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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:Annual Operating Report
MONTHYEARML23079A0362023-03-20020 March 2023 10 CFR 50.46 Annual Report ML22133A2222022-05-13013 May 2022 Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report ML22077A0032022-03-18018 March 2022 10 CFR 50.46 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors ML21195A0332021-07-14014 July 2021 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML20078F4232020-03-18018 March 2020 10 CFR 50.46 Annual Report ML19198A1072019-07-15015 July 2019 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML19077A1292019-03-18018 March 2019 10 CFR 50.46 Annual Report ML18011A6252017-12-11011 December 2017 the 2017 Annual Report of the Ceng Independent Nuclear Advisory Committee to the Ceng Board of Directors ML17076A0012017-03-17017 March 2017 Submittal of 10 CFR 50.46 Annual Report ML16078A0672016-03-18018 March 2016 Submittal of 10 CFR 50.46 Annual Report ML16011A0032016-01-0707 January 2016 Submittal of Annual Report of the Nuclear Advisory Committee ML15196A0392015-07-14014 July 2015 Revised 2015 10 CFR 50.46 Annual Report RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report ML14197A1122014-07-11011 July 2014 Annual Radioactive Effluent Release Report ML14126A6182014-05-0505 May 2014 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report ML14080A3072014-03-20020 March 2014 10 CFR 50.46 30-day Report and Annual Report for Changes to the Emergency Core Cooling System Performance Analysis ML13192A3282013-07-0909 July 2013 Independent Spent Fuel Storage Installation - 2012 Annual Radioactive Effluent Release Report ML13142A1482013-05-14014 May 2013 Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report ML13070A0922013-03-0707 March 2013 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML13037A3802012-12-17017 December 2012 Attachment 1b, 2012 Annual Report of the Ceng Independent Nuclear Advisory Committee ML12199A3252012-07-13013 July 2012 Enclosure (1), Annual Radioactive Effluent Release Report for Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation ML12137A8742012-05-15015 May 2012 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report ML1212203062012-04-30030 April 2012 CFR 50.46 30-day Report and Annual Report for Changes to the Emergency Core Cooling System Performance Analysis ML11229A7752011-08-15015 August 2011 Independent Spent Fuel Storage Installation - Submittal of Annual Radiological Environmental Operating Report ML11137A1722011-05-13013 May 2011 Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report for 2010 ML1106302032011-03-0202 March 2011 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML1021001912010-07-26026 July 2010 Units I & 2 and Independent Spent Fuel Storage Installation, Submittal of 2009 Radioactive Effluent Release Report ML1013803212010-05-14014 May 2010 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report ML1006901462010-03-0505 March 2010 Independent Spent Fuel Storage Installation - Report of Changes, Tests, & Experiments for 2009 ML0513203002005-03-31031 March 2005 CENPD-279, Supplement 16, Annual Report on Combustion Engineering ECCS Performance Evaluation Models for PWRs ML0508000292005-03-16016 March 2005 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML0421700302004-07-30030 July 2004 Guarantee of Retrospective Premium ML0314004782003-05-15015 May 2003 Independent Spent Fuel Storage Installation, Radiological Environmental Monitoring Program Annual Report 2023-03-20
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Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG a joint venture of constellation. 9J*eDF Ener"gMOy CALVERT CLIFFS NUCLEAR POWER PLANT March 7, 2013 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Independent Spent Fuel Storage Installation; Docket No. 72-8 Report of Changes, Tests, and Experiments- 10 CFR 50.59 and 10 CFR 72.48 In accordance with 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2), a report of changes, tests and experiments is provided as Attachment (1). The attachment contains brief descriptions of changes, tests, and experiments approved under the provisions of 10 CFR 50.59 and 10 CFR 72.48 between January 1, 2012 and December 31, 2012.
Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.
Very truly yours, for James J. Stanley Manager - Engineering Services JJS/PSF/bjd
Attachment:
(1) Calvert Cliffs Nuclear Power Plant Report of Changes, Tests, and Experiments
[10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
cc: B. Vaidya, NRC S. Gray, DNR W. M. Dean, NRC C. Haney, NMSS Resident Inspector, NRC 471
ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT REPORT OF CHANGES, TESTS, AND EXPERIMENTS
[10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
Calvert Cliffs Nuclear Power Plant, LLC March 7,2013
ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT REPORT OF CHANGES, TESTS, AND EXPERIMENTS
[10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
Document Id Doc Type Rev Status Revision Date Issued SE00512 50.59 62 0000 2/23/2012 Subject Implementation of ISFSI License Amendment 9 to extend NUHOMS-32P DSC Bumup Limit Summary Proposed Activity:
The proposed activity is the Unit 1 Cycle 21 (U1C21) core reload in all plant modes.
Reason for Activity:
The proposed activity is required to support the biennial refueling of Unit 1 at Calvert Cliffs.
Activity Evaluation:
All safety analyses required to justify Unit 1 Cycle 21 operation in all plant modes have been completed/evaluated and the currently reported UFSAR accident doses remain bounding for operation of Unit 1 Cycle 21.
Conclusions:
- Unit 1 Cycle 21 is authorized for operation in all plant modes.
- The proposed activity has been evaluated against the eight criteria of 10 CFR 50.59. It is concluded that no additional License Amendment is required prior to implementation since all items requiring prior NRC review and approval were included in the NRC Tech Spec changes and SER received on 2/18/11 Document Id Doc Type Rev Status Revision Date Issued SE00165 72.48 62 0000 11/15/2012 Subject Implementation of ISFSI License Amendment 9 to extend NUHOMS-32P DSC Burnup Limit Summary Proposed Activity:
To enable CCNPP to continue with loading operations after 2009, changes to ISFSI Technical Specification sections 1.0, 2.1, LCO 3.1.1, LCO 3.4.1.1 were submitted to the NRC on June 15, 2009, and approved on September 14, 2010 via Amendment No. 9 to SNM License-2505. Specifically these changes:
" Increase the neutron and gamma source for fuel assemblies stored in NUHOMS-32P DSCs,
" Increase the maximum fuel assembly burnup to 52,000 MWd/MTU for the NUHOMS-32P DSCs,
" Increase the maximum air temperature rise from the HSM inlet to the HSM outlet from 607F to 64°F.
" Change the definitions of intact and undamaged fuel.
In addition to the above Technical Specification changes, the NRC also required CCNPP to add a new Technical Specification requirement for hydrogen monitoring of the void space below the top shield plug during closure welding for consistency with other ISFSI Technical specification (this monitoring is already performed in ISFSI-03). No physical changes to the NUHOMS-32P DSC, the transfer cask, or the HSMs will occur as a result of this change, and the maximum heat load of the DSC will not increase. This package completes other document changes required to implement ISFSI License Amendment No. 9. This 72.48 is primarily focused on analyses associated with ES200600043-000 that were not submitted as part of the above mentioned License Amendment Request.
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ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT REPORT OF CHANGES, TESTS, AND EXPERIMENTS
[10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
Document Id Doc Type Rev Status Revision Date Issued SE00165 72.48 62 0000 11/15/2012 Reason for Activity:
The supply of fuel assemblies meeting the fuel storage requirements in the Independent Spent Fuel Storage Installation (ISFSI) Technical Specifications was exhausted during the 2009 loadings. Specifically, the burnup limit of 47,000 megawatt-days per metric ton uranium (MWd/MTU) for the NUHOMS-32P Dry Shielded Canister (DSC) was insufficient to allow all the horizontal storage modules (HSMs) in Phase III to be filled. Increasing the burnup limit to 52,000 MWd/MTU would be sufficient to allow all of the HSMs to be utilized.
Activity Evaluation:
New analyses are performed to verify that confinement, shielding, DSC internal pressure, structural stresses, and cladding temperatures are acceptable with the use of the NUHOMS-32P DSC containing fuel with a maximum burnup of 52 GWD/MTU at the CCNPP ISFSI.
The results of the analyses demonstrate that the extended burmup 32P DSC and the existing TC and HSM with the use of the extended burnup 32P DSCs meet all of the design criteria, and will provide for a safe storage of the spent fuel assemblies under normal, off-normal and postulated accident conditions.
Conclusions:
The proposed activity has been evaluated against the eight criteria of 10 CFR 72.48(c)(2). Based on this evaluation, an additional amendment for portions of the package not already submitted for ISFSI License Amendment 9 is not required. In addition, no technical specification changes beyond those which were approved with ISFSI License Amendment 9 are required.
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