-770-1 baseline exams for the components listed above as an alternative to the N-770-1 and 10 CFR 55a(g)(6)(ii)(F)(4) required examination coverage of "essentially 100 percent" or "100 percent of the susceptible material volume" because this coverage is unattainable without enduring significant hardship. These welds have been examined in the past (i.e. 2011) using examination techniques qualified to meet the requirements of ASME Section XI, Appendix VIII as required in 1 O CFR 50.55a(g)(6) and achieved the maximum practical amount of examination coverage obtainable within the limitations imposed by the design, geometry and materials of construction for the components. The examination coverage achieved for these components during the 2011 exams was shown in Table 1A of the January 28, 2016 submittal. The 12 unmitigated welds are found in lower temperature regions of the reactor coolant system (at temperatures near Tcold). Therefore, there is a lower probability of crack initiation and a slower crack growth rate. These welds are also highly flaw tolerant, as demonstrated in MRP-109. As shown in MRP-109, it can be demonstrated that piping with substantial size flaws can continue to demonstrate structural integrity for a prolonged period of operation without repair. The additional 4 welds have been mitigated by stress improvement. Where appropriate, contouring has already been completed on the examination surface. Further actions are limited by the design minimum wall calculations for the piping. Additional axial flaw coverage would require a weld build-up of the OM weld followed by additional contouring and a Construction Code required radiography examination. The licensee proposes that these additional steps to improve axial coverage constitute a hardship that does not result in an increase to health and safety of the public. Additionally, bare metal visual examinations in accordance with ASME Code Case N-722-1 (Reference 4) and N-770-1 will continue to be performed. During refueling outages qualified examiners perform walkdowns of the Class 1 components at both pressurized and cold shutdown conditions. These walkdowns satisfy the ASME Section XI pressure testing and the station Boric Acid Corrosion Control Program requirements. Therefore, the licensee proposes that the UT examination coverages, which include a large percentage of the susceptible material for the circumferential and axial flaws, combined with the periodic system pressure tests and outage walk downs, provide an acceptable level of quality and safety for identifying degradation from primary water stress corrosion cracking (PWSCC) prior to the development of a safety significant flaw. 3.5 NRC Staff Evaluation Operational experience has shown that PWSCC can occur as the result of the combination of susceptible material, corrosive environment, and tensile stresses, resulting in leakage and the potential for loss of structural integrity. The subject DMBWs meet these conditions, and therefore, may be susceptible to PWSCC. The examination requirements of N-770-1, as conditioned by 1 O CFR 50.55a(g)(6)(ii)(F), are intended to ensure the structural integrity and leak tightness, thus an acceptable level of quality and safety, of DMBWs through nondestructive examination. The staff notes that the generic rules for the frequency of volumetric examination of dissimilar metal butt welds were established to provide reasonable assurance of the structural integrity of the reactor coolant pressure boundary. As such, the staff finds that plant specific analysis could be used to provide a basis for inspection relief if the inspection requirement presents a significant hardship. As such, the staff reviewed the licensee's proposed alternative under the requirements of 1 O CFR 50.55a(z)(2), such that; Compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Full coverage of the welds is unattainable due to the presence of CASS material, physical obstructions and the limitations imposed by design, geometry, and/or materials of construction. The staff is not aware of other options for attaining the required examination coverage and, therefore, finds that attaining the required ASME Code Case N-770-1 examination coverage would present a hardship. The licensee stated that CCNPP2 has examined these welds in the past (2011 ). The UT examination performed in spring 2011 was a manually-delivered, phased-array, single-sided UT examination performed in both the circumferential and axial directions from the outside diameter. The personnel and UT procedure, Sl-UT-130, "Procedure for the Phased Array Ultrasonic Examination of Dissimilar Metal Welds" were qualified to the requirements of ASME Code Section XI Appendix VIII, Supplement 10, for detection and characterization of PWSCC.
The Sl-UT-130 procedure is also qualified to scan DMBWs with single-sided access. This qualification allows for interrogation of DMBWs that have CASS safe ends or restricted scanning conditions from the opposite side. These previous UT examinations could not obtain essentially 100 percent coverage of the required examination volume due to weld taper, insulation support obstruction, and the presence of the CASS safe-ends. In the January 28, 2016 submittal the licensee stated that Exelon Nondestructive Examination procedures have adopted the industry NOE Improvement Focus Group (NIFG) guidance for examination of DMBWs based on operating experience with these examinations. These procedures will be in effect during the CCNPP2 DMBW examinations. In the September 1, 2016 response to NRG request for additional information the licensee confirmed that they would use current qualified techniques and the NIFG requirements determined to be "needed" according to the Nuclear Energy Institute Guideline for the Management of Materials Issues. As identified in MRP-109 (Reference 5) and WCAP-17128-NP (Reference 6), the axial flaw(s) that could result from a PWSCC mechanism in the susceptible alloy 82/182 butt weld are not structurally significant. The axial critical flaw length for an RCP inlet and outlet alloy 82/182 butt weld is 38.2" (MRP-109 Table 5-2) which exceeds the width of the CCNPP2 RCP inlet and outlet alloy 82/182 butt weld material width of 1.75"-2.5". Therefore a critical axial flaw in an RCP inlet or outlet alloy 82/182 butt resulting from a PWSCC mechanism is not credible and improving the exam axial flaw examination volume coverage would not result in an increase in safety. All of the welds identified in this request received essentially 100 percent examination coverage for circumferential flaws in the susceptible material which alleviates any structural integrity concerns, because an axial PWSCC flaw will be arrested in the adjacent non-susceptible material. Flaw tolerance was further documented in Reference 7, which summarized a flaw tolerance evaluation which is bounding for all the Reactor Coolant Pump (RCP) inlet and outlet Dissimilar Metal Welds (DMWs). In addition, all DMWs operating at hot leg temperature or greater have been mitigated with stress improvement. The initiation or growth of a safety significant flaw in a cold leg or mitigated alloy 82/182 DM butt weld is extremely unlikely. However, as an added measure of safety, the industry has developed guidelines, to improve their RCS leak detection capability in part due to the concern with PWSCC. In the January 28, 2016 submittal the licensee indicated the CCNPP2 procedures for reactor coolant inventory analysis use the recommendations and guidance of WCAP-16423-NP (Reference 8) and WCAP-16465-NP (Reference 9) as described in a previous response to NRC's request for additional information associated with CCNPP Unit 1 dated November 24, 2015 (ADAMS Accession No. ML 15328A513). The enhanced leak rate monitoring and detection procedure monitors specific values of unidentified leakage, seven day rolling average, and baseline means. Action levels are initiated as low as when the unidentified leak rate exceeds 0.1 gpm. The enhanced leak detection capability provides an increased level of safety that if a flaw were to grow through wall, although unlikely, that it would be detected prior to growing to a safety significant size. The licensee states that contouring has already been completed on the examination surface and further actions are limited by the design minimum wall calculations for the piping; obtaining additional circumferential scan coverage would require a weld build-up of the DMBW, followed by contouring and an ASME Code, Section Ill, required radiographic examination. The NRG staff has examined the drawings submitted by the licensee and finds that fulfilling the essentially 100 percent examination coverage requirement is not possible using currently available UT technology and procedures. The NRC staff finds that the lack of ASME Code Section XI, Appendix VIII-compliant examination of the CASS and carbon steel materials is not a structural integrity concern since they are not known to be susceptible to PWSCC or other service-related cracking in the reactor coolant system environment; thus, the NRC staff accepts the UT examination achieved for these materials. The NRC staff further finds that the efforts needed to obtain essentially 100 percent scan coverage of the susceptible material would present a hardship. Additionally in the January 28, 2016 submittal, the licensee confirmed that they would continue to evaluate new technologies that offer improvements in nondestructive examination performance and examination coverage. Therefore, examination coverage meeting that which was achieved previously and described in the January 28, 2016 submittal, which includes essentially 100 percent of the susceptible material for the safety significant circumferential flaw and a significant percentage of the susceptible material for the less safety significant axial flaw combined with the periodic system pressure tests, outage walkdowns and leakage monitoring, provides an acceptable level of quality and safety for identifying degradation from PWSCC prior to a safety significant flaw developing. In summary, the NRC staff finds that performing the actions needed to achieve the UT examination coverage required by 1 O CFR 50.55a(g)(6)(ii)(F)(4) would constitute a hardship. The NRC staff also finds that there is reasonable assurance of structural integrity and leak tightness of the subject welds.
4.0 CONCLUSION
As set forth above, the NRC staff has concluded that proposed alternative RR ISl-04-11, provides reasonable assurance of structural integrity and leak tightness of the subject dissimilar metal butt welds and that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the regulatory requirements of 1 O CFR 50.55a(z)(2) have been fulfilled and authorizes use of RR ISl-04-11 at CCNPP2, for the remainder of the fourth 10-year inservice inspection interval. All other ASME Code,Section XI requirements for which relief was not specifically requested and authorized in the subject proposed alternative remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
5.0 REFERENCES 1. Letter from David T. Gudger, Exelon Generation Company, LLC to NRC, "Relief Request for Dissimilar Metal Butt Weld Examinations," January 28, 2016 (ADAMS Accession No. ML 16028A156). 2. Letter from David T. Gudger, Exelon Generation Company, LLC to NRC, "Relief Request for Dissimilar Metal Butt Weld Examinations," September 1, 2016 (ADAMS Accession No. ML 16246A202). 3. ASME Code Case N-770-1, Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without of Application of Listed Mitigation Activities, December 25, 2009. 4. ASME Code Case N-722-1, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 MaterialsSection XI, Division 1, January 26, 2009. 5. EPRI, Materials Reliability Program Technical Report MRP-109, Rev. 1, Final Report, July 2004, "Materials Reliability Program: Alloy 82/182 Pipe Butt Weld Safety Assessment for US PWR Plant Designs: Westinghouse and CE Design Plants," (ADAMS Accession No. ML042430004). 6. Westinghouse Topical Report WCAP-17128-NP, Rev. 1, May 2010, "Flaw Evaluation of CE Design RCP Suction and Discharge Nozzle Dissimilar Metal Welds, Phase Ill Study," (ADAMS Accession No. ML 12306A291 ). 7. Letter from J. Stanley (CENG) to U.S. Nuclear Regulatory Commission, "Response to Request for Additional Information -Relief Request RR-ISl-04-07 A, Dissimilar Metal Butt Welds Baseline Examinations," dated February 18, 2013 (ADAMS Accession No. ML 13051A740). 8. Westinghouse Topical Report WCAP-16423-NP, Rev. 0, September 2006, "Pressurized Water Reactor Owners Group Standard Process and Methods for Calculating RCS Leak Rate for Pressurized Water Reactors," (ADAMS Accession No. ML070310084). 9. Westinghouse Topical Report WCAP-16465-NP, Rev. 1, September 2006, "Pressurized Water Reactor Owners Group Standard RCS Leakage Action Levels and Response Guidelines for Pressurized Water Reactors," (ADAMS Accession No. ML070310082). Principal Contributor: Keith Hoffman Date: December 19, 2016 B. Hanson If you have any questions, please contact the project manager, Richard Guzman, at 301-415-1030 or Richard.Guzman@nrc.gov. Docket Nos. 50-318
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv DISTRIBUTION: PUBLIC LPL1-1R/F RidsNrrDeEpnb Resource RidsACRS_MailCTR Resource RidsNrrLAKGoldstein Resource ADAMS Accession No.: ML 16337A190 Sincerely, IRA/ Stephen S. Koenick, Acting Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorlLpl1-1 Resource RidsNrrPMCalvertCliffs Resource RidsNrrDorlDpr Resource RidsRgn1 MailCenter Resource KHoffman, NRR *SE and concurrence transmitted via e-mail OFFICE DORL/LPL 1-1 /PM DORL/LPL 1-1/LA DE/EPNB/BC* DORL/LPL 1-1/BC(A) NAME RGuzman KGoldstein DAiiey* SKoenick DATE 12/2/16 12/05/16 11/28/16 12/19/16 OFFICIAL RECORD COPY