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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 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 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 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 ML24040A0962024-02-0909 February 2024 Notification of Readiness for NRC 95001 Inspection ML24040A1492024-02-0909 February 2024 Response to NRC Request for Additional Information Regarding Final Response to Generic Letter 2004-02 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
[Table view] Category:Report
MONTHYEARML24240A2462024-08-27027 August 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report ML23055A2842023-02-24024 February 2023 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22178A1722022-06-27027 June 2022 Long Term Coupon Surveillance Program ML22147A1782022-05-27027 May 2022 Owners Activity Report (Form OAR-1) for the Calvert Cliffs Nuclear Power Plant Unit 1 Spring 2022 Refueling Outage ML21263A1862021-09-20020 September 2021 Proposed Alternative Concerning Pressure Testing of ASME Section XI Class 2 Portions of the Auxiliary Feedwater System RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21210A3252021-07-30030 July 2021 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld ML21077A1802021-03-18018 March 2021 10 CFR 50.46 Annual Report and 30-day Report for Framatome'S Protect Enhanced Accident Tolerant Fuel (Eatf) Lead Test Assembly (LTA) ML21013A5302021-01-13013 January 2021 Reactor Vessel Level Monitoring System Special Report RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20280A5082020-10-0606 October 2020 Submittal of Relief Request CISI-03-01 Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML20034E3462020-02-0707 February 2020 Review of the Spring 2019 Steam Generator Tube Inspection Report ML19347A7792019-12-12012 December 2019 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML19072A0962019-03-11011 March 2019 Information Regarding Dissimilar Metal Weld 2-CV-2005-30 Flaw Characteristic and Repair Weld Overlay ML17324B3692017-12-20020 December 2017 Flood Hazard Mitigation Strategies Assessment RS-16-181, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-11-0909 November 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16061A0162016-02-26026 February 2016 ISFSI - Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72-48 ML16057A0022016-02-25025 February 2016 Report Concerning Dissimilar Metal Weld Flaw in Pressurizer Safety Relief Nozzle-to-Safe-End Weld ML16076A3522016-02-24024 February 2016 Plants, Units 1 and 2 - E-mail Re. Draft Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzel to Safe End Weld ML15350A1082016-01-19019 January 2016 Review of the 2015 Steam Generator Tube Inspections ML15281A2182015-10-21021 October 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation RS-15-095, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-04-30030 April 2015 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML15077A1032015-04-16016 April 2015 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15075A3392015-03-10010 March 2015 NUH32PHB-0101, Revision 4, Design Criteria Document (DCD) for the Nuhoms 32PHB System for Storage ML15062A0432015-02-27027 February 2015 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML15042A1372015-02-0303 February 2015 Gesc, NAC International, Atlanta Corporate Headquarters, 655 Engineering Drive, Norcross, Georgia (Engineering Report #NS3-020, Effects of 1300F on Unfilled NS-3, While Bisco Products, Inc., 11/84), Enclosure 4 L-14-036, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-17017 December 2014 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14212A3072014-07-25025 July 2014 NUH32PHB.0101, Rev. 2, Design Criteria Document (DCD) for Nuhoms 32PHB System for Storage. ML14212A3082014-07-25025 July 2014 NUH32PHB-011, Rev 3, Design Report for 32PHB Dsc. ML14170B0222014-06-26026 June 2014 Staff Assessment of Flooding Walkdown Reports Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Accident ML14206B0072014-05-19019 May 2014 Considerations for Using Marinite in Refined GSI-191 Chemical Effects Testing. CCNPP-CHLE-009, Revision 4 ML14206B0092014-05-12012 May 2014 Considerations for Using Zinc in Refined GSI-191 Chemical Effects Testing. CCNPP-CHLE-008, Revision 4 ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML14071A4782014-02-21021 February 2014 Response to Nrc'S Request for Cashflow Statements Regarding Application for Order Approving Transfer of Operating Authority and Conforming License Amendments ML13225A5662013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) ML13338A6462013-12-0909 December 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2, TAC Nos.: MF1142 and MF1143 ML13319B0802013-11-14014 November 2013 Proposed 10 CFR 50.55a Request for Repair of Saltwater Piping Leak (RR-ISI-04-09) ML13319A9322013-11-11011 November 2013 CCNPP-BPPlan-002, Rev 0E, Small Scale Debris Bypass-Penetration Test Plan for Calvert Cliffs Nuclear Power Plant. ML13319A6792013-10-31031 October 2013 CCNPP-CHLE-007, Appendix 1, Alkyd Coatings in Refined GSI-191 Chemical Effects Testing. ML13319A6702013-10-18018 October 2013 CCNPP-CHLE-007, Rev. G, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. ML13319A6212013-10-0404 October 2013 CCNPP-CHLE-003, Rev. 0d Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant. ML13301A6742013-09-24024 September 2013 Enclosure 1 - Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML13224A1032013-08-0808 August 2013 CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. ML13224A0942013-08-0606 August 2013 Chemical Effects Pirt Considerations for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-003, Revision 0c ML13149A4052013-05-23023 May 2013 Metals BENCH-TOP Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant, CCNPP-CHLE-006, Revision 0, May 23, 2013 2024-08-27
[Table view] Category:Miscellaneous
MONTHYEARML21263A1862021-09-20020 September 2021 Proposed Alternative Concerning Pressure Testing of ASME Section XI Class 2 Portions of the Auxiliary Feedwater System ML21013A5302021-01-13013 January 2021 Reactor Vessel Level Monitoring System Special Report ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML17324B3692017-12-20020 December 2017 Flood Hazard Mitigation Strategies Assessment RS-16-181, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-11-0909 November 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16061A0162016-02-26026 February 2016 ISFSI - Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72-48 ML16057A0022016-02-25025 February 2016 Report Concerning Dissimilar Metal Weld Flaw in Pressurizer Safety Relief Nozzle-to-Safe-End Weld ML16076A3522016-02-24024 February 2016 Plants, Units 1 and 2 - E-mail Re. Draft Report Concerning Dissimilar Metal Weld Indication on Pressurizer Safety Relief Nozzel to Safe End Weld ML15350A1082016-01-19019 January 2016 Review of the 2015 Steam Generator Tube Inspections ML15281A2182015-10-21021 October 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanism Reevaluation RS-15-095, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2015-04-30030 April 2015 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML15062A0432015-02-27027 February 2015 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 L-14-036, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-17017 December 2014 Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14170B0222014-06-26026 June 2014 Staff Assessment of Flooding Walkdown Reports Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Accident ML14206B0092014-05-12012 May 2014 Considerations for Using Zinc in Refined GSI-191 Chemical Effects Testing. CCNPP-CHLE-008, Revision 4 ML14099A1962014-03-31031 March 2014 Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. ML13225A5662013-12-17017 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049(Mitigation Strategies) ML13224A1032013-08-0808 August 2013 CCNPP-CHLE-007, Revision 0c, Coatings Bench-Top Autoclave Experiment Test Plan for Calvert Cliffs Nuclear Power Plant. ML13078A0102013-03-12012 March 2013 Flood Hazard Reevaluation Report ML13066A1712013-02-28028 February 2013 R.E. Gina, Overall Integrated Plan for Mitigation Strategies for Beyond-Design-Basis External Events ML12055A0482012-02-22022 February 2012 Independent Spent Fuel Storage Installation, Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML12027A0122012-01-24024 January 2012 Core Operating Limits Report for Unit 1, Cycle 20 ML1109400392011-03-31031 March 2011 10 CFR 50.46 30-day Report for Changes to the Emergency Core Cooling System Performance Analysis ML1024302022010-08-27027 August 2010 Reactor Vessel Water Level Monitoring System Special Report ML0935205402009-11-25025 November 2009 Submittal of Updated List of Facility Emission Inventory Registration ML0911901582009-04-24024 April 2009 Post-Accident Monitoring Report ML12220A1012008-11-24024 November 2008 Constellation Energy Group, Inc. Definitive Proxy Statement Schedule 14A ML0827602832008-10-0101 October 2008 Attachments 1 & 2, Calvert Cliffs Nuclear Power Plant Inc., Proposed Alternative ISI-020, and Proposed Alternative ISI-021 ML0827404972008-09-30030 September 2008 Calvert Cliffs Nuclear Plant, Attachment 2, ECCS and CS System Figures ML0827404952008-09-30030 September 2008 Calvert Cliffs Nuclear Plant, Attachment 1, Supplemental Response to Generic Letter 2004-02 ML0807402272008-03-12012 March 2008 Response to Request for Additional Information Control Room Habitability ML0805004452008-02-14014 February 2008 Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 ML0709305152007-03-27027 March 2007 Core Operating Limits Report for Unit 2, Cycle 17, Revision 0 ML0703201272007-01-30030 January 2007 Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds ML0625600382006-09-0707 September 2006 Special Report: Technical Specification 4.1, Appendix B, Unusual Fish Kill IR 05000317/20040082006-06-0101 June 2006 Final Precursor Analysis - Calvert Cliffs 2, LER 318/04-001-00; IR 05000317-04-008 and 05000318-04-008 - Excessive Steam Demand - Reactor Trip Due to Low Steam Generator Water Level After Feed Pump Trip ML0611101802006-04-21021 April 2006 Enclosure 1 - Report ORNL/NRC/LTR-05/22, Results of Probabilistic Fracture Mechanics Analyses of Pressurized Thermal Shock Transients for Calvert Cliffs Nuclear Power Plant Using Favor 04.1 ML0611704292006-04-11011 April 2006 Core Operating Limits Report for Unit 1, Cycle 18, Revision 2 ML0606100812006-02-27027 February 2006 2005 Steam Generator Tube Inspection Results Report ML0513701102005-05-12012 May 2005 Days After Plant Restart Report - First Revised NRC Order EA-03-009, Interim Inspection Requirement for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0421501542004-07-28028 July 2004 Special Report: Mortality of a Species Protected by the Endangered Species Act of 1973 ML0318909502003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-duty Enhancements for Nuclear Security Force Personnel for Calvert Cliffs, ML0313301332003-05-0707 May 2003 Emergency Response Data System ML0306202372003-02-26026 February 2003 Report of Changes, Tests, & Experiments - 10 CFR 50.59 ML0306202432003-02-21021 February 2003 Reactor Vessel Water Level Monitoring System Special Report ML0300805942003-01-0303 January 2003 Report of Changes, Tests, & Experiments - 10 CFR 50.59 ML0223203592002-08-13013 August 2002 Special Report Re National Pollution Discharge Elimination System Permit No. 99-DP-0187 Violation from Calvert Cliffs Units 1 & 2 ML0220001132002-07-15015 July 2002 Emergency Response Data System ML0215503102002-05-29029 May 2002 Submittal of Emergency Core Cooling System Codes and Methods Report 2021-09-20
[Table view] |
Text
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Constellation Generation Group, LLC Lusby, Maryland 20657 Constellation I Energy Group May 7, 2003 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:
Point Unit Description - -PreviousRange New Range Identifier'--;.-- :---
SP3I17A 2 Steam Generator 21 Water -401.5:62.5 inches 401.0:63.5 inches Level SP3Il7B 2 Steam Generator 22 Vater 401.5:62.5 inches -401.0:63.5 inches Level SPOI06A 2 Steam Generator 21 Inlet 212:705 DEGF 50:700 DEGF Temperature SPOI06B 2 Steam Generator 22 Inlet 212:705 DEGF 50:700 DEGF Temperature SP3113A 2 Steam Generator 21 Outlet 212:705 DEGF 50:700 DEGF Temperature SP3113B 2 Steam Generator 22 Outlet 212:705 DEGF 50:700 DEGF Temperature The Data Point Library Sheet for point SP3123, Core Subcooled Margin, wvas revised to delete the alarzm setpoint to match the SPDS Alarm Manual and to change the number of sensors from 45 to 35.
The "before" and "after" ERDS Data Point Library sheets are attached. 1A (DC 7 0
Document Control Desk May 7, 2003 Page 2 Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, 304842? C/
Edward H. Roach Director - Emergency Planning EHR/CAN/bjd
Attachment:
As Stated cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R. I. McLean, DNR G. S. Vissing, NRC J. R. Jolicoeur, NRC
PWR DATA POINT LIBRARY REFERENCE FILE REV DATE: 11/04/92 PAGE : 4 DATE: 07/005/91 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC ERDS PARAMETER: SUB MARGIN POINT ID: SP31 23 PLANT SPEC POINT DESC.: CORE SUBCOOLED MARGIN GENERIC/COND DESC.: SATLIRATION TEMPERATURE-HIGH CET ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: DEGF ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 40 MAXIMUM INSTR RANGE: 230C ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 45 HOW PROCESSED: AVG EACH QUADRANT'S PTS.:4 QUADS-4 AVGS SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: 2 OF 4 HIGHEST AVGS IN QUADRANT 650 NI DETECTOR POWER SUPPLY CUT-OFF POWER LEV: N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEV: N/A INSTRUMENT FAILURE HOE: N/A TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N tEVEL-REFERENCE-4EG* 4h-k UNIQUE SYSTEM DESC.: CORE SUBCOOLED MARGIN IS CALCULATED BY THE
)RATION TEMPERATURE AS DETERMINED FROM SURIZER PRESSURE MINUS THE CORE EXIT TEMP 2113).
PWR Data Point Library Reference File Report Date: 03-26-2003 Page: 4 Date: 03/26/2003 Reactor Unit: CC2 Data Feeder CC21 NRC ERDS Parameter SUB MARGIN Point ID: SP3123 Plant Speclfic Point Descripion: CORE SUBCOOLED MARGIN Generic / Condition
Description:
SATURATION TEMPERATURE-HIGH CET Analog I Dlgital: A ENGR Units / Digital States: DEGF ENGR UnIts Converslon: N/A Minimum Instrument Range: 40 Maximum Instrument Range: 2300 Zero Point
Reference:
N/A Reference Point Notes N/A Proc or Sens: P Number of Sensors: 35 How Processed: AVG EACH QUADRANTS PTS.:4 QUADS-4 AVGS Sensor Locations N/A Alarm / Trip Stpoints: N/A NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Tum-on Power Level: N/A Instrument Failure Mode: N/A Tempetature Conpensation for DP Transmitters: N Level Reference Leg: N/A Unique System
Description:
CORE SUBCOOLED MARGIN ISCALCULATED BY THE SATURATION TEMPERATURE AS DETERMINED FROM PRESSURIZER PRESSURE MINUS THE CORE EXIT TEMP (SP2113).
PWR DATA POINT LIBRARY REFERENCE FILE REV DATE: 11/04/92 PAGE 6 DATE: 07/05/91 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC ERDS PARAMETER: SG LEVEL 1/A POINT ID: SP3117A PLANT SPEC POINT DESC.: SG LEVEL LOOP 21 GENERIC/COND DESC.: STEAM GENERATOR 21 WATER LEVEL ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: INCHES ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: -401.5 MAXIMUM INSTR RANGE: 62.5 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: Oil= 601" ABOVE THE FEED RING PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED: AVG OF TWO CHANNELS SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: X >= 50 X =-170 NI DETECTOR POWER SUPPLY CUT-OFF POWER LEV-: N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEV: N/A INSTRUMENT FAILURE MOE: N/A TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N
-6E-VE-REFERENGE-LEG-UNIQUE SYSTEM DESC.: A LOW LEVEL REACTOR TRIP OCCURS AT -50" AS READ ON THE NARROW RANGE LEVEL DETECTOR. AFAS WILL ACTUATE AT -170" AS READ ON THE WIDE RANGE S/G LVL DETECTOR. POINT ID SP3117A IS A WIDE RANGE LVL INDICATOR.
PWR Data Point Ubrary Reforence File Report Date: 03-18-2003 Page: 6 Date: 03/18/2003 Reactor Unit CC2 Data Feeder CC21 NRC ERDS Parameter: SG LEVEL 1/A Point ID: SP311 7A Plant Specific Point
Description:
SG LEVEL LOOP 21 Goneric / Condition
Description:
STEAM GENERATOR 21 WATER LEVEL Analog / Digital: A ENGR Units / Digital States: INCHES ENGR Units CoQrensIon: N/A Minimum Instrument Range: -401.0 Maximum Instrument Range: 63.5 Zero Point
Reference:
N/A Reference Point Notes 0" = 60" ABOVE THE FEED RING Proc or Sens: p Number of Sensors: 2 How Processed: AVG OF TWO CHANNELS S6ris6r16citins N/A Alarm / Trip Setpoints: X>=50 X <=-170 NI Detector Power Supply Cut-Off Power Level: N/A Ni Detector Power Supply Tum-on Power Level: N/A Instrument Failure Mode: N/A Temperature Compensation for DP Transmitters: N Level Reference Leg: WET Unique System
Description:
A LOW LEVEL REACTOR TRIP OCCURS AT AS READ ON THE NARROW RANGE LEVEL DETECTOR. AFAS WILL ACTUATE AT -170" AS READ ON THE WIDE RANGE S/G LVL DETECTOR. POINT IDSP3I17A ISA WIDE RANGE LVL INDICATOR.
PUR DATA POINT LIBRARY REFERENCE FILE REV DATE: 11/04/92 PAGE : 7 DATE: 07/05/91 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC ERDS PARAMETER: SG LEVEL 2/B POINT ID: SP3117B PLANT SPEC POINT DESC.: SG LEVEL LOOP 22 GENERIC/COND DESC.: STEAM GENERATOR 22 WATER LEVEL ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: INCHES ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: -401.5 MAXIMUM INSTR RANGE: 62.5 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: 0" = 60" ABOVE THE FEED RING PROC OR SENS: P NUMBER OF SENSORS: 2 HOW PROCESSED: AVG OF TWO CHANNELS SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: X >= 50 X <=-170 NI DETECTOR POWER SUPPLY.CUT-OFF POWER.LEV: N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEV: N/A INSTRUMENT FAILURE MODE: N/A TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N LEYEL_REFERENCE_LEG: LWEL..
UNIQUE SYSTEM DESC.: A LOW LEVEL REACTOR TRIP OCCURS AT -50" AS READ ON THE NARROW RANGE LEVEL DETECTOR. AFAS WILL ACTUATE AT -170" AS READ ON THE WIDE RANGE S/G LVL DETECTOR. POINT ID SP3117B IS A WIDE RANGE LVL INDICATOR.
PWR Data Point Library Reference File Report Date: 03-18-2003
- Page: 7 Date: 03/18/2003 Reactor Unit: CC2 Dala Feeder. CC21 NRC ERDS Parameter: SG LEVEL 2/B Point ID: SP311 7B Plant Specific Point
Description:
SG LEVEL LOOP 22 Generic / CondiHion
Description:
STEAM GENERATOR 22 WATER LEVEL Analog / Digital: A ENGR Units / Digital States: INCHES ENGR Vnits Conversion: NA,.
Minimum Instrument Range: -401.0 Maximum Instrument Range: 63.5 Zero Point
Reference:
N/A Reference Point Notes 0 = 60" ABOVE THE FEED RING Proc or Sens: p Number of Sensors: 2 How Processed: AVG OF TWO CHANNELS Sbffs6rlcbti6ris N/A Alarm / Trip Setpoints: X>=50 X<=-170 NI Detector Power Supply Cut-Off Power Level: N/A Ni Detector Power Supply Tum-on Power Level: NIA Instrument Failure Mode: N/A Temperature Compensaffon for DP Transmiters: N Level Reference Leg: WET Unique System
Description:
A LOW LEVEL REACTOR TRIP OCCURS AT -50 AS READ ON THE NARROW RANGE LEVEL DETECTOR. AFAS WILL ACTUATE AT -170 AS READ ON THE WIDE RANGE S/G LVL DETECTOR. POINT IDSP31178 ISA WIDE RANGE LVL INDICATOR.
PWR DATA POINT LIBRARY REFERENCE FILE REV DATE: 11/04/92 PAGE : 14 DATE: 08/15/91 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC ERDS PARAMETER: HL TEMP 1/A POINT ID: SPOI06A PLANT SPEC POINT DESC.: THOT LOOP 21 GENERIC/COND DESC.: STM GEN 21 INLET TEMPERATURE ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: DEGF ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 212 MAXIMUM INSTR RANGE: 705 ZERO POINT REfERENCE: N/A REFERENCE POINT NOTES: N/A PROC OR SENS: p NUMBER OF SENSORS: 2 HOW PROCESSED: AVG OF TWO CHANNELS
) SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: N/A NI DETECTOR POWER SUPPLY CUT-OFF POWER LEV; N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEV: N/A INSTRUMENT FAILURE MODE: N/A TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N LEVEL REFERENCE-LEG. IA.
UNIQUE SYSTEM DESC.: THOT IS THE COOLANT TEMPERATURE MEASURED AT THE INLET TO THE STEAM GEN. THOT PROVIDES INPUT TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE TM/LP) CIRCUIT FOR A TOTAL POWER CALCULATION IN THE REACTOR PROTECTION SYSTEM.
PWR Data Point Library Reference File Report Date: 03-18-2003 Page:' 14 Date: 03/18/2003 Reactor Unit: CC2 Data Feeder CC21 NRC ERDS Parameter HL TEMP 1/A Point ID: SPOI06A Plant Specific Point
Description:
THOT LOOP 21 Generic / Condition
Description:
STM GEN 21 INLET TEMPERATURE Analog I Digital: A ENGR Units I Digital States: DEGF ENGR.UnIts Conyversjon:
Minimum Instrument Range: 50 Maximum Instrument Range: 700 Zero Point
Reference:
N/A Reference Point Notes N/A Proc or Soens: P Number of Sensors: 2 How Processed: AVG OF IWO CHANNELS V1A Alarm I Trip Setpolnts: 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:
THOT ISTHE COOLANT TEMPERATURE MEASURED AT THE INLET TO THE STEAM GEN. THOT PROVIDES INPUT TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE (TM/LP) CIRCUff FOR A TOTAL POWER CALCULATION INTHE REACTOR PROTECTION SYSTEM.
PWR DATA POINT LIBRARY REFERENCE FiLE REV DATE: 11/04/92 PAGE : 15 DATE: 08/15/91 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC ERDS PARAMETER: HL TEMP 2/B POINT ID: SPOI06B PLANT SPEC POINT DESC.: THOT LOOP 22 GENERIC/COND DESC.: STM GEN 22 INLET TEMPERATURE ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: DEGF ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 212 MAXIMUM INSTR RANGE: 705 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 2 HOW PROCESSED: AVG OF TWO CHANNELS SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: N/A NI DETECTOR POWER SUPPLY CUT-OFF POWER LEV:
NI DETECTOR POWER SUPPLY TURN-ON POWER LEV:
INSTRUMENT FAILURE MODE:
TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N LEVEL REFERENCE lEL UNICUE SYSTEM DESC.: THOT IS THE COOLANT TEMPERATURE MEASURED AT THE
-INLET TO THE STEAM GEN. THOT PROVIDES INPUT TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE (TM/LP) CIRCUIT FOR A TOTAL POWER CALCULATION IN THE REACTOR PROTECTION SYSTEM.
PWR Data Point Library Reference File Report Date: 03-18-2003 Page: 15 Date: 03/18/2003 Reactor Unit-. CC2 Data Feeder CC21 NRC ERDS Parameter HL TEMP 2/B Point ID: SPOIo6B Plant Specific Point
Description:
THOT LOOP 22 Generic / Condition
Description:
STM GEN 22 INLET TEMPERATURE Analog / Digital: A ENGR Units / Digital States: DEGF ENGR Units Conversion: N/A Minimum Instrument Range: 50 Maximum Instrument Range: 700 Zero Point
Reference:
N/A Reference Point Notes N/A Proc or Sens: P Number of Sensors: 2 How Processed: AVG OF TWO CHANNELS SensofrLcaltons- N/A Alarm / Trip Setpoints: N/A Ni Detector Power Supply Cut-Off Power Level: N/A Ni Detector Power Supply Tum-on Power Level: N/A Instrument Failure Mode: N/A Temperature Compensafon for DP Transmitters: N Level Reference Leg: N/A Unique System Descriphion: THOT ISTHE COOLANT TEMPERATURE MEASURED AT THE INLET TO THE STEAM GEN. THOT PROVADES INPUT TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE (TMILP) CIRCUIT FOR A TOTAL POWER CALCULATlON INTHE REACTOR PROTECTION SYSTEM.
PWR DATA POINT LIBRARY REFERENCE FILE REV DATE: 11/04/92 PAGE : 16 DATE: 08/15/91 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC ERDS PARAMETER: CL TEMP 1/A POINT ID: SP3113A PLANT SPEC POINT DESC.: TCOLD LOOP 21 GENERIC/COND DESC.: STM GEN 21 OUTLET TEMPERATURE ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: DEGF ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 212 HAXIMUM INSTR RANGE: 705 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 3 HOW PROCESSED: AVG OF TWO CHNLS AUCTIONEERED:WR OR NR)
SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: X >= 560 X <= 504 NI DETECTOR POWER SUPPLY CUT-OFF-POWER LEV: N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEV: N/A INSTRUMENT FAILURE MODE: N/A TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N LEVEL-REF-ERENCE--LEG<- -U/A_-. .
UNIQUE SYSTEM DESC.: THE ALARM/TRIP SET POINTS SUPPLIED ABOVE ARE SPDS ALARM SET POINTS. TCOLD PROVIDES CONTROL ROOM AND AUX SHUTDOWN PANEL INDICATION. TCOLD ALSO SUPPLIES SIGNALS TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE (TM/LP) CIRCUIT FOR TOTAL POWER CALCULATION IN THE REACTOR PROTECTION SYSTEM. AS A DNB PARAMETER TCOLD IS REQUIRED TO BE LESS THAN 548 DEG WITH 4 REACTOR COOLANT PUMPS RUNNING.
PWR Data Point Library Reference File Report Date: 03-18-2003 Page: 16 Date: 03/18/2003 Reactor Unit: CC2 Data Feeder: CC21 NRC ERDS Parameter: CL TEMP 1/A Polnt ID: SP311 3A Plant Specific Point Descripton TCOLD LOOP 21 Generic / Condition Descriptlo an: STM GEN 21 OUTLET TEMPERATURE Analog / Digital: A ENGR Units / Digital States: DEGF ENGR Units Conversion: NI/A Minimum Instrument Range: 50 Maximum Instrument Range: 700 Zero Point
Reference:
N/A Reference Polnt Notes N/A.
Proc or Sens: p Number of Sensors: 3 How Processed: AVG OF WO CHNLS (AUCTIONEERED:WR OR NR)
Sensor Locahions N/A Alarm / Trip Setpolnts: X>=560 X<=504 NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Tum-on Power Level: N/A Instrument Failure Mode: N/A Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Unlquejystem Description. THE ALARM/TRIP SET POINTS SUPPUED ABOVE ARE SPDS ALARM SET POINTS.
TCOLD PROVIDES CONTROL ROOM AND AUX SHUTDOWN PANEL INDICAION. TCOLD ALSO SUPPLIES SIGNALS TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE (TM/U') CIRCUIT FOR TOTAL POWER CALCULAlON INTHE REACTOR PROTECTION SYSTEM. AS A DNB PARAMETER TCOLD ISREQUIRED TO BE LESS THAN 548 DEG VTH 4 REACTOR COOLANT PUMPS RUNNING.
PWR DATA POINT LIBRARY REFERENCE FILE REV DATE: 11/04/92 PAGE : 17 DATE: 08/15/91 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC ERDS PARAMETER: CL TEMP 2/B POINT ID: SP3113B PLANT SPEC POINT DESC.: TCOLD LOOP 22 GENERIC/COND DESC.: STM GEN 22 OUTLET TEMPERATURE ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: DEGF ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 212 MAXIMUM INSTR RANGE: 705 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: p NUMBER OF SENSORS: 3 HOW PROCESSED: AVG OF TWO CHNLS (AUCTIONEERED:WR OR NR)
SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: X >= 560 X <= 504 NI DETECTOR POWER SUPPLY CUT-OFF POWER LEV: N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEV: N/A INSTRUMENT FAILURE MODE: N/A TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N
-LEVEL-REFERENCE-LEG4-- -flA- - ...
UNIQUE SYSTEM DESC.: THE ALARM/TRIP SET POINTS SUPPLIED ABOVE ARE SPDS ALARM SET POINTS. TCOLD PROVIDES CONTROL ROOM AND AUX SHUTDOWN PANEL INDICATION. TCOLD ALSO SUPPLIES SIGNALS TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE (TM/LP) CIRCUIT FOR TOTAL POWER CALCULATION IN THE REACTOR PROTECTION SYSTEM. AS A DNB PARAMETER TCOLD IS REQUIRED TO BE
-LESS-THAN-548-DEG-WI-TH-4-REACTOR-COOL-ART-PUMPS- - -
RUNNIAG.
. t . r 4,
PWR Data Point Library Reference File Report Dote: 03-18-2003 Page: 17 Date: 03/18/2003 Reactor Unit CC2 Data Feeder: CC21 NRC ERDS Parameler: CL TEMP 2/B Point ID: SP31 13B Plant Specific Point Descripffon: TCOLD LOOP 22 Generic / Condition
Description:
STM GEN 22 OUTLET TEMPERATURE Analog / Digital: A ENGR Units / Digital States: DEGF ENGR Jits CQnverslon:
Mlnimum Instrument Range: 50 Maximum Instrument Range: 700 Zero Point
Reference:
N/A Reference Point Notes N/A Proc or Sens: p Number of Sensors: 3 How Processed: AVG OF TWO CHNLS (AUCTIONEERED:WR OR NR)
- N7A Alarm / Trip Setpoints: X >= 560 X < 604 NI Detector Power Supply Cut-Off Power Level: N/A NI Detector Power Supply Tum-oh Power Level: N/A Instrument Failure Mode: N/A Temperature Compensation for DP Transmitters: N Level Reference Leg: N/A Uniaue System
Description:
THE ALARM/TRIP SET POINTS SUPPUED ABOVE ARE SPDS ALARM SET POINTS.
TCOLD PROVIDESCONTROL ROOM AND AUX SHUDOWN PANEL INDICATION. TCOLD ALSO SUPPUES SIGNALS TO THE SUBCOOLED MARGIN MONITOR AND THE THERMAL MARGIN/LOW PRESSURE (TMILP) CIRCUIT FOR TOTAL POWER CALCULATION INTHE AEACTOR PROTECTION SYSTEM. AS A DNB PARAMETER TCOLD ISREQUIRED TO BE LESS THAN 548 DEG WITH 4 REACTOR COOLANT PUMPS RUNNING.