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MONTHYEARML17129A5062017-05-12012 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 Project stage: Approval 2017-05-12
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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: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
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Mr. Bryan Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 May 12, 2017
SUBJECT: CALVERT CLIFFS NUCLEAR POWER PLANT, 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 (CAC NOS. MD7315 AND MD7316)
Dear Mr. Hanson:
On April 23, 2008 (Agencywide Documents Access and Management System Accession No. ML080840339), the U.S. Nuclear Regulatory Commission issued Amendment Nos. 286 and 263 to Renewed Facility Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant (Calvert Cliffs}, Units 1 and 2, respectively. During the issuance of the amendments, errors were inadvertently introduced on Technical Specification pages 1.1-2, 1.1-3, and 1.1-4. Specifically, the definitions of "DOSE EQUIVALENT 1-131" and "La" were inadvertently changed. These inadvertent changes were neither addressed in the notice for the amendments nor reviewed as part of the license amendment request. Enclosed are the corrected pages. Please, replace Technical Specification pages 1.1-2, 1.1-3, and 1.1-4 of the Calvert Cliffs, Units 1 and 2, Renewed Facility Operating Licenses with the enclosed corrected pages. If you have any questions, please contact me at (301) 415-2871 or Michael.Marshall@nrc.gov. Docket Nos. 50-317 and 50-318
Enclosure:
Corrected Calvert Cliffs, Unit 1 and 2, Technical Specification Pages cc w/encls: Distribution via Listserv
Sincerely,Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ENCLOSURE CORRECTED PAGES 11.1-2, 1.1-3, AND 1.1-4 OF RENEWED FACILITY OPERATING LICENSE NOS. DPR-53 AND DPR-69 FOR AMENDMENT NOS. 286 AND 263 EXELON GENERATION COMPANY, LLC CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-317 AND 50-318 1.1 Definitions CHANNEL FUNCTIONAL TEST CORE OPERATING LIMITS REPORT (COLR) DOSE EQUIVALENT I-131 CALVERT CLIFFS -UNIT 1 CALVERT CLIFFS -UNIT 2 Definitions 1.1 indication and status to other indications or status derived from independent instrument channels measuring the same parameter. A CHANNEL FUNCTIONAL TEST shall be: Analog Channels -the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY of a11 devices in the channel required for channel OPERABILITY. Bistable Channels -the injection of a simulated signal into the channel sensor to verify OPERABILITY of all devices in the channel ired r channel ILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential. overlapping or total channel steps. The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications. DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, I-133, 1-134, and 1-135 actually present. The TEDE (Total Effective Dose Equivalent) inhalation dose conversion factors used for this calculation shall be those listed in Table 2.1 in the column headed "effective" of Federal Guidance Report 11, ORNL, 1988, "Limiting Values of Radionuclide Intake and 1.1-2 Amendment No. 286 Amendment No. 263 1.1 Definitions f-AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE (ESF} RESPONSE TIME LEAKAGE CALVERT CLIFFS -UNIT 1 CALVERT CLIFFS -UNIT 2 Definitions 1.1 Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling} of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives> 15 minutes, making up at least 95% of the total non-iodine activity in the coolant. The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. The maximum allowable containment leakage rate, L., shall be 0.16% of containment air weight per day at the calculated peak containment pressure (P .) . LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant 1.1-3 Amendment No. 286 Amendment No. 263 1.1 Definitions MODE CALVERT CLIFFS -UNIT 1 CALVERT CLIFFS -UNIT 2 Definitions 1.1 pump (RCP) seal leakoff), that is captured and conducted to collection systems or a sump or collecting tank; 2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or 3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE). b. Unidentified LEAKAGE All LEAKAGE (except RCP seal leakoff) that is not identified LEAKAGE; c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall. A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolts specified in Table 1.1-1 with fuel in the reactor vessel. 1.1-4 Amendment No. 286 Amendment No. 263