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Category:Letter
MONTHYEARIR 05000336/20240032024-11-0707 November 2024 Integrated Inspection Report 05000336/2024003 and 05000423/2024003 and Apparent Violation and Independent Spent Fuel Storage Installation Inspection Report 07200008/2024001 IR 05000318/20240072024-11-0606 November 2024 Assessment Follow-Up Letter for Calvert Cliffs Nuclear Power Plant, Unit 2 (Report 05000318/2024007) IR 05000317/20240032024-10-22022 October 2024 Integrated Inspection Report 05000317/2024003, 05000318/2024003, and Independent Spent Fuel Storage Installation Report 07200008/2024001 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24283A0012024-10-0909 October 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000317/20245012024-10-0707 October 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000317/2024501 and 05000318/2024501 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification IR 05000317/20240052024-08-29029 August 2024 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2024005 and 05000318/2024005) ML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML24240A1112024-08-27027 August 2024 Registration of Use of Casks to Store Spent Fuel ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000317/20240022024-08-0606 August 2024 Integrated Inspection Report 05000317/2024002 and 05000318/2024002 IR 05000317/20240102024-07-31031 July 2024 Age-Related Degradation Inspection Report 05000317/2024010 and 05000318/2024010 ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24198A0442024-07-16016 July 2024 Inservice Inspection Report IR 05000317/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000317/2024401 and 05000318/2024401 ML24177A1832024-06-25025 June 2024 Inservice Inspection Report RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24161A0012024-06-0909 June 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML24150A0522024-05-29029 May 2024 Operator Licensing Examination Approval ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24136A1962024-05-15015 May 2024 Independent Spent Fuel Storage Installation - Annual Radiological Environmental Operating Report IR 05000317/20240012024-05-0707 May 2024 Integrated Inspection Report 05000317/2024001 and 05000318/2024001 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests 05000317/LER-2024-002, Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus2024-04-29029 April 2024 Emergency Diesel Generators Automatic Start Due to Loss of a 13kV Bus 05000318/LER-2024-001, Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip2024-04-24024 April 2024 Manual Reactor Trip Due to 22 Steam Generator Feed Pump Trip ML24101A1942024-04-22022 April 2024 Closeout Letter for GL 2004-02 ML24114A0182024-04-18018 April 2024 Electronic Reporting of Occupational Exposure Reporting ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition 05000318/LER-2023-004-01, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-04-12012 April 2024 Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer IR 05000317/20240402024-04-11011 April 2024 95001 Supplemental Inspection Report 05000317/2024040 and Follow-Up Assessment Letter RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24082A0082024-03-22022 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24078A1152024-03-18018 March 2024 10 CFR 50.46 Annual Report ML24059A0632024-03-15015 March 2024 Authorization and Safety Evaluation for Alternative Request ISI-05-021 (EPID L-2023-LLR-0006) - Non-Proprietary IR 05000317/20230062024-02-28028 February 2024 Annual Assessment Letter for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, (Reports 05000317/2023006 and 05000318/2023006 ML24052A0072024-02-14014 February 2024 Core Operating Limits Report for Unit 1, Cycle 27, Revision 0 ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 ML24040A0962024-02-0909 February 2024 Notification of Readiness for NRC 95001 Inspection IR 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)) ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 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 2024-09-06
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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.