|
---|
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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A 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 ML23164A1702023-06-13013 June 2023 License Amendment Request to Adopt TSTF-59-A, Incorporate (Combustion Engineering) NPSD-994 Recommendations Into the (Safety Injection Tanks) Specification, Revision 1 ML23153A0982023-06-0202 June 2023 Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (CREVS) Technical Specification RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23052A0632023-02-21021 February 2023 License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-017, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs2022-04-20020 April 2022 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs ML22067A0772022-03-31031 March 2022 Correction of License Amendment Nos. 337 and 315 to Revise Response Time Testing Definition RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments ML20329A3342020-11-24024 November 2020 Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues ML19347A7792019-12-12012 December 2019 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies ML19346E5362019-12-11011 December 2019 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions ML19325C1282019-11-21021 November 2019 License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19127A0762019-05-0606 May 2019 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML18333A0222018-11-28028 November 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. ML18235A1992018-08-23023 August 2018 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to ... ML18113A0902018-04-20020 April 2018 Administrative Change to Technical Specification 5.2.2, Unit Staff RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML17164A1432017-05-31031 May 2017 Enclosure 2C - EAL Basis Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1412017-05-31031 May 2017 Enclosure 2A - EAL Comparison Matrix Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1422017-05-31031 May 2017 Enclosure 2B - EAL Red-Line Basis Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1452017-05-31031 May 2017 Enclosure 2E - Procedure Matrix for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17087A3742017-03-28028 March 2017 License Amendment Request, Refueling Water Tank RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16266A0862016-09-22022 September 2016 License Amendment Request - Control Room Emergency Ventilation System ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16060A2232016-02-25025 February 2016 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. ML16035A2272016-02-0404 February 2016 License Amendment Request - Change to Surveillance Requirement 3.5.3.1 ML15310A0642015-11-0505 November 2015 License Amendment Request to Relocate Surveillance Frequency Requirements ML15212A9022015-07-30030 July 2015 Supplemental Information Regarding TSTF-425 License Amendment Request ML15210A3142015-07-29029 July 2015 License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 82014-08-29029 August 2014 License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8 ML14050A3742014-02-13013 February 2014 License Amendment Request Re Pressurizer Safety Valve Technical Specification Revision ML14050A3752014-02-13013 February 2014 Summary of Analysis Supporting Pressurizer Safety Valve Technical Change ML14015A1382014-01-13013 January 2014 License Amendment Request: Add Technical Specification for Atmospheric Dump Valves ML13308A3872013-10-31031 October 2013 Application for Technical Specification Improvement to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. ML13228A2652013-08-14014 August 2013 Independent Spent Fuel Storage Installations Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act & License Amendment Request ML13232A1562013-08-0606 August 2013 ISFSI, Nine Mile Point, Units 1, 2 and ISFSI and R.E. Ginna, and ISFSI, Application for Order Approving Transfer of Operating Authority and Conforming License Amendments. Part 1 of 2 ML13030A1332013-01-28028 January 2013 License Amendment Request Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML13029A4562013-01-22022 January 2013 Emergency License Amendment Request: Revise Description of Operable Containment Air Cooling Train ML11222A0202011-08-0808 August 2011 License Amendment Request: Diesel Generator Surveillance Requirement 3.8.1.11 Revision 2023-08-21
[Table view] Category:Technical Specifications
MONTHYEARML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML22067A0772022-03-31031 March 2022 Correction of License Amendment Nos. 337 and 315 to Revise Response Time Testing Definition ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position 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 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 ML18270A1302018-10-30030 October 2018 Issuance of Amendment Nos. 326 and 304 to Add Risk-Informed Completion Time Program ML17129A5062017-05-12012 May 2017 Plants, Units 1 and 2 - Correction to Technical Specification Pages 1.1-2, 1.1-3, and 1.1-4 to Correct Errors Introduced During the Issuance of Amendment Nos. 286 and 263 ML15352A1642016-03-17017 March 2016 Calvert Cliffs, Units 1 & 2 and Independent Spent Fuel Storage Installation; Nine Mile, Units 1 & 2 and R. E. Ginna - Issuance of Amendments Regarding the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel ML15279A1912015-12-30030 December 2015 Issuance of Amendment Revision to Pressurizer Safety Valve Technical Specifications ML15211A0052015-08-17017 August 2015 Amendment Adoption of TSTF-425, Relocate Specific Surveillance Frequencies to a Licensee Controlled Program ML15223B2502015-08-14014 August 2015 and Nine Mile Point Nuclear Station, Unit No. 2- Copy of License Amendment Nos. 313, 291, 118, and 150 ML15161A3802015-07-30030 July 2015 R. E. Ginna and Nine Mile Point, Unit 2 - Issuance of Amendments Regarding Implementation of Technical Specification Task Force Traveler 523, Generic Letter 2008-01, Managing Gas Accumulation (TAC Nos. MF4405 - MF4409) ML15133A1442015-07-23023 July 2015 Amendment Regarding New Technical Specification 3.7.18 for Atmospheric Dump Valves ML15154A6612015-07-16016 July 2015 Amendment License Amendment Request to Extend Containment Leakage Rate Test Frequency ML14307A8422015-01-14014 January 2015 Issuance of Amendment Regarding the Adoption of Technical Specification Task Force (TSTF) 426, Revision 5, Revise or Add Actions to Preclude Entry Into LCO (Limiting Condition of Operation) 3.0.3 ML14280A5222014-10-21021 October 2014 Amendment Enhancements to Diesel Generator Surveillance Requirements (Tac Nos. ME9832 and ME9833) ML14239A4912014-10-21021 October 2014 Issuance of Amendments Regarding the Adoption of Technical Specification Task Force 501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (TAC Nos. ME9794-95) ML14153A5622014-05-30030 May 2014 Response to Request for Additional Information Regarding Enhancements to Diesel Generator License Amendment Request ML14091A2972014-04-0101 April 2014 Issuance of Amendments to Conform the Renewed Facility Operating Licenses and Materials License to Reflect the Direct Transfer of Operating Authority (TAC Nos. MF2584, MF2585, and L24780) ML13308A3872013-10-31031 October 2013 Application for Technical Specification Improvement to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. ML13030A1332013-01-28028 January 2013 License Amendment Request Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML1134104612012-01-11011 January 2012 Amendment Technical Specification Task Force Traveler 487-A, Revision 1, Relocate DNB Parameters to the COLR ML1129406452011-12-20020 December 2011 Technical Specification Interpretation for Calvert Cliffs Nuclear Power Plant Units 1 & 2 on Limiting Condition for Operation (LCO) Applicability (LCO) 3.0.5 ML1103902242011-02-18018 February 2011 License Amendment, Transition from Westinghouse Nuclear Fuel to Areva Nuclear Fuel ML1030101702010-10-25025 October 2010 License Amendment Request: Revision of Limiting Condition for Operation 3.0.5 ML1026505292010-09-22022 September 2010 9/22/10 E-Mail to P. S. Furio from J. Goshen Calvert Amendment 9 Tech Specs Page 5 ML1026605642010-09-17017 September 2010 Technical Specification Bases, Revisions 38 & 39, Section B 3.8 - Electrical Power Systems ML1009700702010-04-0505 April 2010 License Amendment Request: Section 5.0, Administrative Controls, Personnel Title Revisions & Administrative Changes ML0933500992009-11-23023 November 2009 License Amendment Request - Transition from Westinghouse Nuclear Fuel to Areva Nuclear Fuel ML0827603842008-10-0101 October 2008 Attachment 2, Marked Up Tech Spec Pages for License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel.. ML0824706232008-08-29029 August 2008 License Amendment Request: Appendix K Measurement Uncertainty Recapture - Power Uprate Request ML0824106932008-08-28028 August 2008 Attachment (2), Marked Up Technical Specification Pages for License Amendment Request: Application for Technical Specification Change TSTF-491 ML0824806762008-08-27027 August 2008 License Amendment Request: Replacement of the Trisodium Phosphate Buffer with a Sodium Tetraborate Buffer, Attachment (2) Markup of Technical Specifications Pages ML0821104652008-07-29029 July 2008 Technical Specifications, Amendment Regarding Control Room Habitability ML0816503472008-06-11011 June 2008 Additional Information Control Room Habitability ML0805303882008-03-24024 March 2008 Units, 1 and 2 - Tech Spec Pages for Amendments 285 and 262 Addition of Limiting Condition of Operation 3.0.8 for Inoperable Snubbers ML0732004702007-12-20020 December 2007 Tech Spec Pages for Amendment Nos. 283 and 260 Use of Lead Fuel Assemblies and Change to Core Operating Limits Report Analytical Methods ML0734706402007-12-13013 December 2007 Supplement to Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0724202032007-08-29029 August 2007 Tech Spec Pages for Amendments 281 and 258 Implementation of Alternative Radiological Source Term ML0712703712007-05-0202 May 2007 License Amendment Request Add LCO 3.0.9 on the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML0712002852007-04-25025 April 2007 Technical Specifications 3.1 and 3.2, Appendix B, Reporting Related to National Pollutant Discharge Elimination System (NPDES) Permit ML0708701102007-03-22022 March 2007 Request for Additional Information Regarding Implementation for Alternative Source Term ML0706103572007-02-27027 February 2007 License Amendment Request: Change to the Core Operating Limits Report Analytical Methods List ML0706104142007-02-27027 February 2007 License Amendment Request: Use of Lead Fuel Assemblies ML0703305992007-02-0101 February 2007 License Amendment Request: Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity ML0632500502006-11-16016 November 2006 License Pages and Technical Specifications, Calvert Cliffs Units 1 & 2 2023-08-30
[Table view] |
Text
James A. Spina Vice President 0 Constellation Energy, Generation Group Calvert Cliffs Nuclear Power Plant, Inc.1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.5200 410.495.3500 Fax February 27, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 License Amendment Request: Change to the Core Operating Limits Report Analytical Methods List
REFERENCES:
(a) Letter from Mr. J. A. Spina (CCNPP) to Document Control Desk (NRC), dated February 23, 2007, Letter of Intent to Irradiate Lead Fuel Assemblies Above the Current Maximum Burnup Limit (b) WCAP-15604-NP Revision 2-A, Limited Scope High Burnup Lead Test Assemblies, September 2003 Pursuant to 10 CFR 50.90, Calvert Cliffs Nuclear Power Plant requests an amendment to Renewed Operating License Nos. DPR-53 and DPR-69 to incorporate the change described below into the Technical Specifications for Calvert Cliffs Unit Nos. 1 and 2. In a letter dated February 23, 2007 (Reference a), we submitted a letter describing our intent to irradiate up to four lead fuel assemblies (LFAs) to a higher burnup limit than currently allowed at Calvert Cliffs. These LFAs are currently installed in the Unit 2 core and are scheduled to be discharged during the 2007 refueling outage. As described in Reference (a), these assemblies are scheduled to undergo a detailed examination and will be inserted into Unit 1 Cycle 19 for the high burnup irradiation.
The purpose of this License Amendment Request is to add the supporting Topical Report (Reference b) to the list of references in Technical Specification 5.6.5, Core Operating Limits Report (COLR). The approved topical report provides guidance for operation with a limited number of LFAs to be irradiated to a higher burnup limit than currently allowed for Calvert Cliffs fuel assemblies.
The NRC Safety Evaluation for the topical report contains eight conditions for allowing a limited number of LFAs to be irradiated to a higher burnup limit. The addition of this reference to Technical Specification 5.6.5, Core Operating Limits Report (COLR), satisfies the first of these eight conditions as described in Attachment (1). Attachment (2) contains the marked up Technical Specification page. The final Technical Specification pages will be renumbered to accommodate the insertion of this change, if necessary.
SAFETY COMMITTEE REVIEW The Plant Operations Review Committee has reviewed this proposed change and concurs that operation with the proposed change will not result in an undue risk to the health and safety of the public.
Document Control Desk February 27, 2007 Page 2 SCHEDULE The re-insertion of the LFAs is currently scheduled to occur during the Unit 1 refueling outage, which is expected to begin in February or March 2008. Should this request not be granted, we would need to insert substitute fuel assemblies in their place or redesign the core loading. Therefore, we request that the license amendment be approved by December 1, 2007.Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.Very truly yours,/W STATE OF MARYLAND COUNTY OF CALVERT: TO WIT: I, James A. Spina, being duly sworn, state that I am Vice President
-Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other CCNPP employees and/or consultants.
Such information has been reviewed in accordance with company practice and I believe it to be reliable.Subscribed and sworn before me, a Notary Public in and for the State of Maryland and County of ,53. _,this ' day of / "r cta ,2007./ ,I, WITNESS my Hand and Notarial Seal: My Commission Expires: 7 ~ ~Notary Pub IiQ/xZec2 7/ -Da'te JAS/PSF/bjd Attachments:
(1) Technical Basis and No Significant Hazards Consideration (2) Marked-up Technical Specification Page Document Control Desk February 27, 2007 Page 3 cc: D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC R. I. McLean, DNR ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION TABLE OF CONTENTS
1.0 DESCRIPTION
2.0 PROPOSED CHANGE
3.0 BACKGROUND
4.0 TECHNICAL
ANALYSIS 5.0 REGULATORY ANALYSIS 6.0 ENVIRONMENTAL CONSIDERATION
7.0 PRECEDENCE
8.0 REFERENCES
Calvert Cliffs Nuclear Power Plant, Inc.February 27, 2007 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION
1.0 DESCRIPTION
This letter is a request to amend Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Units I and 2.The proposed change will revise the Operating Licenses to add an approved topical report to the Core Operating Limits Report (COLR) reference list in Technical Specification 5.6.5.b. The approved topical report presents the conditions to allow limited lead fuel assemblies (LFAs) to be irradiated to a higher burnup level than currently approved.
2.0 PROPOSED CHANGE
The proposed change will add an approved topical report (WCAP-1 5604-NP Revision 2-A) to the COLR list of topical reports in Technical Specification 5.6.5.b. The approved topical report supports the insertion of LFAs to be irradiated to a higher burnup limit than currently approved.
3.0 BACKGROUND
Calvert Cliffs Nuclear Power Plant intends to irradiate a limited number of LFAs above the current maximum burnup limit. The LFAs are part of the irradiation program originally submitted for approval in References (1) and (2) to test advanced cladding materials and an alternate fuel vendor. In the original program, there are four LFAs manufactured by Westinghouse Electric Company (Westinghouse) and four assemblies manufactured by AREVA. These eight LFAs were approved for insertion into Calvert Cliffs Unit 2 Cycles 15 and 16 to begin irradiation in April 2003, Reference (3) and (4). The assemblies are currently in their second cycle of irradiation which is scheduled to end in the spring of 2007.The original intent of the program was to irradiate these eight assemblies for a third cycle and an explicit submittal was to be provided at that time. However, since References (1) and (2) were submitted, Calvert Cliffs has re-evaluated the LFA program and modified it slightly as explained in Reference (5).The modification consists of four of the eight LFAs (two from each manufacturer) to be returned immediately to the core for a third cycle of irradiation (into either Unit 1 Cycle 19 or Unit 2 Cycle 17) in low duty locations on the core periphery to allow evaluation of grid-to-rod fretting resistance.
References (5) and (6) are the Exemption and License Amendment Request to allow the irradiation of these LFAs. These requests included the use of some advanced cladding material while not exceeding the current peak burnup limitation of 60,000 MWD/MTU.Calvert Cliffs now intends to irradiate the other four LFAs above the current maximum burnup limit. The nuclear industry has submitted a Topical Report, Reference (7), to justify the use of limited scope high burnup LFAs. This Topical Report has been approved by the NRC (References 8 and 10) and provides eight conditions for allowing limited LFA irradiation to high burnup. We understand that even though the Topical Report is a Westinghouse report, it is approved for the entire nuclear industry and may be used for the AREVA LFAs as well as the Westinghouse LFAs (Reference 7).4.0 TECHNICAL ANALYSIS The final Nuclear Regulatory Commission (NRC) Safety Evaluation (SE) for WCAP-15604-NP Revision 2-A, "Limited Scope High Burn-up Lead Test Assemblies" includes eight conditions which must be met in order for any particular licensee to participate in the limited scope LFA program. One of the conditions stated, "If the Core Operating Limits Report analytical methods listed in the licensee's Technical Specifications are approved up to a specified burnup limit a license amendment is required to add this topical report to that list in order for the licensee to be able to use the topical report." This proposed Technical Specification change satisfies the condition.
The methods listed in the Calvert Cliffs Unit I and 2 Technical Specifications are limited to a maximum rod average burnup of 60 GWD/MTU.1 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION The purpose of this License Amendment Request is to add topical report WCAP-15604-NP Revision 2-A to the reference list in order to reference it for the high burnup irradiation of a limited number of LFAs.The other seven conditions do not require a technical specification change and are listed in the topical report. Calvert Cliffs responses to these conditions are provided in a separate letter (Reference 9).5.0 REGULATORY ANALYSIS 5.1 Regulatory Requirements The applicable regulatory requirements and guidance for this type of application are as follows: Title 10 of the Code of Federal Regulations (10 CFR) establishes the fundamental regulatory requirements with respect to the reactivity control systems. Calvert Cliffs is committed to the draft General Design Criteria which implement these regulatory requirements.
Specifically, draft General Design Criterion 6, "Reactor Core Design," states, in part, that the reactor core shall be designed to function throughout its design lifetime without exceeding acceptable fuel damage limits which have been stipulated and justified.
Section 50.36(c)(2)(ii) states, in part, that a Technical Specification limiting condition for operation of a nuclear reactor must be established for a process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.Nuclear Regulatory Commission (NRC) Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications," provides guidance on modifying cycle-specific parameter limits in the Technical Specifications.
Specifically, Generic Letter 88-12 provides Core Operating Limits Report implementation guidance, which includes the requirement to list the NRC-approved analytical methods used to determ-ine the core operating limits in the Technical Specifications.
The analytical methods referenced in the Technical Specifications identify the topical report(s) by number and title, or the staffs safety evaluation report for an NRC-approved plant-specific methodology.
5.2 No Significant Hazards Consideration The proposed change to the Technical Specifications has been evaluated against the standards in 10 CFR 50.92. The proposed change has been determined to not involve a significant hazards consideration, in that operation of the facility in accordance with the proposed amendment:
- 1. Would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change would modify the Calvert Cliffs Units I and 2 Technical Specification 5.6.5.b, Core Operating Limits Report by adding an approved topical report to the existing list of topical reports. The topical report provides the technical basis that supports irradiating a limited number of lead fuel assemblies to a higher burnup limit than currently approved for Calvert Cliffs. The proposed change is administrative in nature and has no impact on any plant configurations or on system performance that is relied upon to mitigate the consequences of an accident.In the safety evaluation report approving the requested topical report (WCAP-15604-NP Revision 2-A,), the Nuclear Regulatory Commission concluded that it is acceptable for an individual power licensee to irradiate a limited number of lead fuel assemblies to a maximum burnup to 75 GWD/MTU provided that certain conditions are met. Calvert Cliffs meets those required 2 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION conditions.
Because those required conditions are met and only a limited number of fuel assemblies are included in this change, the probability or consequences of an accident previously evaluated are not significantly increased.
Therefore, the proposed change does not involve a significant increase in the probability or consequence of an accident previously evaluated.
- 2. Would not create the possibility of a new or different kind of accident from any accident previously evaluated The proposed change does not add any new equipment, modify any interfaces with existing equipment, change the equipment's function, or change the method of operating the equipment.
The proposed change does not affect normal plant operations or configuration.
Since the proposed change does not change the plant design, operation or configuration, it could not become an accident initiator.
Therefore, the proposed change does not create the possibility of a new or different type of accident from any previously evaluated.
- 3. Would not involve a significant reduction in a margin of safety.The proposed change will add a reference to an approved topical report to allow a limited number of lead fuel assemblies to be irradiated to a higher burnup level than is currently allowed at Calvert Cliffs. The higher burnup limit has been evaluated and approved in the topical report being referenced.
Calvert Cliffs conforms to the requirements of the topical report. The addition of an approved reference to the Technical Specifications is administrative in nature and has no impact on the margin of safety for any plant configuration or on system performance that is relied upon to mitigate the consequences on an accident.Therefore, the proposed change does not involve a significant reduction in the margin of safety.6.0 ENVIRONMENTAL CONSIDERATION We have determined that operation with the proposed amendment would not result in any significant change in the types, or significant increases in the amounts, of any effluents that may be released offsite, and no significant increases in individual or cumulative occupational radiation exposure.
The addition of four LFAs at a slightly higher burnup to the full core does not significantly change the type or amount of effluents released nor does it significantly affect occupational radiation exposure.
Therefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement, or environmental assessment is needed in connection with the approval of the proposed amendment.
7.0 PRECEDENCE
None.
8.0 REFERENCES
(1) Letter from Mr. P. E. Katz (CCNPP) to Document Control Desk (NRC), dated July 17, 2002, Westinghouse Lead Fuel Assemblies
-Temporary Exemption Request and License Amendment Request 3 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION (2) Letter from Mr. P. E. Katz (CCNPP) to Document Control Desk (NRC), dated August 6, 2002, Framatome Lead Fuel Assemblies
-Temporary Exemption Request and License Amendment Request (3) Letter from Mr. G. S. Vissing (NRC) to Mr. P. E. Katz (CCNPP), dated April 14, 2003, Amendments Re: Lead Fuel Assemblies (TAC Nos. MB5646, MB5647 and MB6064)(4) Letter from Mrs. G. S. Vissing (NRC) to Mr. P. E. Katz (CCNPP), dated April 11, 2003, Exemption from the Requirements of 10 CFR 50.44, 10 CFR 50.46, and 10 CFR Part 50, Appendix K (TAC Nos. MB5648 and MB6065)(5) Letter from Mr. J. A. Spina (CCNPP) to Document Control Desk (NRC), dated January 19, 2006, Temporary Exemption Request for Use of Lead Fuel Assemblies (6) Letter from Mr. J. A. Spina (CCNPP) to Document Control Desk (NRC), dated February 27, 2006, License Amendment Request: Use of Lead Fuel Assemblies (7) WCAP-15604-NP Revision 2-A, "Limited Scope High Burnup Lead Test Assemblies," September 2003 (8) Letter from W. H. Ruland (NRC) to R. H. Bryan (Westinghouse), dated January 8, 2003, Acceptance for Referencing of Topical Report WCAP-15604-NP, Revision 1 (9) Letter from Mr. J. A. Spina (CCNPP) to Document Control Desk (NRC), dated February 23, 2007, Letter of Intent to Irradiate Lead Fuel Assemblies Above the Current Maximum Burnup Limit (10) Letter from Mr. H. N. Berkow (NRC) to Mr. R. H. Bryan (Westinghouse), received August 28, 2003, Response to Comments Received from the Westinghouse Owners Group on the Safety Evaluation for WCAP-15604-NP, Revision 1 4 ATTACHMENT (2)MARKED-UP TECHNICAL SPECIFICATION PAGE Calvert Cliffs Nuclear Power Plant, Inc.February 27, 2007 Reporting Requirements 5.6 5.6 Reporting Requirements
- 46. CENPD-132, Supplement 4-P-A, "Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model" 47. CENPD-137, Supplement 2-P-A, "Calculative Methods for the ABB CE Small Break LOCA Evaluation Model" 48. WCAP-11596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System for Pressurized Water Reactor Cores" 49. WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code" 50. WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code; Enhancements to ANC Rod Power Recovery" 51. WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs" 52. WCAP-16045-P-A, "Qualification of the Two-Dimensional GTransport Code PARAGON" c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits)of the safety analysis are met.d. The COLR, including any mid cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.Not Used 5.6.6 CALVERT CLIFFS -UNIT 1 CALVERT CLIFFS -UNIT 2 5.6-8 Amendment No. 272 Amendment No. 249 INSERT 53. WCAP-15604-NP, "Limited Scope High Burnup Lead Test Assemblies"