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MONTHYEARML0517200622005-06-21021 June 2005 Forthcoming Closed Meeting with Exelon Generation Company and Westinghouse Electric Company to Discuss Proprietary Information Related to Request for License Amendment Supporting Transition to Westinghouse Fuel Project stage: Meeting ML0519303152005-06-30030 June 2005 June 30, 2005, Closed Meeting Handouts Project stage: Meeting ML0517503642005-07-0505 July 2005 7/5/05, Dresden and Quad Cities - Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 Project stage: Withholding Request Acceptance ML0519303142005-07-18018 July 2005 Summary of Closed Meeting with Exelon Generation Company and Westinghouse Electric Company to Discuss Proprietary Information Related to Request for License Amd Supporting Transition to Westinghouse Fuel Project stage: Meeting ML0533400992005-12-0808 December 2005 RAI Regarding Transition to Westinghouse SVEA-96 Optima2 Fuel Project stage: RAI ML0606203682006-01-26026 January 2006 Attachment 3 (Technical Specifications) and 4 (Affidavit and Non-Proprietary Version of Attachment 2 to Exelon Letter Dated January 26, 2006) Project stage: Other RS-06-009, Letter, Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel2006-01-26026 January 2006 Letter, Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel Project stage: Request ML0606203672006-01-26026 January 2006 Attachment 1 to Exelon Letter Dated January 26, 2006 Project stage: Other RS-06-018, Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel2006-01-31031 January 2006 Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel Project stage: Request RS-06-043, Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel2006-03-23023 March 2006 Additional Information Supporting Request for License Amendment Regarding Transition to Westinghouse Fuel Project stage: Request ML0607303242006-03-29029 March 2006 Company Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0609705192006-04-0404 April 2006 Technical Specifications, Transition to Westinghouse Fuel and Minimum Critical Power Ratio Safety Limits Project stage: Other ML0607502582006-04-0404 April 2006 License Amendments, Transition to Westinghouse Fuel and Minimum Critical Power Ratio Safety Limits Project stage: Other ML0619400202006-07-0707 July 2006 2006/07/07-Oyster Creek - Additional Information Concerning FSAR Supplement Supporting the License Renewal Application Project stage: Supplement RS-06-107, Clarification Regarding Backup Stability Protection Methodology2006-07-25025 July 2006 Clarification Regarding Backup Stability Protection Methodology Project stage: Other RS-07-004, Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and Divom Correlation2007-01-10010 January 2007 Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and Divom Correlation Project stage: Other RS-07-167, Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and Divom Correlation2007-12-17017 December 2007 Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and Divom Correlation Project stage: Other RS-08-020, Supplemental Information Concerning Backup Stability Protection Methodology2008-02-18018 February 2008 Supplemental Information Concerning Backup Stability Protection Methodology Project stage: Supplement 2006-03-23
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Category:Letter type:RS
MONTHYEARRS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 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-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b 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-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location RS-23-034, Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program2023-02-0202 February 2023 Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program 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-23-033, Request for Exemption from 10 CFR 2.109(b)2023-01-27027 January 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request RS-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023 Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves RS-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair2022-12-14014 December 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair 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-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-119, Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval2022-10-31031 October 2022 Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022 Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage 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-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-102, Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times2022-08-18018 August 2022 Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022 Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel 2024-01-03
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Exelem,,
Lxelon Generation 4300 Winfield Road www.exeloncorp.com Nuclear Warrenville. IL 60555 RS-07-167 December 17, 2007 U . S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos . 50-254 and 50-265
Subject:
Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and DIVOM Correlation
References:
(1) Letter from Patrick R . Simpson (Exelon Generation Company, LLC), to U . S.
NRC, "Request for License Amendment Regarding Transition to Westinghouse Fuel," dated June 15, 2005 (2) Letter from Maitri Banerjee (U. S. NRC) to Christopher M. Crane (Exelon Generation Company, LLC), "Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 - Issuance of Amendments re: Transition to Westinghouse Fuel and Minimum Critical Power Ratio Safety Limits (TAC NOS. MC7323, MC7324, MC7325 and MC7326)," dated April 4, 2006 (3) Letter from Patrick R. Simpson (Exelon Generation Company, LLC), to U. S.
NRC, "Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and DIVOM Correlation," dated June 20, 2006 (4) Letter from Kenneth M. Nicely (Exelon Generation Company, LLC), to U. S .
NRC, "Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and DIVOM Correlation, " dated January 10, 2007 (5) Letter from Patrick R. Simpson (Exelon Generation Company, LLC), to U. S.
NRC, "Oscillation Power Range Monitor Instrumentation Plant Specific Scram Setpoints and DIVOM Correlation," dated July 2, 2007
U. S. Nuclear Regulatory Commission December 17, 2007 Page 2 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to Renewed Facility Operating License Nos . DPR-19 and DPR-25 for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, to support the transition to Westinghouse SVEA-96 Optima2 fuel . This request was subsequently approved by the NRC in Reference 2.
As part of the review of Reference 1, the NRC requested EGC to provide plant specific values for the Oscillation Power Range Monitor (OPRM) scram setpoints and the Delta Critical Power Ratio/Initial Critical Power Ratio Versus Oscillation Magnitude (DIVOM) correlation for the next unit cycles, when they become available. The requested values for DNPS, Unit 2 are now available and are provided below.
A DNPS, Unit 2 specific analysis was performed to determine a DIVOM curve that is applicable to Cycle 21 . The DIVOM analysis was performed using NRC approved methodologies and was based on limiting conditions during the operating cycle . The stability analysis was performed for the power/flow state point, corresponding to a post two-pump trip condition at 26% rated core flow along the licensed upper boundary of the power flow map. The limiting exposure condition was identified and utilized to bound the entire operating cycle. A limiting DIVOM curve for DNPS, Unit 2, Cycle 21, was developed. The limiting DIVOM curve is bounded by a slope of 0.44. However, a more conservative DIVOM slope of 0.45 was selected for application in the OPRM Trip Setpoint calculations .
A calculation of the OPRM Amplitude Trip Setpoints (Sp), and associated OPRM Confirmation Count Trip Setpoints (Np) , was performed. The OPRM trip setpoints are a function of the calculated DIVOM curve and the cycle specific Operating Limit Minimum Critical Power Ratio and Safety Limit Minimum Critical Power Ratio.
Based on the Cycle 21 cycle-specific parameters and the conservative DIVOM slope of 0.45, the required Sp was determined to be 1 .18. The associated NP was determined to be 18.
This letter concludes EGC's transmittal of plant specific values for the OPRM scram setpoints and DIVOM correlations as requested by the NRC for DNPS, Units 2 and 3, and QCNPS, Units 1 and 2 (References 3, 4, and 5 for 02C19, D3C20, Q1 C20, respectively) . There are no regulatory commitments contained within this letter .
Should you have any questions or require additional information, please contact Michelle Yun at 630-657-2818.