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MONTHYEARML0904001862009-02-12012 February 2009 Acceptance Review of Relief Request ISI-04-04-Calvert Cliffs Nuclear Power Plant, Units 1 and 2-(TAC ME0298 and ME0299) Project stage: Acceptance Review 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 Project stage: Acceptance Review ML0910303782009-04-27027 April 2009 Request for Additional Information Concerning the Risk Evaluation for the Fourth Ten-Year Interval Inservice Inspection Program Plan for Calvert Cliffs Nuclear Power Plant Units 1 and 2 (TAC Nos. ME0298 and ME0299) Project stage: RAI ML0911802362009-05-0505 May 2009 Request for Additional Information Relief Request No. ISI-04-04 - Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Project stage: RAI ML0913302472009-05-13013 May 2009 Response to Request for Additional Information - ASME Code Case N-747 Relief Request ISI-04-0 1 Project stage: Response to RAI ML0915302742009-06-0101 June 2009 Response to Request for Additional Information Concerning Relief Request ISI-04-04, Attachment 1 Project stage: Response to RAI ML0916003072009-06-0909 June 2009 Units, 1 & 2 - Response to Request for Additional Information Concerning Relief Request ISI-04-04 Project stage: Response to RAI ML0932200902009-11-19019 November 2009 Relief Requests for the Fourth 10-Year Interval Inservice Inspection Program Project stage: Other 2009-04-27
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Category:Code Relief or Alternative
MONTHYEARML24179A3262024-07-23023 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-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 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 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 2024-07-23
[Table view] Category:Letter
MONTHYEARML24255A8642024-09-0606 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 05000317/LER-2024-001, Submittal of LER 2024-001-01 for Calvert Cliffs Nuclear Power Plant, Unit 1, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed2024-07-0202 July 2024 Submittal of LER 2024-001-01 for Calvert Cliffs Nuclear Power Plant, Unit 1, Condition Prohibited by Technical Specifications Due to Safety Injection Check Valve Not Full Closed 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 ML24121A0022024-04-29029 April 2024 Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus ML24115A1832024-04-24024 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 ML24107B0992024-04-12012 April 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000317/20240402024-04-11011 April 2024 95001 Supplemental Inspection Report 05000317/2024040 and Follow-Up Assessment Letter RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24082A0082024-03-22022 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24078A1152024-03-18018 March 2024 10 CFR 50.46 Annual Report ML24059A0632024-03-15015 March 2024 Authorization and Safety Evaluation for Alternative Request ISI-05-021 (EPID L-2023-LLR-0006) - Non-Proprietary IR 05000317/20230062024-02-28028 February 2024 Annual Assessment Letter for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, (Reports 05000317/2023006 and 05000318/2023006 ML24052A0072024-02-14014 February 2024 Core Operating Limits Report for Unit 1, Cycle 27, Revision 0 ML24040A0962024-02-0909 February 2024 Notification of Readiness for NRC 95001 Inspection ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 IR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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-2023-003, 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 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 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 2024-09-06
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Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 SUB.JECT: ACCEPTANCE REVIEW OF RELIEF REQUESTS ISI-04-01 THROUGH ISI-04 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 (TAC NOS. ME0293, ME0294, ME0295, ME0296, ME0301, ME0302, ME0298, AND ME0299)
Dear Mr. Spina:
By letter dated December 29, 2008, Calvert Cliffs Nuclear Power Plant, Inc. (the licensee),
submitted the Fourth Ten-Year Intervallnservice Inspection Program Plan and a request for approval of relief requests to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI. The relief requests included:
- Relief Request ISI-04-02 would implement the alternative requirements of ASME Code Case I'J-753.
- Relief Request ISI-04-03 would not classify the steam generator closure girth weld as a structural discontinuity therefore, not SUbjecting it to volumetric examination.
- Relief Request ISI-04-04 would implement a risk-informed safety-based inservice inspection (lSI) program for Class 1 and 2 piping. The relief request is based upon ASME Code Case N-716, "Alternative Piping Classification and Examination Requirements,Section XI Division 1," which is founded on the risk-informed lSI process described in Eiectric Power Research Institute Topical Report 112657 Rev. B-A, "Revised Risk-Informed Inservice Inspection Evaluation Procedure."
The purpose of this letter is to provide the results of the Nuclear Hequlatory Commission (NRC) staff's acceptance review of the relief requests. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
By letter dated February 12, 2009, the NRC provided the results of its acceptance review for Relief Request ISI-04-04 and concluded that supplemental information would be necessary in order to complete the acceptance review process. By letter dated February 18, 2009, the licensee supplemented the original application thus providing additional clarification.
J. Spina -2 The I\IRC staff has completed its review of the original application and the supplemental letter and concludes that technical information has been provided in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief requests in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 Distribution via Listserv
J. Spina -2 The NRC staff has completed its review of the original application and the supplemental letter and concludes that technical information has been provided in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief requests in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, IRA!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318 Distribution via Listserv Distribution PUBLIC LPLI-1 RidsNrrDraApla RidsNrrDorlLpl1-1 RidsNrrPMDPickett RidsNrrLASLittle RidsOgcMailCenter RidsAcrsAcnwMailCenter GDentel, R1 SDinsmore, APLA RidsNrrDciCvib CSydnor, CVIB ADAMS Accession No. ML090540122 OFFICE LPLI-1/PM LPLI-1/LA APLAlBC(A) LPLI-1/BC NAME DPickett SLittie AHowe MKowal DATE 02/24/09 02/23/09 02/24/09 02/24/09 OFFICIAL RECORD COpy