Letter Sequence Other |
---|
|
|
MONTHYEARML14034A1732014-01-29029 January 2014 Revised Proposed Alternative for Mitigation of Buried Saltwater Piping Degradation (RR-ISI-04-08, Revision 1) Project stage: Request ML14041A4272014-02-11011 February 2014 Request for Additional Information Regarding Relief Request RR-ISI-04-08, Revision 1, Mitigation of Buried Saltwater System Piping Degradation Project stage: RAI ML14050A1272014-02-14014 February 2014 Response to Request for Additional Information Proposed Alternative RR-ISI-04-08, Revision I Project stage: Response to RAI ML14055A2132014-02-25025 February 2014 Summary of Telephone Conference Regarding the Verbal Authorization of Relief Request RR-ISI-04-08, Revision 1 Project stage: Other 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) Project stage: Other 2014-02-11
[Table View] |
|
---|
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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 19, 2014 Mr. George H. Gellrich, Vice President Calvert Cliffs Nuclear Power Plant, LLC Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2- RELIEF REQUEST RR-ISI-04-08, REVISION 1, REGARDING MITIGATION OF BURIED SALTWATER PIPING DEGRADATION (TAC NOS. MF3413AND MF3414)
Dear Mr. Gellrich:
By letter dated January 29, 2014, as supplemented by letter dated February 14, 2014, Calvert Cliffs Nuclear Power Plant, LLC (the licensee), submitted to the Nuclear Regulatory Commission (NRC) relief request RR-ISI-04-08, Revision 1, for authorization of a proposed alternative to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Article IWA-4000, for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs).
Specifically, the licensee proposed to use a mechanical sleeve assembly to repair inside surface degradation of mortar lined ductile iron piping in the saltwater system for the remainder of the Calvert Cliffs fourth 10-year inservice inspection (lSI) interval. Pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.55a(a)(3)(ii), the licensee requested to use the proposed alternative on the basis that complying with the specified ASME Code requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The NRC staff has determined that the licensee's proposed alternative provided reasonable assurance of structural integrity or leak tightness of the subject component, 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 has concluded that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii). Therefore, the NRC staff authorizes the use of the licensee's proposed alternative in relief request RR-ISI-04-08, Revision 1, for the remainder of the fourth 10-year lSI interval, which ends on June 30, 2019, for Calvert Cliffs.
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including the third party review by the Authorized Nuclear lnservice Inspector.
G. Gellrich On February 25, 2014, the NRC staff granted verbal authorization of the licensee's proposed alternative in relief request RR-ISI-04-08, Revision 1. The enclosed safety evaluation documents the NRC staff's review and technical basis for this authorization.
If you have any questions, please contact the Calvert Cliffs Project Manager, Nadiyah Morgan, at (301) 415-1016, or by e-mail at Nadiyah.Morgan@nrc.gov.
Sincerely, Benjamin G. Beasley, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST RR-ISI-04-08, REVISION 1, REGARDING MITIGATION OF BURIED SALTWATER PIPING DEGRADATION CALVERT CLIFFS NUCLEAR POWER PLANT, LLC EXELON GENERATION COMPANY, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
By letter dated January 29, 2014 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML14034A173), as supplemented by letter dated February 14, 2014 (ADAMS Accession No. ML14050A127), Calvert Cliffs Nuclear Power Plant, LLC (the licensee),
submitted relief request RR-ISI-04-08, Revision 1, for authorization of a proposed alternative to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Article IWA-4000, for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs).
Specifically, the licensee proposed to use a mechanical sleeve assembly to repair inside surface degradation of mortar lined ductile iron piping in the saltwater system for the remainder of the Calvert Cliffs' fourth 10-year inservice inspection (lSI) interval. Pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.55a(a)(3)(ii), the licensee requested to use the proposed alternative on the basis that complying with the specified ASME Code requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
On February 25, 2014 (ADAMS Accession No. ML14055A213), the U.S .. Nuclear Regulatory Commission (NRC) staff granted verbal authorization of the licensee's proposed alternative in relief request RR-ISI-04-08, Revision 1. This safety evaluation documents the NRC staff's review and technical basis for this authorization.
2.0 BACKGROUND
By letter dated January 17, 2013 (ADAMS Accession No. ML13022A048), as supplemented by letter dated May 17, 2013 (ADAMS Accession No. ML13141A270), the licensee submitted relief request RR-ISI-04-08 for authorization of a proposed alternative to use metal reinforced polymeric Enclosure
patches to address inside diameter degradation of mortar lined ductile iron piping in the saltwater system. By letter dated November 13, 2013 (ADAMS Accession No. ML13297A293), the NRC staff authorized the proposed alternative. Subsequently, the licensee submitted relief request RR-ISI-04-08, Revision 1, to correct the design temperature of the saltwater system used in the stress calculation and to add a specific statement that mentions that the installation of the mechanical sleeve assembly is applicable to joints within the buried saltwater system piping.
3.0 REGULATORY EVALUATION
In relief request RR-ISI-04-08, Revision 1, the licensee requests authorization of an alternative to the requirements of the ASME Code,Section XI, Article IWA-4000 pursuant to 10 CFR 55a(a)(3)(ii).
Adherence to Article IWA-4000 of Section XI of the ASME Code is mandated by 10 CFR 50.55a(g)(4), which states, in part, that ASME Code Class 1, 2, and 3 components (including supports) will meet the requirements, except the design and access provisions and the preservice examination requirements set forth in the ASME Code,Section XI.
The regulations at 10 CFR 50.55a(a)(3) state, in part, that alternatives to the requirements of paragraph (g) of 10 CFR 50.55a may be used, when authorized by the NRC, if the licensee demonstrates that: (i) the proposed alternative provides an acceptable level of quality and safety, or (ii) 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 the use of an alternative and the NRC to authorize the proposed alternative.
4.0 TECHNICAL EVALUATION
4.1 RR-ISI-04-08. Revision 1 For the most part, relief request RR-ISI-04-08, Revision 1, is consistent with the relief request RR-ISI-04-08, except for the following significant changes with corresponding sections and page numbers.
Change #1: Section 5, Page 2, the licensee added the following new requirement:
The supporting calculation ... states any repairs are made in straight lengths of pipe. This includes the bell and spigot joints that are part of straight lengths of pipe within the Saltwater System. The proposed repair alternative is not designed to be used in pipe elbows or across mitered joints.
Using the proposed alternative to repair bell and spigot joints, the licensee stated in its February 14, 2014 letter:
The pipe joint consists of a bell and spigot configuration with fittings that connect to compress the joint gasket. Bolting between the gland and the bell provides a leak tight joint and also develops a friction fit to inhibit differential axial or rotational pipe movement.
The licensee also stated in part that:
In an unrepaired joint, a small gap in the concrete pipe lining exists across the bell and spigot joint to allow for limited movement between the pipe segments.
Absence of such a gap would result in cracking of the concrete liner. For the same reason, in a repaired joint, a similar gap will be left between pipe segments when the sealant is applied.
Relative motion across the bell and spigot joint due to temperature variations, moisture variations or seismic activity is expected to be very small. This expected lack of relative motion is due to, in part, the fact that the subject pipe is located under the North Service Building and Turbine Building. The location of the subject piping relative to these structures is expected to substantially restrict relative motion of piping segments by constraining the fill in which the subject pipe is located. Additionally, there are concrete thrust barriers installed at each elbow where a straight pipe changes directions. These concrete thrust barriers further prevent any relative movement of the pipe in the axial direction.
Water is prevented from reaching the joint by the Ethylene Propylene Diene Monomer (EPDM gasket). This gasket is flexible so it can accommodate the small amount of relative motion expected between pipe segments. The EPDM gasket is held in place firmly by retaining bands located at each end; minor relative motion between the pipe segments will not affect the retaining bands and, therefore, will not cause the gasket to leak. Therefore, corrosion of the backing plate and other joint components is not expected. Likewise, due to the flexibility of the gasket and the manner in which it is retained against the pipe, relative motion across the pipe joint is not expected to dislodge or tear the gasket so that it could potentially foul downstream components.
Change #2: Section 5, Page 2, the licensee added the following new requirement:
The buried saltwater piping has a design pressure of 50 psig [pounds per square inch gauge]. The Saltwater System temperature varies in accordance with Chesapeake Bay temperature throughout the year and load demands on the system. The Saltwater System is exposed to temperatures from 30 oF [degrees Fahrenheit] up to its design temperature of 200 °F.
The licensee revised the stress calculation by using a design temperature of 200 oF.
Change #3: Section 7, Page 4, the licensee revised the text of RR-ISI-04-08:
From:
Prior to installation of the sleeve, the cement coating of the degraded area and its surrounding area will be removed and repaired with an approved sealant.
To:
Prior to installation of the sleeve, the cement lining for the entire length of the sleeve assembly will be removed and repaired with an approved sealant.
Regarding the installation of sealant, in its February 14, 2014 letter, the licensee stated in part that:
- 1. The sealant that will be used is a paste grade. It is used for filling degraded ductile and cast iron pipe back to its original contours. It provides erosion and corrosion resistance to the metal surfaces. The sealant will be applied to provide a smooth, continuous surface, which will allow good contact with other components of the repair.
- 2. The sealant and coating materials have been used in many applications in the saltwater system since 1992.
- 3. The sealant and coating material were qualified for the saltwater system design conditions and in accordance with the American Society for Testing and Materials tests performed by the manufacturer (per the material's specification sheets).
- 4. The sealant and coating were not qualified for a specific service life.
However, they have been used for over 20 years in the licensee's saltwater system piping. Inspections of the materials have revealed no significant degradation.
Change #4: Section 7, Page 6, the licensee revised the text of RR-ISI-04-08:
From:
This proposed repair system will not be used in cases of discovered cracking or on corrosion that initiated on the external diameter of the saltwater piping.
To:
This proposed repair system will not be used in cases of discovered crack like flaws, through wall degradation, or on corrosion that initiated on the external diameter of the saltwater piping.
The licensee noted that by making a limitation which precludes the use of the alternative for instances in which through-wall leakage is occurring, corrosion of the repair due to water ingress from outside the pipe need not be considered.
Change #5: Section 7, page 8, the licensee revised the text of RR-ISI-0-08:
From:
- A check of the retaining bands and backing ring for corrosion
- A check of the liner under the sleeve for wetness
- A check for any damage of the liner To:
- A check of the retaining bands and backing ring for corrosion
- A check of the area under the sleeve for wetness
- A check for any damage of the liner
- A check for damage of the EPDM gasket The licensee added additional steps in the examination after the sleeve is installed.
Change #6: Section 7, Page 8, the licensee revised the text of RR-ISI-04-08:
From:
Defects where the repair system is utilized will be characterized and projections on growth will be provided to ensure that the defect will be contained within the specified limits of the repair system.
To:
Defects where the repair system is utilized will be characterized to ensure that the defect will be contained within the specified limits of the repair system.
The licensee deleted the crack growth projections.
Change #7: The licensee added the following commitments in RR-ISI-04-08, Revision 1:
After Unit 1 RFO [refueling outage], establish a work order to inspect one installed Saltwater System sleeve assembly approved in RR-ISI-04-08, Revision 1, after two operating cycles. If no sleeve assembly installed during RFO, no action required. Create a new action item for subsequent Unit 1 RFO if Saltwater System piping inspection to be conducted. Date -
May 1, 2014.
After Unit 2 RFO, establish a work order to inspect one installed Saltwater System sleeve assembly approved in RR-ISI-04-08, Revision 1, after two operating cycles. If no sleeve assembly installed during RFO, no action required.
Create a new action item for subsequent Unit 2 RFO if Saltwater System piping inspection to be conducted. Date - May 1, 2015.
The licensee indicated that any additional repair system installed will be visually inspected every other refueling outage. The licensee noted that because the proposed alternative will only be implemented when applicable degraded conditions are identified during future inspections, the intent of the two commitments was to ensure that the disassembly of the first installed sleeve assembly is tracked regardless of whether it was installed on Unit 1 or Unit 2. The licensee explained that the purpose of the commitments was not meant to disassemble the first installed sleeve assembly on each unit.
4.2 NRC Staff Evaluation The NRC staff evaluated the design, examinations, analysis, pressure tests, and hardship justification of the proposed repair method in relief request RR-ISI-04-08, as documented in its safety evaluation dated November 13, 2013. Therefore, for relief request RR-ISI-04-08, Revision 1, the purpose of the NRC staff's review is not to repeat the review of the proposed alternative, but to evaluate the above changes with respect to the original relief request RR-ISI-04-08.
4.2.1 Change #1 -The Repair of the Bell and Spigot Joint The NRC staff evaluated the concept of using the proposed alternative to repair bell and spigot joints. The NRC staff notes that the potential for relative motion between the two pipe sections to be the significant difference in using the proposed alternative to repair pipe joints as compared to the previously approved use of the proposed alternative to repair pipe segments.
The NRC staff also notes that, as in the case of the "as designed" joint, no rigid material will be applied across the joint which would be damaged by relative motion between the two pipe segments. The NRC staff has determined that relative motion between pipe segments will be minimized as a result of the location of that piping relative to other structures. The NRC staff has also determined that the EPDM gasket is sufficiently flexible to maintain the necessary seal and not become dislodged due to relative motion between pipe segments. Therefore, the NRC staff finds this change to the proposed alternative to be acceptable.
4.2.2 Change #2- Change in Design Temperature The NRC staff notes that the licensee has revised its stress calculations using a design temperature of 200 °F. The licensee's revised calculation shows that the sleeve components will be within the allowable stresses, based on a design temperature of 200 °F. Therefore, the NRC staff finds this change to be acceptable.
4.2.3 Change #3- Removal of Cement Lining The NRC staff reviewed the extent to which concrete lining will be removed from the pipe and the sealant material which will be installed. The NRC staff has determined that the extent to which the concrete lining will be removed from the pipe is sufficient to ensure an adequate surface over which the EPDM gasket can be applied. The NRC staff has also determined that the qualification and expected service life of the sealant are reasonable for the sealant's intended purpose. Therefore, the NRC staff finds this change to the proposed alternative to be acceptable.
4.2.4 Change #4- Limitation on Application The NRC staff reviewed the additional limitation on the applicability of the proposed alternative.
The proposed alternative will not be used in cases of through-wall leakage. The NRC staff has determined that this limitation is appropriate, because this limitation obviates the need to consider the ingress of water into the repair from the outside of the repair. Since the repair is not designed to prevent the entry of water into the repair from the outside, the NRC has determined that this limitation is both necessary and sufficient to protect the repair from water intrusion. Therefore, the NRC staff finds this change to the proposed alternative to be acceptable.
4.2.5 Change #5- Inspection Procedures The NRC staff reviewed the additional steps which the licensee added to the inspection procedures. The NRC has determined that the additional steps will reduce the possibility that degradation of the repair would not be identified during a scheduled inspection. Therefore, the NRC staff finds this change to the proposed alternative to be acceptable.
4.2.6 Change #6- Projection of Defect Growth The NRC staff has no objections to the deletion of "projections on growth will be provided" because neither the ASME Code,Section XI, nor 10 CFR 50.55a, requires licensees to submit defect growth projections regarding ASME Code Class 3 piping. However, while the licensee is not required to submit these projections to the NRC, the NRC staff notes that these projections are necessary to ensure the adequacy of the repair and, therefore, must be made and appropriately documented. The NRC staff finds this change to the proposed alternative to be acceptable.
4.2.7 Change# 7- Regulatory Commitments The NRC staff reviewed the regulatory commitments and finds these commitments to be technically acceptable.
5.0 CONCLUSION
As set forth above, and in conjunction with the its November 13, 2013, safety evaluation for RR-ISI-04-08, the NRC staff has determined that the licensee's proposed alternative provided reasonable assurance of structural integrity or leak tightness of the subject component, 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 had concluded that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii). Therefore, the NRC staff authorizes the use of the licensee's proposed alternative in relief request RR-ISI-04-08, Revision 1, for the remainder of the fourth 10-year lSI interval, which ends on June 30, 2019 for Calvert Cliffs.
All other ASME Code,Section XI requirements for which relief has not been specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor: John Tsao Date: December 19, 2014
G. Gellrich On February 25, 2014, the NRC staff granted verbal authorization of the licensee's proposed alternative in relief request RR-ISI-04-08, Revision 1. The enclosed safety evaluation documents the NRC staff's review and technical basis for this authorization.
If you have any questions, please contact the Calvert Cliffs Project Manager, Nadiyah Morgan, at (301) 415-1016, or by e-mail at Nadiyah.Morgan@nrc.gov.
Sincerely, IRA/
Benjamin G. Beasley, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
Safety Evaluation cc w/enclosure: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorllpl1-1 LPLI-1 RIF RidsNrrLAKGoldstein RidsNrrPMCalvertCiiffs NrrRidsDoriDpr RidsNrrDeEpnb JTsao, NRR RidsAcrsAcnw_MaiiCTR RidsRgn 1MaiiCenter ADAMS Accession No.: ML14246A069 *see dated memo OFFICE LPLI-1/PM LPLI-1/PM LPLI-1/PM DE/EPNB/BC LPLI-1/BC NAME DRender NMorgan KGoldstein DAiley BBeasley DATE 12/02/2014 12/02/2014 12/02/2014 5/15/2014* 12/19/2014 OFFICIAL RECORD COPY