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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] |
Text
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Constellation Generation Group, LLC Lusby, Maryland 20657 0 Constellation Energy April 10, 2007 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Emergency Response Data System The attached revision to the Emergency Response Data System (ERDS) Data Point Library for the Calvert Cliffs Nuclear Power Plant is provided pursuant to 10 CFR Part 50, Appendix E, Section VI.3.a.
The table below provides a brief summary of the changes:
Previous Sensor New Sensor Point Identifier Unit Description Location Location SP2112 2 Reactor Vessel Level 185 inches 160 inches SP2112 2 Reactor Vessel Level 153 inches 151 inches The "before" and "after" ERDS Data Point Library sheets are attached.
Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.
Very truly yours, Edward N. Schinner Director - Emergency Planning ENS/CAN/bjd
Attachment:
Emergency Response Data System Data Point Library (2 pages) cc: D. V. Pickett, NRC R. I. McLean, DNR S. J. Collins, NRC J. R. Jolicoeur, NRC Resident Inspector, NRC 402-(
ATTACHMENT (1)
EMERGENCY RESPONSE DATA SYSTEM DATA POINT LIBRARY Calvert Cliffs Nuclear Power Plant, Inc.
April 10, 2007
PWR Data Point Library Reference File Report Date: 06-08-2006 Page : 2 Date: 1114/1992 Reactor Unit: CC2 Data Feeder: CC21 NRC ERDS Parameter: REC VES LEV Point ID: SP2112 Plant Specific Point
Description:
REACTOR VESSEL LEVEL Generic I Condition
Description:
REACTOR VESSEL WATER LEVEL Analog I Digital: A ENGR Units I Digital States: INCHES ENGR Units Conversion: N/A Minimum Instrument Range: N/A Maximum Instrument Range: N/A Zero Point
Reference:
FAP Reference Point Notes N/A Proc or Sens: P Number of Sensors: 32 How Processed: RE:USD (REFERENCE UINQ SYS DESC)
Sensor Locations 185,153,112,71,50,29,19, & 10" ABOVE FAP Alarm / Trip Setpolnts: VOID DETECTED NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: N/A Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unique System
Description:
8 HEATED JUNCTION THERMOCOUPLES (HJTC) ARE SPACED STRATEGICALLY IN AVACANT CEA SHROUD ASSEMBLY NEAR THE VICINITY OF ONE HOT LEG OUTLET NOZZLE. AS HJTC IS UNCOVERED THE LVL THAT THE REACTOR HEAD IS UNCOVERED IS INDICATED IN INCREMENTAL STEPS. THE 1ST HJTC IS 185" FROM TOP OF FUEL ALIGNMENT PLATE(FAP); 8TH HJTC IS 10 FROM FAP: 5TH HJTC IS 50" FROM FAP WHICH IS THE CENTER LINE OF THE HOT LEGS. HOW PROCESSED: WHEN LVL DECREASES A VOID IN THE HJTC WILL PROVIDE AN OUTPUT SIGNAL FOR THAT SPECIFIC HJTC POSITION.
PWR Data Point Library Reference File Report Date: 03-13-2007 Page: 2 Date: 3/12/2007 Reactor Unit: CC2 Data Feeder: CC21 NRC ERDS Parameter: REC VES LEV Point ID: SP2112 Plant Specific Point
Description:
REACTOR VESSEL LEVEL Generic / Condition
Description:
REACTOR VESSEL WATER LEVEL Analog I Digital: A ENGR Units / Digital States: INCHES ENGR Units Conversion: N/A Minimum Instrument Range: N/A Maximum Instrument Range: N/A Zero Point
Reference:
FAP Reference Point Notes N/A Proc or Sens: P Number of Sensors: 32 How Processed: RE:USD (REFERENCE UNIQUE SYS DESC)
Sensor Locations 160,151,112,71,50,29,19, & 10" ABOVE FAP Alarm / Trip Setpoints: VOID DETECTED NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: N/A Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unique System
Description:
8 HEATED JUNCTION THERMOCOUPLES (HJTC) ARE SPACED STRATEGICALLY INA VACANT CEA SHROUD ASSEMBLY NEAR THE VICINITY OF ONE HOT LEG OUTLET NOZZLE. AS HJTC IS UNCOVERED THE LVL THAT THE REACTOR HEAD IS UNCOVERED IS INDICATED IN INCREMENTAL STEPS. THE 1ST HJTC IS 160" FROM TOP OF FUEL ALIGNMENT PLATE(FAP); 8TH HJTC IS 10" FROM FAP; 5TH HJTC IS 50" FROM FAP WHICH IS THE CENTER LINE OF THE HOT LEGS. HOW PROCESSED: WHEN LVL DECREASES A VOID INTHE HJTC WILL PROVIDE AN OUTPUT SIGNAL FOR THAT SPECIFIC HJTC POSITION.
