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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
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Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG.
a joint venture of Constellation *EJmeDF Energy,-D CALVERT CLIFFS NUCLEAR POWER PLANT October 23, 2013 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Corntrol Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 2; Dc,cket No. 50-318 E~mer~enev Re *stonse Data System
..
R e...s. . . . D. at . . ...
.... er,--t 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:
Point Identifier Unit Description Status 2R542 1! 2 Main Stm Rad Lp 21 Range changed 2R5422! 2 Main Stm Rad Lp 22 Range changed The "before" and "after" ERDS Data Point Library sheets are attached.
There are no regulatory commitments contained in this correspondence.
Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.
Very truly yours, Michael J. Fick Director-Emergency Planning MJF/PSF/bjd
Attachment:
Emergency Response Data System Data Point Library (4 pages) cc: N. S. Morgan, NRC Resident Inspector, NRC W. M. Dean, NRC S. Gray, DNR
ýLP AD IJ
ATTACHMENT EMERGENCY RESPONSE DATA SYSTEM DATA POINT LIBRARY (4 pages)
Calvert Cliffs Nuclear Power Plant, LLC October 23, 2013
PWR Data Point Library Reference File Report Date: 02-28-2013 Page: 29 Date: 5/29/1997 Reactor Unit: CC2 Data Feeder: CC21 NRC ERDS Parameter: MAIN SL 1/A Point ID: 2R5421!
Plant Specific Point
Description:
MAIN STM RAD LP 21 Generic i Condition
Description:
STM GEN 21 STEAM LINE RAD LEVEL Analog I Digital: A ENGR Units I Digital States: R/HR ENGR Units Conversion: N/A Minimum Instrument Range: 1E-4 Maximum Instrument Range: 1E4 Zero Point Reierence: N/A Reference Point Notes N/A Proc or Sens: P Number of Sensors:
How Processed: INVERSE LOG OF INSTRUMENT VALUE Sensor Locations N/A Alarm / Trip Setpoints: N/A NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode; NfA Temperature Compensation for DP Transmitters: IN Level Reference Leg: N/A Unique System
Description:
THE MAIN STEAM EFFLUENT RADIATION DETECTORS MONITOR FOR NOBLE GASSES WITHIN THE MAIN STEAM LINE. THE MONITORS ARE LOCATED ON THE 27-FOOT LEVEL OF THE AUX BUILDING IN THE MSIV ROOM.
PWR Data Point Library Reference File Report Date: 02-28-2013 Page : 30 Date: 5/29/1997 N
Reactor Unit: CC2 Data Feeder: CC2 1 NRC ERDS Parameter: MAIN SL 2/B Point ID: 2R5422!
Plant Specific Point
Description:
MAIN STM RAD LP 22 Generic I Condition
Description:
STM GEN 22 STEAM LINE RAD LEVEL Analog / Digital: A ENGR Units I Digital States: RIHR ENGR Units C onversion: NIA Minimum Instrument Range: 1E-4 Maximum Instrument Range: 1E4 Zero Point
Reference:
N/A Reference Point Notes NIA Proc or Sens: P Number of Sensors: 1 How Processedl:. INVERSE LOG OF INSTRUMENT VALUE Sensor Locations NIA Alarm I Trip Setpoints: N/A NI Detector Power Supply Cut-Off Power Level: NIA NI Detector Power Supply Turn-on Power Level: N/A Instrument Failure Mode: N/A Temperature Compensation for DP Transmitters: N Level Referenpce Leg: N/A Unique System
Description:
THE MAIN STEAM EFFLUENT RADIATION DETECTORS MONITOR FOR NOBLE GASSES WITHIN THE MAIN STEAM LINE, THE MONITORS ARE LOCATED ON THE 27-FOOT LEVEL OF THE AUX BUILDING INTHE MSIV ROOM.
PWR Data Point Library Reference File Report Date: 10-04-2013 Page: 29 Date: 5/29/1997 Reactor Unit: CC2 Data Feeder: CC21 NRC ERDS Parameter: MAIN SL I/A Point ID: 2R5421 Plant Specific Point
Description:
MAIN STM RAD LP 21 Generic I Condition
Description:
STM GEN 21 STEAM LINE RAD LEVEL Analog / Digital: A ENGR Units I Digital States: uCi/cc ENGR Units Conversion: N/A Minimum Instrument Range: 1E-2 Maximum Instrument Range: 1E4 Zero Point
Reference:
N/A Reference Point Notes N/A Proc or Sens: P Number of Sensors: 1 How Processed: INSTRUMENT VALUE Sensor Locations N/A Alarm I Trip Setpoints: N/A 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:
THE MAIN STEAM EFFLUENT RADIATION DETECTORS MONITOR FOR NOBLE GASSES WITHIN THE MAIN STEAM LINE. THE MONITORS ARE LOCATED ON THE 27-FOOT LEVEL OF THE AUX BUILDING IN THE MSIV ROOM.
PWR Data Point Library Reference File Report Date: 10-04-2013 Page: 30 Date: 5/29/1997 Reactor Unit: CC2 Data Feeder: CC21 NRC EROS Parameter: MAIN SL 2/B Point ID: 2R54221 Plant Specific Point
Description:
MAIN STM RAD LP 22 Generic / Condition
Description:
STM GEN 22 STEAM LINE RAD LEVEL Analog I Digital' A ENGR Units I Digital States: uCi/cc ENGR Units Conversion: NIA Minimum Instrument Range: I E-2 Maximum Instrument Range: 1 E4 Zero Point
Reference:
N/A Reference Point Notes N/A Proc or Sens: P Number of Sensors: 1 How Processed: INSTRUMENT VALUE Sensor Locations N/A Alarm / Trip Sotpoints: N/A NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Turn-oni Power Level: N/A Instrument Failure Mode: N/A Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unique System
Description:
THE MAIN STEAM EFFLUENT RADIATION DETECTORS MONITOR FOR NOBLE GASSES WITHIN THE MAIN STEAM LINE. THE MONITORS ARE LOCATED ON THE 27-FOOT LEVEL OF THE AUX BUILDING IN THE MSIV ROOM.