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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: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 Calvert Cliffs Nuclear Power Plant, Inc.Vice President 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.5200 410.495.3500 Fax 0Constellation Enegye Generation Group February 1, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 License Amendment Request: Revise Containment Sump Surveillance Requirement to Verify Strainer Integrity Pursuant to 10 CFR 50.90, the Calvert Cliffs Nuclear Power Plant, Inc. hereby requests an amendment to the Renewed Operating License Nos. DPR-53 and DPR-69 to revise Surveillance Requirement 3.5.2.8 in Technical Specification 3.5.2, "ECCS -Operating," to reflect the replacement of the containment recirculation sump suction inlet trash racks and screens with strainers.
The containment recirculation sump suction inlet trash racks and screens are being replaced with a strainer design with significantly larger effective surface area in response to Nuclear Regulatory Commission (NRC) Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors." Although the configurations of the existing trash racks and screens and the replacement sump strainer assemblies are different, they serve the same fundamental purpose of passively removing debris from the recirculation sump's suction supply of the Emergency Core Cooling System pumps. The descriptive terminology of trash racks and screens is not descriptive of the new sump strainers.
The proposed replacement of "trash racks and screens" with "strainers" is a descriptive change and Surveillance Requirement 3.5.2.8 will continue to ensure the containment recirculation sump strainers are not restricted by debris and show no evidence of structural distress or abnormal corrosion.
The significant hazards discussion and the technical basis for this proposed change are provided in Attachment (1). A mark-up of the affected Technical Specification page is provided in Attachment (2).The Technical Specification Bases will be changed as appropriate to support this information.
Schedule We request approval of the proposed change during the spring 2008 refueling outage, scheduled to start February 24, 2008, to support completion of the strainer installation on Unit I during that refueling outage. Strainer installation is scheduled to be completed on Unit 2 in the spring 2007 refueling outage.The new Unit 2 strainer will be inspected to the same requirements as the existing surveillance prior to start-up from the spring 2007 refueling outage (i.e., Emergency Core Cooling System train containment sump suction inlet is not restricted by debris and the strainer shows no evidence of structural distress or abnormal corrosion).
Therefore, we will be in compliance with the revised surveillance requirement wording when the proposed amendment request is approved.
In addition, the supporting 10 CFR 50.59 evaluation concludes that the new strainer system will perform the required safety function as well as or better than the existing system.
Document Control Desk February 1, 2007 Page 2 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.Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.Very trul ours, 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 liable.Subscribed and sworn before me, a Notary Public in and for the State of Maryland and County of z.ir § ,this 1 day of dY1 af ,2007.WITNESS my Hand and Notarial Seal: My Commission Expires: Notary Public,/Date JAS/PSF/bjd Attachments:
(1)(2)Technical Basis and No Significant Hazards Consideration Marked Up Technical Specification Page Document Control Desk February 1, 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 PRECEDENTS
8.0 REFERENCES
Calvert Cliffs Nuclear Power Plant, Inc.February 1, 2007 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION EVALUATION
1.0 DESCRIPTION
This license amendment request revises Surveillance Requirement (SR) 3.5.2.8 in Technical Specification 3.5.2, "ECCS -Operating," to reflect the replacement of the containment recirculation sump suction inlet trash racks and screens with strainers.
The containment recirculation sump suction inlet trash racks and screens are being replaced with a strainer design with significantly larger effective surface area in response to Nuclear Regulatory Commission (NRC) Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors" (Reference 1).
2.0 PROPOSED CHANGE
Technical Specification 3.5.2, SR 3.5.2.8 is revised to reflect the replacement of the containment trecirculation sump suction inlet trash racks and screens with strainers.
Surveillance Requirement 3.5.2.8 currently states: "Verify, by visual inspection, each ECCS train containment sump suction inlet is not restricted by debris and the suction inlet trash racks and screens show no evidence of structural distress or abnormal corrosion." Surveillance Requirement 3.5.2.8 is revised to: "Verify, by visual inspection, each ECCS train containment sump suction inlet is not restricted by debris and the suction inlet strainers show no evidence of structural distress or abnormal corrosion."
3.0 BACKGROUND
Generic Safety Issue-191, "Assessment of Debris Accumulation on PWR Sump Performance," deals with the possibility that debris could accumulate on the Emergency Core Cooling System (ECCS) sump screen resulting in a loss of net positive suction head (NPSH) margin. The loss of NPSH margin to ECCS pumps drawing suction from the sump may impede or prevent the flow of water needed to meet the criteria of Title 10, Code of Federal Regulations, Section 50.46 (10 CFR 50.46), "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors." Title 10 CFR 50.46 requires that licensees design their ECCS to meet five criteria, one of which is to provide the capability for long-term cooling. Following a successful system initiation, the ECCS must be able to provide cooling for a sufficient duration that the core temperature is maintained at an acceptably low value. In addition, the ECCS must be able to continue decay heat removal for the extended period of time required by the long-lived radioactivity remaining in the core.Nuclear Regulatory Commission Bulletin 2003-01, "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors," (Reference
- 2) requested information to verify compliance with NRC regulations and to ensure that any interim risks associated with post-accident debris blockage are minimized while evaluations of the latest sump knowledge proceed. Nuclear Regulatory Commission Generic Letter 2004-02 is the follow-on generic communication to NRC Bulletin 2003-01 and requested information on the results of the evaluations referenced in the bulletin.Calvert Cliffs Nuclear Power Plant (CCNPP) has evaluated the containment recirculation sumps for adverse effects due to debris blockage of flow paths necessary for ECCS and Containment Spray System recirculation and containment drainage.
That evaluation concluded that in order to continue to comply with applicable regulatory requirements large sump strainers of a different design are required.Consequently, this license amendment request is to change the Calvert Cliffs Technical Specifications in support of plant modifications required by NRC Generic Letter 2004-02.4.0 TECHNICAL ANALYSIS Calvert Cliffs Nuclear Power Plant plans to install new containment recirculation sump strainers to increase the available (i.e., submerged) strainer area from approximately 102 square feet currently 1 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION available to an expected area of approximately 6000 square feet (Reference 3). The existing recirculation sump design uses multiple screens located above the sump area. The sump screens consist of: (1) an outer trash rack which is constructed of grating material, (2) an inner stainless steel wire mesh screen with a nominal opening of 0.244-inches, and (3) a stainless steel frame constructed of 1 A inch angle iron and bar stock. In addition, a 12-inch concrete curb is provided on which the sump screen is supported to prevent high density particles from entering the recirculation sump. The new design will remove the existing screen hardware described above and replace it with new fabricated strainer assemblies utilizing the Control Components Inc. cassette type suction strainer system. On the floor of each containment building, modules of the cassettes will be installed and will extend approximately three feet above the containment building floor. This strainer design was chosen based on the largest available sump strainer area that would fit within the available space within the containment building and to be compatible with anticipated water level.The new sump strainer is designed to reduce both head loss and the ingestion of debris which could affect downstream components.
The containment recirculation sump strainers are sized to preclude the passage of debris large enough to damage downstream Containment Spray System and ECCS components or block flow passages such as flow channels in the fuel and the Containment Spray System nozzles. This function is required to support operation of the supported systems during postulated accidents which credit recirculation flow from the containment recirculation sump. Activities are currently underway to ensure that the containment recirculation sump functions under debris loading conditions at CCNPP will be in full compliance with the regulatory requirements listed in the Applicable Regulatory Requirements section of NRC Generic Letter 2004-02 following the Unit 1 refueling outage scheduled to begin February 24, 2008 (Reference 4). Full compliance will be achieved through a combination of analysis, testing, modifications to increase the available recirculation sump screen area, other changes to the plant to reduce the potential debris loading on the installed containment recirculation sump strainers, and programmatic and process changes as needed.This proposed amendment to Technical Specification SR 3.5.2.8 is necessary to reflect the new strainer design. Although the configurations of the existing trash racks and screens and the replacement sump strainer assemblies are different, they serve the same fundamental purpose of passively removing debris from the recirculation sump's suction supply of the supported system pumps. The descriptive terminology of trash racks and screens is not descriptive of the new sump strainers.
The proposed replacement of"trash racks and screens" with "strainers" is a descriptive change and SR 3.5.2.8 will continue to ensure the containment recirculation sump strainers are not restricted by debris and show no evidence of structural distress or abnormal corrosion.
5.0 REGULATORY ANALYSIS This section addresses the standards of 10 CFR 50.92 as well as the applicable regulatory requirements and acceptance criteria.5.1 No Significant Hazards Consideration Calvert Cliffs Nuclear Power Plant (CCNPP) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," Part 50.92(c), as discussed below: (1) Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
The consequences of accidents evaluated in the Updated Final Safety Analysis Report that could be affected by the proposed change are those involving the pressurization of Containment and 2 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION associated flooding of the Containment and recirculation of this fluid within the Emergency Core Cooling System (ECCS) or the Containment Spray System (CSS) (e.g., loss-of-coolant accidents[LOCAs]).
The proposed change does not impact the initiation or probability of occurrence of any accident.
Although the configurations of the existing containment recirculation sump trash racks and screen and the replacement sump strainer cassettes are different, they serve the same fundamental purpose of passively removing debris from the sump's suction supply of the supported system pumps. Removal of trash racks does not impact the adequacy of the pump net positive suction head assumed in the safety analysis.
Likewise, the change does not reduce the reliability of any supported systems or introduce any new system interactions.
The greatly increased surface area of the new strainer is designed to reduce head loss and reduce the approach velocity at the strainer face significantly, decreasing the risk of impact from large debris entrained in the sump flow stream.Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2) Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
The containment recirculation sump strainers are a passive system used for accident mitigation.
As such, they cannot be accident initiators.
Therefore, there is no possibility that this change could create any new or different kind of accident.
No new accident scenarios, transient precursors, or limiting single failures are introduced as a result of the proposed change. There will be no adverse effect or challenges imposed on any safety-related system as a result of the change. Therefore, the possibility of a new or different type of accident is not created.There are no changes which would cause the malfunction of safety-related equipment, assumed to be OPERABLE in the accident analyses, as a result of the proposed Technical Specification change. No new equipment performance burdens are imposed. The possibility of a malfunction of safety-related equipment with a different result is not created.Therefore, the proposed change does not create the possibility of a new or different accident from any accident previously evaluated.
(3) Does the proposed change involve a significant reduction in a margin of safety?The proposed change does not affect the acceptance criteria for any analyzed event nor is there a change to any safety analysis limit. There will be no effect on the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined nor will there be any effect on those plant systems necessary to assure the accomplishment of protection functions.
The proposed change does not adversely affect the fuel, fuel cladding, Reactor Coolant System, or containment integrity.
The radiological dose consequence acceptance criteria listed in the Updated Final Safety Analysis Report will continue to be met.Therefore, the proposed change does not involve a significant reduction in a margin of safety.Conclusion:
Based on the above evaluation, CCNPP concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, a finding of "no significant hazards consideration" is justified.
3 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION 5.2 Applicable Regulatory Requirements/Criteria This license amendment request involves replacing the current "trash racks and screens" of the containment sump by installing new "strainers" that increase the area that would filter debris from the water in the containment sump.The NRC's regulatory requirements related to the application to replace the existing containment sump screen or strainer are the following:
- Paragraph 50.46(b)(5) of Title 10 to Part 50 of the Code of Federal Regulations (10 CFR 50.46(b)(5)), "Acceptance criteria for emergency core cooling systems for light water-nuclear power reactors," which states that after any calculated successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptably low value and decay heat shall be removed for the extended period of time required by the long-lived radioactivity remaining in the core." Draft General Design Criterion (GDC) 44, "Emergency core cooling systems capability," which requires, in part, abundant emergency core cooling to prevent fuel and clad damage that would interfere with the emergency core cooling function and to limit the clad metal-water reactions to negligible amounts.* Draft GDC 49, "Containment design basis," which requires, in part, that the containment structure including any necessary containment heat removal systems is designed so the containment structure can accommodate the pressures and temperatures resulting from the largest credible energy release following a LOCA.* Draft GDC 52, "Containment heat removal," which requires, in part, that when active heat removal systems are needed to maintain containment pressure at acceptably low levels they shall be of different design principles and each with full capacity.* Nuclear Regulatory Commission Generic Letter 2004-02, which addresses safety issues associated with Generic Safety Issue-191, "Assessment of Debris Accumulation on PWR [pressurized-water reactor] Sump Performance," requested that PWR licensees improve their plant capability to meet the requirements of 10 CFR 50.46(b)(5) for long-term cooling in the aftermath of a design-basis loss-of-coolant accident (LOCA) with debris loading in the containment sumps.This amendment only affects the containment sump in terms of the screens or strainers that remove debris during accidents.
The trash racks, screens, or strainers ensure that sufficient flow goes from the sump to the ECCS pumps (to provide cooling to the core) and CSS pumps (to provide spray for cooling of the Containment and to reduce the radioiodine and particulate radioactivity in the containment atmosphere).
Therefore, 10 CFR 50.46(b)(5) and draft GDC 44, 49, and 52 must be addressed in the license amendment as to the requirements for long-term flow from the containment sumps to the ECCS and CSS with debris loading in the containment sumps. The amendment does not involve a change to the design, testing, or inspection requirements for the ECCS and CSS in draft GDC 45 through 48 and 58 through 65.The containment recirculation sump strainers are sized to limit the passage of debris precluding damage to the downstream CSS and ECCS components or block flow passages such as flow channels in the fuel and the CSS nozzles. This function is required to support operation of the supported systems during postulated accidents which credit recirculation flow from the containment recirculation sump.Evaluations performed by CCNPP confirm that CCNPP will continue to comply with all applicable regulatory requirements.
4 ATTACHMENT (1)TECHNICAL BASIS AND NO SIGNIFICANT HAZARDS CONSIDERATION In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.6.0 ENVIRONMENTAL CONSIDERATION Calvert Cliffs has determined that the proposed amendment would change requirements with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, or would change an inspection or surveillance requirement.
Calvert Cliffs has evaluated the proposed amendment and has determined that the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
7.0 PRECEDENT A similar change was approved for the Oconee Nuclear Station, Units 1 and 2 in Amendment Nos. 348 and 350 on November 1, 2005. This amendment revised SRs 3.5.2.6 and 3.5.3.6 to accommodate the replacement of the reactor building emergency sump suction inlet trash racks and screen with strainers.
Additionally, a similar change was approved for the Wolf Creek Nuclear Generating Station in Amendment No. 168 on October 5, 2006. This amendment revises SR 3.5.2.6 to accommodate the replacement of the containment emergency sump suction inlet trash racks and screen with strainers.
8.0 REFERENCES
(1) NRC Generic Letter 2004-02, dated September 13, 2004, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors" (2) NRC Bulletin 2003-01, dated June 9, 2003, "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors" (3) Letter from J. A. Spina (CCNPP) to Document Control Desk (NRC), dated September 20, 2006, Update of Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4672 and MC4673)(4) Letter from P. D. Milano (NRC) to J. A. Spina (CCNPP), dated December 18, 2006, Approval of Extension Request for Completion of Corrective Actions in Response to Generic Letter 2004-02 (TAC No. MC4672)5 ATTACHMENT (2)MARKED UP TECHNICAL SPECIFICATION PAGE Calvert Cliffs Nuclear Power Plant, Inc.February 1, 2007 ECCS -Operating 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.6 Verify each ECCS pump starts automatically 24 months on an actual or simulated actuation signal.SR 3.5.2.7 Verify each low pressure safety injection 24 months pump stops on an actual or simulated actuation signal.SR 3.5.2.8 Verify, by visual inspection, each ECCS train containment sump suction inlet is not restricted by debris and the suction inlet show no evidence of structural dstress or abnormal corrosion.
24 months SR 3.5.2.9 Verify the Shutdown Cooling System open- 24 months permissive interlock prevents the Shutdown Cooling System suction isolation valves from being opened with a simulated or actual Reactor Coolant System pressure signal of 309 psia.CALVERT CLIFFS -UNIT 1 CALVERT CLIFFS -UNIT 2 3.5.2-3 Amendment No. 227 Amendment No. 201