Letter Sequence Approval |
---|
TAC:MB6062, Administratively Control Containment Penetrations (Approved, Closed) TAC:MC6062, Administratively Control Containment Penetrations (Approved, Closed) TAC:MC6063, Administratively Control Containment Penetrations (Approved, Closed) |
|
MONTHYEARML0227402062002-09-26026 September 2002 Proposed Amendments Re 2 TSTFs Project stage: Other ML0406406372004-03-0101 March 2004 Response to Request for Additional Information Concerning the License Amendment Request to Revise the Refueling Operations Section of the Technical Specifications Project stage: Response to RAI ML0414505032004-05-20020 May 2004 Additional Information Concerning the License Amendment Request to Revise the Refueling Operations Section of the Technical Specifications Project stage: Request ML0422902382004-08-11011 August 2004 Withdrawal of Change 1 to License Amendment Request Regarding Revisions to the Refueling Operations Section of the Technical Specifications Project stage: Withdrawal ML0425304362004-09-13013 September 2004 Issuance of License Amendments Revision to the Refueling Operations Section of the Technical Specifications Project stage: Approval ML0425802462004-09-13013 September 2004 Tech. Spec. Pages for Amendments 268 and 244 Revision to the Refueling Operations Section of the Technical Specifications Project stage: Other ML0430001872004-10-21021 October 2004 Technical Specification Page for Corrected Amendment Nos. 268 and 244 Project stage: Other ML0429500162004-10-21021 October 2004 Correction to Amendment No. 268 and 244 Project stage: Other 2004-03-01
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications 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 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23086C0672023-04-24024 April 2023 Issuance of Amendment Nos. 345 and 323 Deletion of License Conditions Related to Decommissioning Trust ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22066B3112022-03-31031 March 2022 Correction of License Amendment Nos. 334 and 312 to Revise Instrument Testing and Calibration Definitions ML22021B6602022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000)-Enclosure 1 ML22031A2762022-02-0101 February 2022 Issuance of Indemnity Agreement Amendments-Enclosure 2 ML22021B6592022-02-0101 February 2022 Issuance of Amendments Related to Order Approving Transfer of Licenses (EPID L-2022-LLM-0000) (Letter) ML21347A8642022-01-13013 January 2022 Issuance of Amendment Nos. 342 and 320 Modifying the Licensing Basis to Allow for Full Core Offload with No Shutdown Cooling Loop Available During Certain Refueling Outages ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21299A0052021-12-14014 December 2021 Issuance of Amendments No. 340 and 318 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML20363A2422021-01-26026 January 2021 Issuance of Amendment Nos. 339 and 317 Regarding Accident Tolerant Fuel Lead Test Assemblies (EPID L-2019-LLA-0282) - (Non-Proprietary) ML20273A0882020-11-0909 November 2020 Issuance of Amendment Nos. 338 and 316 Revise Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances ML20182A1942020-08-13013 August 2020 Issuance of Amendment Nos. 336 and 314 Concerning Reactor Coolant Pump Flywheel Inspection Program ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML20034G5462020-03-12012 March 2020 Issuance of Amendments Revising Instrument Testing and Calibration Definitions ML19337D0352020-02-28028 February 2020 Issuance of Amendment Nos. 333 and 311 Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML19330D9092020-02-28028 February 2020 Issuance of Amendment Nos. 332 and 310 Risk-Informed Categorization and Treatment of Systems, Structures, and Components ML19352F1242019-12-23023 December 2019 Correction of License Amendment Nos. 327 and 305 for the Elimination of the Nuclear Advisory Committee Requirements ML19204A0632019-09-13013 September 2019 Independent Spent Fuel Storage Installation, James A. FitzPatrick, and Nine Mile Point - Issuance of Amendments to Revise the Emergency Response Organization Staff 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 ML19053A5882019-04-19019 April 2019 Plants, Units 1 and 2 - Issuance of Amendment Nos. 329 and 307 Removal of an Exception to the Minimum Education Requirements for Shift Technical Advisors ML18365A3732019-01-22022 January 2019 Issuance of Amendment Nos. 328 and 306 to Extend Completion Time of Required Action D.3 of Technical Specification 3.8.1 to 14 Days ML18318A0142018-11-30030 November 2018 Correction to Amendment Nos. 326 and 304 Add Risk-Informed Completion Time Program ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18270A1302018-10-30030 October 2018 Issuance of Amendment Nos. 326 and 304 to Add Risk-Informed Completion Time Program ML18206A2822018-08-0202 August 2018 Issuance of Amendments to Relocate the Staff Qualification Requirements ML18137A6142018-06-26026 June 2018 Calvert Cliffs Independent Spent Fuel Storage Installation; Nine Mile Point Nuclear Station; and R. E. Ginna Nuclear Power Plant - Issuance of Amendments Revising Emergency Action Level Schemes ML17163A3552017-08-31031 August 2017 Calvert Cliff, Clinton, Dresden, LaSalle, Limerick, Nine Mile Point, Peach Bottom, Quad Cities, R. E. Ginna, and Three Miles Island - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules(Cac Nos. MF9470-MF9490) ML17209A6202017-08-30030 August 2017 Issuance of Amendments Control Room Recirculation Signal and Control Room Emergency Ventilation System Technical Specifications ML17073A0672017-05-26026 May 2017 Issuance of Amendments Revising the Technical Specification Requirements for the Inservice Testing Program (CAC Nos. MF8238 - MF8256) ML16263A0012016-10-0707 October 2016 Issuance of Amendments Change to Surveillance Requirement 3.5.3.1 ML16175A3592016-08-30030 August 2016 Issuance of Amendments to Transition to Fire Protection Program NFPA-805. ML16060A4012016-04-11011 April 2016 Issuance of Amendments Relocation of Specific Surveillance Requirement Frequencies 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) ML15153A2822015-07-30030 July 2015 Issuance of Amendments Revising the Completion Date for Milestone 8 of the Cyber Security Plan (TAC Nos. MF4728, MF4729, MF4730, MF4731, MF4732, MF4733, MF4734, MF4735, MF4736, MF4737, MF4738, MF4739, MF4740 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 ML14288A1022014-10-29029 October 2014 Amendment Adoption for Technical Specification Improvement to Adopt TSTF-510-A Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. 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) 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) 2024-01-02
[Table view] Category:Safety Evaluation
MONTHYEARML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23086C0672023-04-24024 April 2023 Issuance of Amendment Nos. 345 and 323 Deletion of License Conditions Related to Decommissioning Trust ML22195A0252023-01-0303 January 2023 Authorization and Safety Evaluation for Alternative Request No. ISI-05-016 ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22202A5142022-07-28028 July 2022 Authorization of Relief Request No. RR-ISI-05-20 Regarding Mitigation of Buried Saltwater System Piping Degradation ML22105A4052022-05-0202 May 2022 Authorization and Safety Evaluation for Proposed Alternative No. ISI-05-019 ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21347A8642022-01-13013 January 2022 Issuance of Amendment Nos. 342 and 320 Modifying the Licensing Basis to Allow for Full Core Offload with No Shutdown Cooling Loop Available During Certain Refueling Outages ML21299A0052021-12-14014 December 2021 Issuance of Amendments No. 340 and 318 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21190A0042021-09-0202 September 2021 Proposed Alternative to the Requirements of the ASME Section XI, Subsection Iwl Concerning Unbound Post-Tensioning Systems ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21166A1682021-06-25025 June 2021 ML21039A6362021-02-17017 February 2021 R. E. Ginna - Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20363A2422021-01-26026 January 2021 Issuance of Amendment Nos. 339 and 317 Regarding Accident Tolerant Fuel Lead Test Assemblies (EPID L-2019-LLA-0282) - (Non-Proprietary) ML20356A1212021-01-15015 January 2021 Relief from the Requirements of the ASME Code ML20273A0882020-11-0909 November 2020 Issuance of Amendment Nos. 338 and 316 Revise Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20275A1022020-11-0404 November 2020 Proposed Alternative I4r-07 to the Requirements of the American Society of Mechanical Engineers Code ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20232A1712020-09-0101 September 2020 Request to Use Alternative Code Case OMN-26 ML20182A1942020-08-13013 August 2020 Issuance of Amendment Nos. 336 and 314 Concerning Reactor Coolant Pump Flywheel Inspection Program ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19330D9092020-02-28028 February 2020 Issuance of Amendment Nos. 332 and 310 Risk-Informed Categorization and Treatment of Systems, Structures, and Components ML19337D0352020-02-28028 February 2020 Issuance of Amendment Nos. 333 and 311 Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19298C9722019-10-31031 October 2019 50.69 Apla SE Input L-2018-LLA-0482 ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19165A2472019-08-26026 August 2019 Issuance of Amendment Nos 330 and 308 Relocation and Consolidation the Emergency Operations Facility and Joint Information Center for the Calvert Cliffs Nuclear Power Plant ML19168A1172019-07-29029 July 2019 Issuance of Relief Request 15R-03 Use of ASME Code N-513-4 ML19196A1232019-07-19019 July 2019 Issuance of Relief Request 15R-04 Use of Encoded Phased Array Ultrasonic Examination Techniques ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19134A3732019-05-30030 May 2019 Issuance of Relief Request I5R-05 Relief from the Requirements of the ASME Code ML19136A2162019-05-30030 May 2019 Use of a Provision in a Later Edition of the ASME Code ML19053A5882019-04-19019 April 2019 Plants, Units 1 and 2 - Issuance of Amendment Nos. 329 and 307 Removal of an Exception to the Minimum Education Requirements for Shift Technical Advisors ML19046A0432019-02-25025 February 2019 Plants, Units 1 and 2 - Revision to the Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule ML18365A3732019-01-22022 January 2019 Issuance of Amendment Nos. 328 and 306 to Extend Completion Time of Required Action D.3 of Technical Specification 3.8.1 to 14 Days ML18318A0142018-11-30030 November 2018 Correction to Amendment Nos. 326 and 304 Add Risk-Informed Completion Time Program ML18309A3012018-11-15015 November 2018 R. E. Ginna - Issuance of Amendment Nos. 327, 305, 232, 173, and 133, Respectively, Eliminating the Nuclear Advisory Committee Requirements ML18270A1302018-10-30030 October 2018 Issuance of Amendment Nos. 326 and 304 to Add Risk-Informed Completion Time Program 2024-01-02
[Table view] |
Text
September 13, 2004 Mr. George Vanderheyden, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: REVISION TO THE REFUELING OPERATIONS SECTION OF THE TECHNICAL SPECIFICATIONS (TAC NOS.
MB6062 AND MB6063)
Dear Mr. Vanderheyden:
The Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. DPR-53 and Amendment No. 244 to Renewed Facility Operating License No.
DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 6, 2002, as supplemented by letters dated December 12, 2002, July 24, 2003, and March 1, May 20, and August 11, 2004.
The amendments replace the TS 3.9.4 and TS 3.9.5 requirements to close all containment penetrations providing direct access from the containment atmosphere to outside temperature with a set of more detailed and less restrictive requirements. In your supplemental letter dated August 11, 2004, you determined that the calculations needed to support an interim control room habitability determination did not form a sufficient basis to support your proposed change to TS 3.9.3. Therefore, you withdrew the proposed change to TS 3.9.3 from further NRC review.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions Biweekly Federal Register Notice.
Sincerely,
/RA/
Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. Amendment No. 268 to License No. DPR-53
- 2. Amendment No. 244 to License No. DPR-69
- 3. Safety Evaluation cc w/encls: See next page
September 13, 2004 Mr. George Vanderheyden, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: REVISION TO THE REFUELING OPERATIONS SECTION OF THE TECHNICAL SPECIFICATIONS (TAC NOS.
MB6062 AND MB6063)
Dear Mr. Vanderheyden:
The Commission has issued the enclosed Amendment No. 268 to Renewed Facility Operating License No. DPR-53 and Amendment No. 244 to Renewed Facility Operating License No.
DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 6, 2002, as supplemented by letters dated December 12, 2002, July 24, 2003, and March 1, May 20, and August 11, 2004.
The amendments replace the TS 3.9.4 and TS 3.9.5 requirements to close all containment penetrations providing direct access from the containment atmosphere to outside temperature with a set of more detailed and less restrictive requirements. In your supplemental letter dated August 11, 2004, you determined that the calculations needed to support an interim control room habitability determination did not form a sufficient basis to support your proposed change to TS 3.9.3. Therefore, you withdrew the proposed change to TS 3.9.3 from further NRC review.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions Biweekly Federal Register Notice.
Sincerely,
/RA/
Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosures:
- 1. Amendment No. 268 to DISTRIBUTION:
License No. DPR-53 PDI-1 R/F GMatakas, RGN-1
- 2. Amendment No. 244 to ACRS RGuzman OGC License No. DPR-69 PUBLIC SLittle GHill (4)
- 3. Safety Evaluation JHayes RLaufer JDixon DCullison cc w/encls: See next page
- Provided SE input by memo. No substantive changes made.
Accession No.: ML042530436 Package No.: ML042530441 TSs: ML OFFICE PDI-1/PM PDI-2/LA SPLB* OGC PDI-1/SC NAME RGuzman SLittle SWeerakkody SLewis RLaufer DATE 9/10/04 9/10/04 1/7/03 9/2/04 9/13/04 OFFICIAL RECORD COPY
Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 cc Mr. George Vanderheyden Regional Administrator, Region I Vice President U.S. Nuclear Regulatory Commission Calvert Cliffs Nuclear Power Plant, Inc. 475 Allendale Road Calvert Cliffs Nuclear Power Plant King of Prussia, PA 19406 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Kristen A. Burger, Esquire Maryland Peoples Counsel President 6 St. Paul Centre Calvert County Board of Suite 2102 Commissioners Baltimore, MD 21202-1631 175 Main Street Prince Frederick, MD 20678 Patricia T. Birnie, Esquire Co-Director James M. Petro, Esquire Maryland Safe Energy Coalition Counsel P.O. Box 33111 Constellation Energy Baltimore, MD 21218 750 East Pratt Street, 17th floor Baltimore, MD 21202 Mr. Loren F. Donatell NRC Technical Training Center Jay E. Silberg, Esquire 5700 Brainerd Road Shaw, Pittman, Potts, and Trowbridge Chattanooga, TN 37411-4017 2300 N Street, NW Washington, DC 20037 Lou Larragoite Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. R. I. McLean, Administrator Radioecology Environ Impact Prog Department of Natural Resources Nuclear Evaluations 580 Taylor Avenue Tawes State Office Building Annapolis, MD 21401
CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 268 Renewed License No. DPR-53
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) dated August 6, 2002, as supplemented by letters dated December 12, 2002, July 24, 2003, and March 1, May 20, and August 11, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2. of Renewed Facility Operating License No. DPR-53 is hereby amended to read as follows:
- 2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 268, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 13, 2004
CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 244 Renewed License No. DPR-69
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) dated August 6, 2002, as supplemented by letters dated December 12, 2002, July 24, 2003, and March 1, May 20, and August 11, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commissions rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2. of Renewed Facility Operating License No. DPR-69 is hereby amended to read as follows:
- 2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 244, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 13, 2004
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 244 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3.9.4-2 3.9.4-2 3.9.4-3 3.9.4-3 3.9.5-3 3.9.5-3
- 3.9.5-4
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 268 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 244 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-69 CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318
1.0 INTRODUCTION
By application dated August 6, 2002 (ADAMS Accession No. ML022210229), as supplemented by letters dated December 12, 2002 (ADAMS Accession No. ML023510053), July 24, 2003 (ADAMS Accession No. ML032110026), March 1, 2004 (ADAMS Accession No. ML040640637), May 20, 2004 (ADAMS Accession No. ML041450503), and August 11, 2004 (ADAMS Accession No. ML042290238), the Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (CCNPP 1 and 2), Technical Specifications (TSs). The requested changes would replace the requirement in TSs 3.9.4 and 3.9.5 to close all containment penetrations providing direct access from containment atmosphere to the outside atmosphere with a set of more detailed and less restrictive requirements.
The supplemental letters dated December 12, 2002, July 24, 2003, March 1, 2004, and May 20, 2004, provided clarifying information that did not change the Nuclear Regulatory Commission (NRC) staffs proposed no significant hazards consideration determination as published in the Federal Register (67 FR 63690, October 15, 2002).
The August 6, 2002, submittal also requested a change to TS 3.9.3 to allow penetration flow paths that have direct access from the containment atmosphere to the outside atmosphere to be unisolated under administrative control during core alterations and fuel handling within containment. Based on its review of the licensee's application and supplements, the NRC staff concluded that the licensee had not demonstrated that the control room operator doses would meet General Design Criterion (GDC) 19 or how normal or accident releases would be monitored. Subsequently, in the supplemental letter dated August 11, 2004, the licensee determined that the calculations needed to support an interim Control Room habitability determination did not form a sufficient basis to support its proposed change to TS 3.9.3.
Therefore, the licensee withdrew its proposed change to TS 3.9.3 from further NRC review, and requested NRC to continue review of the remaining proposed changes.
2.0 REGULATORY EVALUATION
The NRC staff finds that the licensee in its August 6, 2002, submittal identified the applicable regulatory requirements. The regulatory requirements and guidance which the NRC staff considered in its review of the application are as follows:
- 1. Title 10 of the Code of Federal Regulations (10 CFR) establishes the fundamental regulatory requirements with respect to the reactivity control systems. Specifically, GDC 16, Containment design, in Appendix A to Part 50, "General Design Criteria for Nuclear Power Plants," states that reactor containment and associated systems shall be provided to establish an essentially leak tight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require.
- 2. GDC 50, Containment design basis, states, in part, that the reactor containment structure, including access openings, penetrations, and the containment heat removal system shall be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any loss-of-coolant accident.
- 3. NUREG-1432, Revision 2, Standard Technical Specifications Combustion Engineering Plants, provides, in part, the TSs for the shutdown cooling system during refueling operations.
3.0 TECHNICAL EVALUATION
3.1 Technical Specification Task Force 197 (TSTF-197)
The licensee proposed changes to the Action statements in TS 3.9.4, Shutdown Cooling (SDC) and Coolant Circulation - High Water Level, and TS 3.9.5, Shutdown Cooling and Coolant Circulation - Low Water Level. The proposed changes would clarify requirements in the Action statement. Both TSs currently require the licensee to Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere when the limiting condition for operation is not met. This wording is common to Combustion Engineering plant TSs and is the subject of TSTF-197. TSTF-197 addresses the concern that this wording is vague and, in some cases, overly restrictive and that there is no reason that the containment purge valves should be closed as long as they are Operable (i.e., will close automatically on a Containment High Radiation Signal). To replace the overly restrictive actions, TSTF-197 replaces the above phrase with the following actions:
- 1. close the equipment hatch and secure with [four] bolts;
- 2. close one door in each airlock; and
- 3. either close each penetration providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent, or verify the penetration is capable of being
closed by an OPERABLE Containment Purge and Exhaust Isolation System.
3.2 TS 3.9.4, SDC and Coolant Circulation - High Water Level The licensee proposes to replace Action A.4, which is required with One required SDC loop inoperable or not in operation, with more descriptive actions. Action A.4 states:
Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.
Action A.4 will be replaced with the following to clarify what penetrations should be closed:
A.4.1 Close equipment hatch and secure with a minimum of four bolts, OR A.4.2 Close the containment outage door.
AND A.5 Close one door in each airlock.
AND A.6.1 Close each penetration providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.
OR A.6.2 Verify each penetration is capable of being closed by an OPERABLE Containment Purge Valve Isolation System.
3.3 TS 3.9.5, SDC and Coolant Circulation - Low Water Level The licensee proposes to replace Action B.3 which is required with No SDC loop OPERABLE or in operation with more descriptive actions. Action B.3 states:
Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.
Action B.3 will be replaced with the following to clarify what penetrations should be closed:
B.3.1 Close equipment hatch and secure with a minimum of four bolts, OR B.3.2 Close the containment outage door.
AND B.4 Close one door in each airlock, AND B.5.1 Close each penetration providing direct access from the containment atmosphere to the outside atmosphere with a manual or automatic isolation valve, blind flange, or equivalent.
OR B.5.2 Verify each penetration is capable of being closed by an OPERABLE Containment Purge Valve Isolation System.
3.4 Evaluation of the proposed changes to TS 3.9.4 and TS 3.9.5 As stated in TSTF-197, the change to TS 3.9.4 and TS 3.9.5 has several advantages. First, establishing containment closure meets the Bases description for the Action, which is to prevent fission products from being released from the containment during a loss of shutdown cooling event. Secondly, containment closure is a well understood and controlled condition which is used routinely during a refueling outage. Utilizing containment closure instead of the current special actions gives greater confidence that the containment will be in the appropriate state.
Therefore, the analysis assumptions and Bases assumptions for the Actions are preserved while eliminating an unclear requirement, lessening the administrative burden on the plant, and increasing confidence that the containment will be in the proper status should an event occur.
The licensee is not proposing to change the 4-hour completion time for the required action in TS 3.9.4 and TS 3.9.5, which is consistent with TSTF-197. In addition, CCNPP 1 and 2 have containment outage doors in addition to the equipment hatches. The containment outage door can be closed more rapidly than the equipment hatch and was installed so containment closure could be achieved in less time in the event of an accident while shutdown with the equipment hatch open. The containment outage door is designed to prevent a radioactive release to the atmosphere outside containment if SDC is lost, and retain the pressure generated by boiling reactor coolant resulting from a loss of SDC. In the event of a loss of SDC, the containment outage door will perform the function of the equipment hatch. The proposed changes to TS 3.9.4 and TS 3.9.5 are consistent with and meet all the guidance in TSTF-197. Therefore, the NRC staff determines that the proposed changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Maryland State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has
determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (67 FR 63690, dated October 15, 2002). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded based on the considerations discussed above that: (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 Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: D. Cullison Date: September 13, 2004