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Category:Annual Operating Report
MONTHYEARRS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station ML23122A0682022-12-31031 December 2022 Annual Radiological Environmental Operation Report RS-20-125, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2020-10-0909 October 2020 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-19-099, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2019-10-10010 October 2019 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-18-133, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2018-10-18018 October 2018 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-17-140, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-10-18018 October 2017 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report RS-14-307, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2014-10-24024 October 2014 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors U-604118, Annual Radiological Environmental Operating Report, January 1 Through December 31, 20122013-04-30030 April 2013 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2012 RS-12-187, Submittal of Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors2012-10-26026 October 2012 Submittal of Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors U-604072, Annual Radiological Environmental Operating Report2012-04-25025 April 2012 Annual Radiological Environmental Operating Report RS-11-168, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2011-10-28028 October 2011 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors U-604017, Annual Radiological Environmental Operating Report for the Period of January 1 Through December 31, 20102011-04-30030 April 2011 Annual Radiological Environmental Operating Report for the Period of January 1 Through December 31, 2010 U-604018, Annual Radioactive Effluent Release Report2011-04-28028 April 2011 Annual Radioactive Effluent Release Report RS-10-162, Submittal of Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2010-10-29029 October 2010 Submittal of Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors U-603962, Addenda to 2009 Annual Radioactive Effluent Release Report2010-06-0707 June 2010 Addenda to 2009 Annual Radioactive Effluent Release Report U-603952, 2009 Annual Radiological Environmental Operating Report2010-04-19019 April 2010 2009 Annual Radiological Environmental Operating Report RS-09-143, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Period of November 1, 2008 Through October 30, 20092009-10-30030 October 2009 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Period of November 1, 2008 Through October 30, 2009 U-603893, Annual Radiological Environmental Operating Report for January 1 Through December 31, 20082009-04-30030 April 2009 Annual Radiological Environmental Operating Report for January 1 Through December 31, 2008 U-603816, Annual Radiological Environmental Operating Report2007-04-27027 April 2007 Annual Radiological Environmental Operating Report RS-07-068, Updated Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors from November 4, 2005 Through November 3, 20062007-04-19019 April 2007 Updated Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors from November 4, 2005 Through November 3, 2006 RS-06-165, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for November 4, 2005 Through November 3, 20062006-11-0303 November 2006 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for November 4, 2005 Through November 3, 2006 RS-05-152, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for November 6, 2004 Through November 4, 20052005-11-0404 November 2005 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for November 6, 2004 Through November 4, 2005 RS-04-170, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2004-11-0505 November 2004 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors U-603660, 2003 Annual Radiological Environmental Operating Report2004-04-27027 April 2004 2003 Annual Radiological Environmental Operating Report U-603607, Annual Radiological Environmental Operating Report2003-04-0707 April 2003 Annual Radiological Environmental Operating Report U-603550, Annual Environmental Operating Report for Period of January 1, 01 Through December 31, 012002-04-22022 April 2002 Annual Environmental Operating Report for Period of January 1, 01 Through December 31, 01 2023-09-07
[Table view] Category:Letter type:RS
MONTHYEARRS-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-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2022-09-29029 September 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022 Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-068, Constellation Radiological Emergency Plan Addendum Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-055, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan2022-04-18018 April 2022 Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock 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 RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-09-29029 September 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021 Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-069, Third Inservice Inspection Interval Relief Request I3R-182021-06-28028 June 2021 Third Inservice Inspection Interval Relief Request I3R-18 RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments RS-21-037, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 22021-03-23023 March 2021 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 RS-21-028, Fitness for Duty Performance Data Reports - Annual 20202021-02-26026 February 2021 Fitness for Duty Performance Data Reports - Annual 2020 RS-21-032, Amended Decommissioning Trust Agreements2021-02-25025 February 2021 Amended Decommissioning Trust Agreements RS-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency2021-02-24024 February 2021 License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency RS-21-030, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2021-02-24024 February 2021 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values 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 2023-09-07
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Exelon Generation www.exeloncorp.com Exelvna 4300 Winfield Road Warrenville, IL 60555 Nuclear RS-10-162 10 CFR 50.46 October 29, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Annual Report of Emergency Core Cooling System Evaluation Model Change s
and Errors for Clinton Power Station In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Exelon Generation Compa ny, LLC (EGC) is submitting the annual report of the Emergency Core Cooling System (ECCS)
Evaluation Model changes and errors for Clinton Power Station, Unit 1 (CPS).
This report covers the period from October 31, 2009 through October 29, 2010.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-28 19.
Respectfully, JeffreiL. Hansen Manager - Licensing and Regulatory Affairs Attachments:
- 1. 10 CFR 50.46 Report
- 2. 10 CFR 50.46 Report Assessment Notes
Attachment 1 Clinton Power Station, Unit 1 10 CFR 50.46 Report Page 1 of 2 PLANT NAME: Clinton Power Station, Unit 1 ECCS EVALUATION MODEL: SAFER/GESTR - LOCA REPORT REVISION DATE: 10/29/10 CURRENT OPERATING CYCLE: 13 ANALYSIS OF RECORD Evaluation Model Methodology: The GESTR -LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident; Volume III, SAFER/GESTR Application Methodology, NEDC-23785 PA, Revision 1, General Electric Company, October 1984.
Calculation: Clinton Power Station, SAFE R/G ESTR-LOCA Analysis Basis Documentation, NEDC-32974P, GE Nuclear Energy, October 2000.
Fuel: GE 14 Limiting Fuel: GE 14 Limiting Single Failure: High Pressure Core Spray (HPCS) Diesel Generator Limiting Break Size and Location: 1.0 Double Ended Guillotine of Recirculation Pump Suction Piping Reference Peak Cladding Temperature (PCT): 1550°F
Attachment 1 Clinton Power Station, Unit 1 10 CFR 50.46 Report Page 2 of 2 MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated November 13, 2000 (See Note 1)
APCT = 0°F 10 CFR 50.46 report dated November 08, 2001 (See Note 2)
APCT = 5°F 10 CFR 50.46 report dated November 05, 2002 (See Note 3)
APCT = 35°F 10 CFR 50.46 report dated November 05, 2003 (See Note 4)
APCT = 5°F 10 CFR 50.46 report dated November 05, 2004 (See Note 5)
APCT = 0°F 10 CFR 50.46 report dated November 04, 2005 (See Note 6)
APCT = 0°F 10 CFR 50.46 report dated November 03, 2006 (See Note 7)
LPCT = 0°F 10 CFR 50.46 report dated April 19, 2007 (See Note 8)
APCT = 6°F 10 CFR 50.46 report dated November 02, 2007 (See Note 9)
APCT = 0°F 10 CFR 50.46 report dated October 31, 2008 (See Note 10)
APCT = 0°F 10 CFR 50.46 report dated October 30, 2009 (See Note 11)
APCT = 0°F Net PCT 1601 OF B. CURRENT LOCA MODEL ASSESSMENTS None (Note 12)
APCT = 0°F Total PCT change from current assessments Y-APCT = 0°F Cumulative PCT change from current assessments APCT I = 0°F Net PCT 1601 °F
Attachment 2 Clinton Power Station, Unit 1 10 CFR 50.46 Report Assessment Notes Page 1 of 3 NOTES:
- 1. Prior LOCA Model Assessments The referenced letter reported a new analysis of record for Clinton Power Station (CPS).
[
Reference:
Letter from M. A. Reandeau (AmerGen Energy Company) to U.S. NRC, "Report of a Change to the ECCS Evaluation Model Used for Clinton Powe r Station (CPS),"
dated November 13, 2000.]
- 2. Prior LOCA Model Assessments An inconsistent core exit steam flow was used in the pressure calcul ation in the SAFER code when there is a change in the two-phase level. The incorrect calcul ated pressure may result in premature termination of ECCS condensation and will impact the second peak clad temperature (PCT). GE evaluated the impact of this error and determined that the impact is an increase of 5°F in the PCT. This error was reported to the NRC in the referenced letter.
[
Reference:
Letter from K. A. Ainger (Exelon Generation Company) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Chang es and Errors for Clinton Power Station," dated November 8, 2001.]
- 3. Prior LOCA Model Assessments In the referenced letter to the NRC, the impact of the Low Pressure Coolant Injection (LPCI) and Low Pressure Core Spray (LPCS) minimum flow valve flow divers ion was reported and was found to have a 0°F impact. Also in the referenced letter GE LOCA errors were reported all of which had a 0°F PCT increase except for a SAFER Core Spray sparge r injection elevation error that resulted in a 15°F increase in the PCT. The Extended Power Uprate (EPU) has resulted in an increase of 20°F in the PCT. The EPU was implemented in Cycle 9 Reload.
[
Reference:
Letter from Patrick R. Simpson (Exelon Generation Comp any) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Mode l Changes and Errors for Clinton Power Station," dated November 5, 2002.]
- 4. Prior LOCA Model Assessments In the referenced letter to the NRC, the impact of an error found in the initial level/volume table for SAFER was reported. The level/volume tables were generated with incorrect initial water levels. This resulted in an incorrect volume split in the nodes above and below the water surface, and incorrect initial liquid mass. This error resulted in a 5°F increase in the PCT for all fuel types (i.e., GE 10 & GE14).
[
Reference:
Letter from Patrick R. Simpson (Exelon Generation Comp any) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Mode l Changes and Errors for Clinton Power Station," dated November 5, 2003.]
Attachment 2 Clinton Power Station, Unit 1 10 CFR 50.46 Report Assessment Notes Page 2 of 3
- 5. Prior LOCA Model Assessments In the referenced letter to the NRC, the impact of a GE postulated new heat source applicable to the LOCA event was reported. This heat source is due to recom bination of hydrogen and excess oxygen drawn into the vessel from containment during core heatup. The PCT impact for all fuel types was 0°F and the effect on local oxidation was neglig ible.
[
Reference:
Letter from Patrick R. Simpson (Exelon Generation Company) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated November 5, 2004.]
- 6. Prior LOCA Model Assessments In the referenced letter to the NRC, the impact of the 24-month cycle operation was reported.
The evaluation determined that the LOCA analysis of record was performed with bounding assumptions and hence is not impacted with the 24-month cycle.
A 0°F PCT impact was assigned.
[
Reference:
Letter from Patrick R. Simpson (Exelon Generation Company) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated November 4, 2005.]
- 7. Prior LOCA Model Assessments In the referenced letter to the NRC, the impact of the top peak axial power shape on the small break LOCA was reported. The impact of the top peak axial power shape on the licensing basis PCT was 0 °F for GE 14 Fuel for CPS.
[
Reference:
Letter from Kenneth M. Nicely (Exelon Generation Company) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Chang es and Errors for Clinton Power Station," dated November 3, 2006.]
- 8. Prior LOCA Model Assessments In the referenced letter, the impact of the core shroud repair on the PCT was reported to the NRC. The leakage flows through the repair holes result in slightl y increased time to core recovery, following core uncovery. The effect has been conservativ ely assessed to increase the PCT for the limiting LOCA by less than 6 °F.
[
Reference:
Letter from Patrick R. Simpson (Exelon Generation Company) to U.S. NRC, "Updated Annual Report of Emergency Core Cooling System Evalu ation Model Changes and Errors for Clinton Power Station," dated April 19, 2007.]
Attachment 2 Clinton Power Station, Unit 1 10 CFR 50.46 Report Assessment Notes Page 3 of 3
- 9. Prior LOCA Model Assessments In the referenced letter, Exelon submitted to the NRC the annual 10CFR 50.46 report for 2007.
There was no LOCA model assessment for the Clinton LOCA analys is.
[
Reference:
Letter from Jeffrey L. Hansen (Exelon Generation Company) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated November 2, 2007.]
- 10. Prior LOCA Model Assessments In the referenced letter, Exelon submitted to the NRC the annua l 10CFR 50.46 report for 2008.
There was no LOCA model assessment for the Clinton LOCA analys is.
[
Reference:
Letter from Jeffrey L. Hansen (Exelon Generation Company) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 31, 2008.]
- 11. Prior LOCA Model Assessments In the referenced letter, Exelon submitted to the NRC the annual 10CFR 50.46 report for 2009.
There was no LOCA model assessment for the Clinton LOCA analys is.
[
Reference:
Letter from Jeffrey L. Hansen (Exelon Generation Company) to U.S. NRC, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station," dated October 30, 2009.]
- 12. Current LOCA Model Assessments Since the last annual report (see Note 11), no vendor notifications of Emerg System (ECCS) model error/changes that are applicable to Clinton have ency Core Cooling been issued. No ECCS-related changes or modifications have occurred at Clinton that affects the assumptions of the ECCS analyses. Eight Isotope Test Assemblies (GE14i ITA) were loaded in to the cycle 13 core, all the GE14 10CFR50.46 errors are applicable to the GE14i ITA and the PCT for GE14 fuel remain applicable for GE14i ITAs.